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REGULAT# INFORMATION DISTRIBUTION STEM (RIDS)
ACCESSION NBR.:7812130145 DOC.DATE: 78/08/10 NOTARIZED-: NO FACIL:50-331 DUANE ARNOLD, IOWA ELECTRIC & POWER Co.
AUTH.NAME AUTHOR AFFILIATION PARDUE,L.W. IA ELEC LIGHT & PWR
* RECIP.NAME RECIPIENT AFFILIATION
DOCKET # 05000331
SUBJECT: -"Stress Rept Recirc.ulation Inlet Nozzle Safe End Replacement at Duane .Arn-old Nuc Plant.-" Incliprimary stress analysis, thermal analysis & primary plus secondary stress analysis.
DISTRIBUTION CODE.: A001S COPIES RECEIVED:LTR - ENCL SIZE TITLE: GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC
N TES-:
ACTLON:
INTERNAL:
RECIPIENT ID CODE/NAME
05 BC
0 1 12 15 17 19 21
REG FILE I&E CORE PERF BR ENGR BR PLANT SYS BR EFLT TRT SYS
COPIES LTTR ENCL
7 7
.1 2
I1
.1
.1 2
RECIPIENT ID CODE/NAME
02 NRC .PDR 14 HANAUER16 AD SYS/PROJ 18 REAC SFTY BR 20 EEB 22 BRINKMAN
CfPIES LTTR ENCL
0II II
.I 11
S1
.1EXTERNAL- 03 LPDR * 23 ACRS
0
TOTAL NUMBER OF COPIES REQUIRED: LTTR
I . I 16 16
04 NSIC
38 ENCL 38
C8I NUCLEAR COMPANY
STRESS REPORT
RECIRC INLET NOZZLE
SAFE END REPLACEMENT
DUANE ARNOLD NUCLEAR PLANT
CBIN CONTRACT NO. 8-CN245
DM0- 206CLH
1
C31 NUCLEAR COMPANY
Stress Report Certification
As a Professional Engineer experienced in pressure vessel
design and registered in the State of Tennessee with License
No. 7486 and using the Certified Design Specification, General
Electric Document DC22A5645, Revision 2 as the basis-for
design, I do hereby certify that: I have reviewed the stress
report for the Replacement Safe End and Sleeve Adapter for
the Recirculation Inlet Nozzle of the Duane Arnold Reactor.
Vessel, CBIN Contract No. 8CN245 and have found that except
as noted below it properly and completely reconciles the
requirements of Article 4, ASME Boiler & Pressure Vessel
Code, Section III, 1965 Edition with Addenda to and including
Summer 1967.
As permitted by Paragraph 4.6.1 of General Electric Design
Specification 22A5645, Revision 2, the isimplified elastic
plastic analysis provisions of NB3228.2 of ASME Section
III, 1977 Edition including Summer 1977 Addenda were used
in the stress report. The 1965/Edition of ASME Section
III, including Addenda to' and including Summer 1967, does
not contain provisions for simplified elastic plastic analysis.
Signed ~z~ &.c2~ -. ouis W. Pardue Tennessee Certificate No. 7486
Dated 96: * /0 ,78
CSI NUCLEAR COMPANY
qW Table of Contents
Stress Report Certification
Table of Contents
Introduction
Summary of Results
Primary Stress Analysis .8
Design Information D8-/ Safe End Configuration D8-Z Model for Program 948 D8-3
Input to Program 948 D8-4
Membrane Stress Intensity D8
Output from Program 948 D8- 7
+ BStress Category D8-fc(
Model for Program 781 D8- Z5
+ BStress Intensities D8-2
Torsion Check D8-37Boundary Conditions for Program 781 Ds- -3
Computer Output from Program 781 DS
Thermal Analysis T8-' Thermal Model T8-/
Geometry TS-2.
Material Properties T8-3
Selection and Description of Significant
Thermal Transients TS-2 3
Thermal Boundary Conditions T8-2q
Selection of Critical Times for Thermal
Stress Analysis TS-35
Primary Plus Secondary Stress Analysis SS-i
Stress Sections S8-4L
Summary of Stress Intensity Ranges S8-6
Piping Loads S8-6
Mechanical Load Cases S8-6
S~.1OJCC T CN^;aGC C O.a
It,~ e CAT
CSI NUCLEAR COMPANY
Scaling Factors for Mechanical Loads S8-/Z Evaluation of Torsional Moment Mz 58-13 Thermal Ratcheting Check S8-/4 Tabulated Stress Component Results SS-/6
Fatigue Analysis Fg-/ Summary of Fatigue Usage Factors P8Stress Concentration Factors F8-3 Fatigue Families Fs-7 Tabulated Detailed Fatigue Analysis Results F8-9
Appendix A Computer Printouts
Appendix B - Computer Program Writeups
Appendix C3 - Thermal Analysis Guide
Appendix CS - List of References
WACC b. a T C AAGS
S u J C IM 0 7 1 ,P 2 ? .* AGL I SOO
C81 NUCLEAR COMPANY
Introduction
This report documents a thermal, stress and fatigue analysis of a recirculation inlet nozzle replacement safe end and adapter. The analyses are performed in accordance with Design Spec 122AS645 (Reference 1) and Article 4 of ASME Boiler and Pressure Vessel Code, Section III, 1965 Edition with addenda through Summer 1967 (Reference 2). Use is also made of the simplified elastic plastic analysis rules
of NB3228.2 of the 1977 ASME Code as permitted by Paragraph 4.6 of the Design Spec.
1A TAY a~ S CNaG car
1Wej IC T
7 3 A e I
* . - -. -CBI NUCLEAR COMPANY
.~. _7. Locatior,_ _ __ _ _ _
caC /-a~/# Y6- li e
V7L.AIw~~e eee~~
0.3 F3 --
Pm ~ By CHARGE NO. I AI CTE tJCXI(D
?/7 e 4EST O
SUBJECT
G064 CSINC
CSI NUCLEAR COMPANY
DUANE ARNOLD
RECIRCULATION INLET NOZZLE
SAFE END REPLACEMENT
Replacement to the 1965 ASME Boiler and Pressure Vessel
Code including the Summer of 1967 addenda
Design Pressure............... ............
Flow Path Pressure.............. ...............
Design Temperature ........
Material for Safe End. ............... ....
Material for Thermal Sleeve Stub..... ...... .....
k"~ my 4L ar sw- NBy AA6 Pt.Y I-- 8-N
OAT smi O4r
stUoiC cc
Womm,
SAFE END CONFIGURATION
CSI NUCLEAR COMPANY
0
___ ___ ___ ___ ___ ___ ___ ___ ___ ARE 31Z LC ~ A 4 CAc 7E CApZ m C-Ke
7/13/78 8 -8-78 0*.o
MODEL FOR PROGRAM 948. S ULA OPN
In
U
0
-4
r-4
r-4
FII'dJCGC T hSov aw ft sy ~ I __________________________ARE lLP a. 8-CN245
IOAT c OATt 4E c"40
7/12 /7 8 78~ v
C31 NUCLEAR COMPANY
INPUT FOR PROGRAM 948
NT:Load= I.- "M±4ps and inch V i-s
Design pressure - 1250 psi Flow path pressure -1565 psi
-THERMAL SLEEVE LOA.DS
F~ f F y Fz M M y
M, z
DEAD WEIGHT a a 0 a 0a 0 92.5
HYDRAULIC-_. .0. 4-3.- 13'.0 a _-44.0 a. a 92.5
SEISMIC a.. 0.0_. 0 92.5
NOTE: LOA.DS IN KIPS & INCH KIPS _TSL - 24.12 -
LOAD DESIGN MECHANICAL
x
=zr F 4.3
T7 F
z z__ _ _ _ _ _ _
TM x r MV+ TSL-(P ) v -44+(24.12)(4.3)=59.72
TM~ = MY TSL (F X)-.0
= M2 0
F2 . F7 Fz Mx MYr Mz R
Design (Wt. & seismic) 1 .1I 7.3 Z.3 250 96 V. Il. 5
-NOZZLE END LOADS-
CS1 NUCLEAR COMPANYOUTPUT FROM PROGRAM 948
7 MAXn4UM MEX4BRAE STRESS INTENSITY(1PESIGN MzcaANICAL)
Sec. Loads J Ref Loads Only Ref. Total All.owable Only (PSI) Page (PSI) Page (PSI) Sm @ 575 F0
A. ljj.4 G - i !1 42I-0%
B 6937. 9 0 1.7 6937 23300
C 548 0 18 48.23300
D. 8562.- 12 336 19 8898 23300
B83.25 13 .331 210 J 8456 23300
F8139i 14 494 2. J 8633 23300
The design mechanical loads and pressure adcled.-to. the stress intensity due to the
stress intensity are. conservatively thermal sleeve loads.
~ 8-Ca45
O~~tL C~Ee sw r ov~CA 1 t
*u&~i~C r
Cal NUCLEAR COMPANYOUTPUT FROM PROGRAM 948
Ref. Design Alowable Stress .Section Page Mechanical Intensity
575 0
Ar 21 6335 23300
B' 24 8006 23300
C' 25 7543 23300
TERMAL SLEVE ANALYZED AS A NOZZLE
-MA MIM MEMBRANE STRESS INTENSITY-
vv
CRI NIUCLER COlMPA'NY
NOZES ANAIAYSIS POGRAM-ALL LOADS MECHANICAl- - \IAPAL -ZI nrg A 4 -Man Q A >?=Ntlcs Ma 3- y,
A.MP N lfAI 4 vo e cr gP Ttwf-- \ey Z I- 1077!: 000 ver
\tIAh=4 Q4 I lIArrnlN1 Tn AZ A1lI9 V7=, Nl - 3
1o i3f Z(7 norT nA!- 7.\I e .- Tarr Ir'q rn I= in- i
-ONISIDRq: 2-dN'qYZE CR INPUT LOADIN O-fNLY
'Th'd'A 3qZ' cippQ < q~ rJ, rn,* _A.\.AI v7= W TT r on-
,4E rHoUT: Z-dNdb-YZE WITHOUJT: 3-doNdtLYl7 4TH
rIT'. CoOTII\: g-rBv1-Cu iNUCEAR KrTO= 1
O4TA SH=-E=T REVISION NIUMER \OS= 2
UNITf CODJP NUMER: 1=LASZ=KIPS IUC= 1
PRESSUR (PSI) P= 15'15.
O)NST\AN.T '.0ov 0oTION: O=1\O0 1=YES IOPT= 1
NO THrNaMA' S..EEV/E, OR NO THERMAL SAEE LJAnS Apa.tlE0
TAcCr- 7i AT 'jHTfH T- AAXT!i1 ' q7 cqq Ty rjrr= r r :I
gy 5 3, S q- O ri'rraM yg AT T,4= inr* r Tu= A Y r Ai;.
STI=SS Ivris!TY
72- OISTACE PROM SAE JE1O O NOZZLE TO POINT n= ANALYSIS
)K4 0 Y Rtwr r) 4T A ) A T ET
w . ~~~~C.9 iii ,_Et4R r M'C A /fl A, \iy
i -C'I245 IJJV\E NOL)ECR.INL ET -NIZZLEP- ANAL4!YSIS
)isr. FP40OM SAFE SMD OF NOZZI-E TOi DT. OP ANIAI-YSIS
n,,1IT,; r I)
Z= 0.75
r .\I' 1'n
Q tJ N TI T Y UNITS S; R):-AC SIJR-ACE SLIRPACE
'~0: 7 -A, 4 .11
Ai 7~ r ,IjA1.11-1177( f
5O T
1;r) T- iT (TN rl= 4- Te 5 70 lm1sz ,4
lIST.~~4 r 7T -1' 'AO ~ If~l O ~ .IlCr') 7=
OU T I' EfSrim - =i NL (iN) 00= 0."7 .)!AS. l\ ;7 411 T fl C* AO)- (I' I) ~T= rn 7,1 - : 1
=-,-T CnM\T. r-Ar=
-A CN
nA
3-C'4245 DUANE ARNOLO 'lc. INLET NOZZLE 1AIA-YSS
01ST. FROM SAI=END OF NOZZ LE TO OT. OF A1NMIAIYStS Z= 2.12 IN
riitTSTOrnp N T rT M rM Aq AIP
Q J 4 NTITY UNrTS SIJ7A: Si JRC SA1j1A'-E
xart'.fq ;TU _, TNT N;TTY 14 o rA70 of, 7
rH=T nequ
X I -1100, -r"V , R14;
riFA; 7-200 7100, 71n11
7 -AA tin 20 7
AO TN-IO -79tmnnr -2:z(In -7)0= 00
MY Thita QrA Qnn in
M .7 -NIJf RI; T- fl Q'\ -I7 07fl -67000
;'), [NTR~E (PRF RE) o; *:on 1O, T
10 V ficKS(4XNa TN080) o(TN) As= ra 0JNG. --m G g 'NT aOU TS TE I" 01 7C y >o
S H;PAR STRRSi(FQGfgeS TQRC.TnN) T9 s,50,Gv
c1 T9 ST7R =s S aR1rf y7 , c3R
53 o 1;T r,-7 4, 7 2
T~Se:# T 0=M Tnpa Tt v inA=i= Tos cng - -- r)= 4
00NST~ I,-)= 1) 1 T'In7= o I .qin
OTST, P-70M DT, MF APPi-, n= in-AnS Tn qApp PNin (rN) 7r= -1,.450
,1-dO), CNs IOR ONI-Y ( { ) .- I- = f. :04405fnIN V-n1 NC TAIR1TiOr- (TNI) r-A T= nr)
CORO IO ALO AN EOt)TSriOE;( IN) C0= 1 . .
SUBJECT r) NT. '"ATE &ial -1 Y CHC j SY RLf A T g-,Q7,e4=1 , 1-) A TE P RT
CBT NUCLEAR COMPANY
'8-C\245 DUANE ARNOI.0 RECIRC. INLET NIOZZLE ANAL.YSIS
oisr. Pr=oM SAFE -'\O OF NGZZL-E TO PT. OF ANdYSTS Z= 2.74 IN
ofitIT,; o rI=rS n= m =4 :?4 1= Q U A N T I T Y UNITS SIJRFAC SURFACE SURFACE
-- ~~- -------a .a.*. . .a . .a...aa.. . .a. a
M4AXT,'4M S;TR=r," rTNla rYv o0 1; r,7
T7 T q1
-X 71TT . -1IT - -;,1 1
v-7 19 7'A fl , 7 -Au 7 -A01
A 7 IA$ 730 7r 70 ,47 TN-1 A S -71 f0 , -710100 -7nnl
7 TM-IR -S70 , -q D r ig-&.
.?\I , STR l;( AX r ra n) aC; T T 74
0ST T1.\ nrmG orG, oT4 Sf tETETING) .D= 4 r -a' i7 r 57 1; 0i 1; * ;11-4 rn Z r -270-7- q -A 7 7,3
sy~1 a r '42 - A , 7 :j
TST F) ad T1) (N) rnMT= E 0. OUTSI DE r)I AMETER (I N) 00D= 12.4q4
O Sr. =R .A OT. OF APps. Qf agacry( Dp 7a --I 7s) 7= .~ o
CL:, ISIOr: ON'Y ( IN ) .Cl= 0.0
i r)3r nfN i i A.in yre a y\j, n r mfv er= 10 -'RROSION A.LOWANIE OUTSIDE(IN) CaO= 0.0
SU0J T CONT. nATE & & & Ay -4 0 Y F2 LPt )AT R-,4-194= A n, CAy -AT .T= q t
a at. i r oz Q qc%/TSrn MAY 10-74
MIA~~fl r- fl Ap-Nini r fl QriT r TI- lZ Ir AMAI V7S
1; 0,=r7 rII I rl .10T r , 0T fl rfl M l-.lrl q:CrT;Tr I nlAr-l.r. Tnl Qir I fl- I J~S )'.~: 2-4,\1L-Y7- i~r)% E NPUT '-0fAI) ENJM;.-lfY
I fl.'T, O=fI;LS nOTTnNim- 't-m -Z' k.i;,r-u ,%mr
rt1r-4i~ ITr~~ 2 -cNu-Y c fTor: 3;tC-A~ ar) I-YZ1r
r t ri-i r - E ItJ I'M~- C - 4 R = 2
A rA .H -Or 4 - IJi si .1 i mi E=3,4Z=NItPSES= 2
~-~SiJV~( 0S1 . ~1 ?:5.3.
r-.JirAq A!.\P( D 0A T 'ION:( 0=1\1 IAAV.'AU !OPT=I rNT M1
I - q - c ~t r o "IrT0%I (~=Z = AT Tt-= I fl(Ar~r1NI r= -,L AAX 'Z r f" '
Sr-llzSS PliNSIT
Z-~s ciIITE*NsTr nTiT0 rYYc
(INIJCIUj! rrJOMPA\JY
OUANE;24 4)R~ 'NjI.~lD RE-,A ' i~T \107-l_;:.. A\IIYST S
=-Tf~ Si \5() OF- :.OZ- TO OT. OF-4R\, AAY S IS Z= 3.3 8 1 NI
-- ~-- IT I; T -)r Ti,, T n- rg- - -
SrMA,.94 TNTP.\ISTTY 1 - 7 C; 07c, T- q rA2
r,-4 r nq.: ~
Ck It -t 72rm'I
4t X TNM-I Ck: OAcmnl 2 M
rA 7; 'A- :j7t =7n- 0
QSV7 1;7 ;n'i-,7 ;7 .
1; 4~ N! n T Nl r,. Ot T 7A--.-- -- --
T5~ 4 f.. 7R 5 1; R S!I l Cf~f~ Tf 5I T \f 714,,1- 7l m1 77A.
rL N1,; r--7 T ,Itn a fTfIT r)Z
CSI NUCLEAR COlMP4NY
d-CN245 OIJNE ARNOL-D REC.IRC. INLET NlZZLE lNA'-YSIS
OIST, FROM SPE-. END OF NOlZZLE TO T.. OF ANALYSTS Z 3.51r IN or=gilv= o= 1 9 0 oT
r0 q T,
asl Tq Trn) rac rn= .a y U A N T I TY UN IrTS SUIRFACE SURACE SU.RFACE
AAXTAIRAJM ST-U= rlFN'R-FP'IY o 4
T, T a a q:44R 0 Th-~-T T n-I
-Ax -1111 -TO 10
Z7 qFRr rm=n Nt-A ; zz
TMN-)a qAA qAA Q1 na
TMS3 -0A 570 -70 *** 7T4 - ( 1; i 1IA r -) a I r -;-- avA, R , Aqo (J r r 7r i)e 1; z T- ( I Iana r s q 0 97 orr 42 C, r rlNI1
ORT~ 1 T7 5 -7
f[\Sloi OfsM iTER (TMI) rn= IT I n OUTSIaE OlE.ErER (IN) 00=. 13.12P O)fsT, =qfj aT, 0F Pppi rip tnan,; rn qA;== (fy) 7n= -7 5-vl
CLAO. INSIO ONLY (IN) .CL= . OAQSTON is , OwAes T nTf= ( TM i r= O40 S1-I V- LLO ANCE OUJTSIDE( IN ) CAO= 0
SJ CTj CNT. DTY a, <:j0 r v 9i 0y T g-R-79 4\v,\in, Av yIM7= ur (
i- 1245 'J~NE A1NOLF) jEC-IrC. INLET IoZZltCE 4NdtYSIS
JEST. ROi SAFE-5NO ON OZ7LE TO T. OP aNtlYSIS Z= 3.'4 1 M DQC i HQ 0= 1717i 0 O T
Q U A N TE T Y UNITS SR ZAC SUJ AGE SUZRFPC
AdIXTMil (T S TM1Ty.INTTY o 7n4 o3 gym
1-x-1 -11c= r1A
7 7A 7
T.11-lR ql 7 qnnnn400 qno
7 TM-l ql0 -AA7AA onnn
, N;, rTR q5 9 49 14 st A9 9 X>s T nPo.T l
LQRNG T s nn ; Tr S q; Iq14n4
HOG ST5(AeynC G r.t u T. &07.
CT 1!, RTR 13 foA 51;1 ); = T A71TA 703 t, A I
1 T 7"K 7cyz
ST o:T 4
53 4Z T , 0_ s
Hi0A : InrAn ocr01
6O1UTs i E Ol E E (1 A E- TO C-.3.120 r)TST , flRO , T i f p Apps - a I n A g rn rAF: \in (T ',1 7
E0 "\IS ID 1)- 3 \ Y (I-N) . = Im. f-1-R1rSTN1TI N I n w Am rr- T\iqTnr ( TM) A OOOTS0IO 1 ) )4= 1.
S 13 J a,- T T ')17 A T b y <= A Y RLA T=Z N--7 ~n, y 0\7 Ta qwT
CB NUCLEAR COMPANY
NOZZLE ANALYSIS PROGRAM-ALL LOADS MECHANICAL - NAPALM PROGRAM NO. 948 REVISED MAY 1974
8-CN245 DUANE ARNOLD NOZZLE ANALYSIS
NUMBER OF LOCATIONS TO BE ANALYZED NL= 6
SPECIAL LOADING OPTION: 1-NO SPECIFIC LOADING TO BE LO= 2 CONSIDERED: 2-ANALYZE FOR INPUT LOADING-ONLY
LONG. PRESSURE STRESS OPTION: 1-ANALYZE WITH AND LPO= 3 WITHOUT: 2-ANALYZE WITHOUT: 3-ANALYZE WITH
TITLE OPTION: O-CSIPt-C8I NUCLEAR KTO= L
DAFA SHEET REVISION NUMBER NOS= 2
UNIT-CODE NUMBER: 1=LBS2=KIPS IUC= L
PRESSURE (PSI)- P= 0.
CONSTANT LOAD OPTION:- O=NO 1=YES IOPT= 0
IST. FROM SAFE END OF NOZZLE TO THERMAL SLEEVE (IN) 3.38
THERMAL SLEEVE LOADS APPLIED WHEN (Z) rS-GREATER THAN OR EQUAL TO (R)
TFX= 04, LBS TFY= 4300. LBS TFZ= 13000 LBS TMX= 59720. IN-LBS TMY= 0. IN-LBS TMZ= 0. IN-LBS
TERMS USED
THETA- ANGLE AT WHICH THE MAXIMUM STRESS INTENSITY OCCURS
S1, S2, S3- PRINCIPAL STRESSES AT THE LOCATION OF THE MAXIMUM STRESS rNTENSITY
Z- DISTANCE FROM SAFE END OF NOZZLE TO POINT OF ANALYSIS
K.AJBJECT bvANje ARtJoLh gir- .tNLt CONT.9-<:N1450ATE 7-14-78 BY A2e CHECKED BY D OATE -a-7 REV.NO. BY OATE SHT IS
CB NUCLEAR COMPANY
8-CN245 DUANE ARNOLD NOZZLE ANALYSIS
DIST. FROM SAFE-END OF NOZZLE TO PT. OF ANALYSIS Z= 0.75 IN PRESSURE P= 0. PST
OUTSIDE INSIDE MEMBRANE Q U A-N T r T Y UNITS SURFACE SURFACE SURFACE
MAXtMUM STRESS INTENSITY PSI 0. 0. 0.
THErA DEGREES 0. 0. 0.
FX LBS 0. 0. 0.
RY LBS 0. 0. 0.
FZ LBS 0. 0. 0.
MX IN-LBS 0. 0. 0.
MY TN-LBS 0. 0. 0.
mZ.-IN-LBS 0. 0. 0.
-ONG, STRESS(PRESSURE) Psr 0.
LONG, STRESS(AX14A-I QAD) PSI 0,. 0- 0
LONG. STRESS(BENDING) PST 0, 0. 0
SHEAR STRESS(FORCES + TORSION) PST 0- 0. 0,
CrRC. STRES5(PRESSUREF Psr 0. 0, fi,
Si. PST 0. 0..0.
S2 PSI 0. 0, 0.
S3 -PSI 0. 0x 0.
**THERMAL SlEEVE LOADS APPLIED WHEN Z IS GRFATFR THAN OR FQUAL TO R*
[NSEDE DEAMETER (IN) I0= 9,470 OUTSIDE DIAMETER (IN) OD= 10.870 DIST. FROM PT. OF APPL. OF I-OADS TO SAFE END (IN) ZO= -1.500 CLAD, INSIDE ONLY (IN) CL= 0.0 CORROSION 4..OWdNCE INSIDE (IN) CAT= 0.0 CORROSION ALLOWANCE OUTSIDE(IN) CAO= 0.0
SUBJECT 'bvte- Ad d)LA Adc< 2w&es' CONT.S5Z450ATE 7-1I -7S By4AE CHECKEQ BY If- DATE J-2--78 REV.N. BY DATE SHT /472
CBI NUCLEAR COMPANY
8-CN245 DUANE ARNOLD NOZZLE ANALYSIS
DIST. FROM SAFE-END OF NOZZLE TO PT. OF ANALYSIS Z= 2.12 IN PRESSURE P= 0. PSI
nUTSTF T NST1F MPMARANF Q U k N T I T Y UNITS SURFACE SURFACE SURFACE
MAXIMU4 STRESS INTENSITY -PST , 0. 0,
THETA DEGREES 0. 0. 0.
FX Las 0. 0, 0
PY LBS 0. 0. 02
F LBS 0. 0. 0.
MX TN-LBS 0. 0. 0.
MY TN-LBS Or 0. 0.
MZ tN-LBS 0.. 0. 0.
WONG. STRE SSURER PST' 0. 0. 0.
LONG. STRESS(AxIAL LOAD) PST 0. 0. 0.
LONG. STRESS(BENOING) PSI 0. 0. 0.
SHEAR STRESS(FORCES + TORSION) PST 0. 0. 0.
CTRC. STRESS(PRESSURE) PST 0. 0. 0.
SI Psr 0. 0. 0.
52 Ps T 0. 0.
S3 PST 0. - 0. 0n
**THERMAL SLEEVE LOADS APPLIED WHEN Z TS GRFATFR THAN OR EQUAL TO *
INSIDE DIAMETER (IN) JD= 9.470 OUTSIDE DIAMETER (IN) 00= 11.986 DIST. FROM PT. OF APPL. OF LOADS TO SAFE ENO (IN) 70= -1.500 CLAD INSIDE ONLY (IN) CL= 0.0 CORROSION ALLOWANCE INSIDE (IN) CAT= 0.0 CORROSION ALLOWANCE OUTSIDE(IN) CAO= 0.0
SUBJECT teA)e A1200" ;rc.T CONT.8-c-z 4 5 DATE 7 BY AR41 CHECKED BY ELP DATE.-R-9REV.NO. BY DATE SHT-/7
C81 NUCLEAR COMPANY
8-CN245 DUANE ARNOLD NOZZLE ANALYSIS
DIST. FROM SAFE END OF NOZZLE TO PT. OF ANALYSIS Z= 2.74 IN PRESSURE P= 0. PST
OUTSIDE INSIDE MEMBRANE 0 U A N T I T Y UNITS SURFACE SURFACE SURFACE
*********** ******************* ***** <*t****~ ****** ******
MAXIMUM STRESS INTENSITY PSI 0. 0. 0.
THETA DEGREES 0. 0. 0.
FX LBS 0. 0. 0.
FY LBS 0. 0. 0.
i- z LBS 0. 0. 0.
MX IN-LBS 0. 0. 0.
MY IN-LBS 0. 0. 0,
ME IN-LBS 0. 0. 0.
!LONG. STRESS(PRESSURE) PST 0. 0, 0.
LONG. STRESS(AXIAL LOAD) PSI 0 0. 0.
LONG. STRESS(BENOING) PSt 0. 0. 0.
SHEAR STRESS(FORCES + TORSION) Psr 0. 0. 0.
CTRC. SrRESS(PRESSURE) PSr 0. 0. 0.
S1 PSr 0. 0. 0.
52 PSI 0. 0. Q.
S3 PST 0. 0. 0.
**THERMAL SLEEVE LOADS APPLID WHEN Z IS GREATER THAN OR EQUAL TO R**
INSIDE DIAMETER (IN) ID= 9.250 OUTSIDE DIAMETER (IN) OD= 12.494 DIST. FROM PT. OF APPL. OF LOADS TO SAFE END (IN) ZO= -1.500 CLAD, INSIDE ONLY (IN) CL= 0.0 CORROSION ALLOWANCE INSIDE (IN) CAT= 0.0 CORROSION ALLOWANCE OUTSIDE(IN) CAO= 0.0
SUBJECT Wo#pc P4zal.6 Asec. :'LT' CONT.82V'V5DATE/-(r-ls BYAt CHECKED BY9'.4 DATE2-J--78REV.NO. BY DATE SHT /A
CBI NUCLEAR COMPANY
8-CN245 DUANE ARNOLD NOZZLE ANALYSIS
DIST. FROM SAFE-END OF NOZZLE TO PT. OF ANALYSIS Z= 3.38 IN PRESSURF P= 0. PST
OUTSTOE [NSTDE M-MBRANE 9 U 4 N T I T Y UNITS SURFACE SURFACE SURFACE
MAXIMUM STRESS INTENSITY PSI 292. 333. 336.
THETA DEGREES 150, 222, Z22.
FxS 0, 0,.
FY LBS 0. 0. 0.
F ZLF3S 0. 0. 0.
MX tN-LBS 0. 0. 0.
MY tN-L8S 0. 0. 0.
K Z -TN-LBS 0. 0. 0.
WONG. STRESS(PRESSURE) PST 0. 0. 0.
LONG. STRESS(AXIAL LOAD) PST 377. 377. 377.
LONG. STRESS(BENOING) -PSr -529. -391. -423,
SHEAR STRESS(FORCES + TORSION) PSt* 124. -166. -166.
CIRC. STRESS(PRESSURE) PS- 0. 0. 0.
St PST 69, 159, 145,
- 2 PST -7 -17,;. -191.
S3 PS 0, 0. 0,
**THERMAL SLEEVE LOADS APPLIED WHEN 7 TS .REATFR THAN OR FOIAl TO R**
INSIDE DIAMETER (IN) t0= 11.200 OUTSIDE DIAMETER (IN) OD= 13.014 DIST. FROM PT. OF APPL. OF LOADS TO SAFE END (IN) ZO= -1.500 CLAO, INSIDEE ONLY (IN) CL= 0.0 C-ORROSION ALLOWANCE INSIDE (IN) CAI= 0.0 CORROSION A;LOWANCE OUTSIDE(IN) CAO= 0.0
SUBJECT DUANE ANOc-4 rease. ZM-C- CONT.Bd5-Z 4eDATE 7-f4 -7 3 By fA CHECKED BYRLP DATE R-1-78REV.NO. BY DATE SHT 1fj
CBI NUCLEAR COMPANY
8-CN245 DUANE ARNOLD NOZZLE ANALYSIS
DIST. FROM SAFE.END OF NOZZLE TO PT. OF ANALYSIS Z= 3.51 IN PRESSURF P= 0. PST
OUTSIDE INSIDE MEMBRANE Q U A.N T I T Y UNITS SURFACE SURFACE SURFACE
*************************~****** ***** ******* ****** *******
MAXIMUM STRESS INTENSITY Psr 444. 330. 331.
THErA DEGREES 246, 225, 225,
FLX tBS 0. 0. 0.
FY LBS 0. 0. 0.
F- LBS 0. 0. 0.
MX IN-LBS 0. 0. 0.
MY IN-LBS 0. 0, 0.
MZ IN-LBS 0, 0, 0.
*ONG, SrRESS(PRESSURE) PST 0. 0n 0.
LONG. SrRESS(AXTAl LOAD) PST 354, 354, 354.
LONG. SrRESS(SENDING) PSI -231, -443, -373
SHEAR STRESS(FORCES + TORSION) PSI -213. -165, -165,
CIRC. SrRESS(PRESSURE) Psr 0.. O 0.
51 . PST 284. 171. 156.
S2 PSI -161, -160. -175.
S3 PST 0, 0. 0.
**THERMAL S'EEVE LOADS APPLIED WHEN Z IS GREATER THAN OR EQUAL TO R*=
INSrDE DIAMETER (IN) TD= 11.200 OUTSIDE DIAMETER (IN) 00= 13.120 DIST. FROM PT. OF APPL. OFLOADS TO SAFE END (IN) ZO= -1.500 CLAD, INSIDE ONLY (IN) CL= 0.0 CORROSION ALLOWANCE INSIDE (IN) CAT= 0.0 CORROSION ALLOWANCE OUTSIDE(IN) CAO= 0.0
SUBJECT Dove"d iJes MAsc. qe.cb CONT. S-2"'4y DATE 7-tf-7h BY 4,z CHECKED BYrL-P DATE 8-?.78REV.NO. BY DATE SHT ZO
C8L NUCLEAR COMPANY
'8-CN245 DUANE ARNOLD NOZZLE ANALYSIS.
oisr. FROM SAFE.END OF NOZZLE TO PT. OF ANALYSIS Z= 8.44 IN" PRESSURE P= 0. Psr
OUTSIDE INSTO ME MBRANE 0 U 4 N T I T Y' UNITS SURFACE SURFACE SURFACE
MAXIMUM STRESS INTENSITY PST 720. 667. 494.
THETA DEGREES 360. 336. 249.
F X I,8 F3SO 0,
Y BS 0. 0. 0.
FL BS 0. 0. 0.
MX rN-LBS 0. 0. 0.
MY rN-LB5 0. 0. o,
MZ rN-LBS 0. 0. 0.
lt-ONG. STRESS(PRESSURE) PST 0. 0. 0.
LONG. STRESS(AXIAL LOAD) PST 354. 354. 354,
LONG. STRESS(8ENONG) PSr 365, 285, -121,
SHEAR STRESS(FORCES + TORSION) PST -0. -95, -219.,
CIRC. STRESS(PRESSURE) Psr 0. O. 0.
Sl PSt 720, 653, 36z.
S2 P1 -- 74
S3 PST 0. 0. 0.
**THERMAL SLEEVE LOADS APPLIED WHEN Z.IS GREATER THAN OR EQUAl TO R4
INSIDE DIAMETER (IN) 10= 11.200 OUTSIDE DIAMETER (IN) 00= 13.120 DIST. FROM PT. OF APPL. OF LOADS TO SAFE END (IN) ZO= -1.500 CLA0, INSIDE ONLY (IN) CL= 0.0 CORROSION ALLOWANCE INSIDE (IN) CAI= 0.0 CORROSION ALLOWANCE OUTSIDE(IN) CAO= 0.0
SUBJECT p"O'e Nawoa R xwcer CONT C DATE 7-1-72 BY AX5 CHECKED BYPLf4 DATE8-1-78REV.NO. BY DATE SHT 21
CST NlJCLE&R C.OMP4,NY
'4OZV7A' 6 Na'YS IS P4OGR4M-AI.). iLoAOS MECHAMTC41 - MAI-i'A
I fl~IlTN(1 n rnflNI: -7TP =rr- I nfl~r'e\Ir. TOl C;; i nl CONSIDE4ED: 2-ANaLE- ciO INPUT i-n' OINrp-,o"ILoY
w I rHO r: 7-AN*,I...YZE WITHOUT: 3-ANi4'-YZE WITH
;)ArA SHeer-= - E\/SIJNI N0JMRER NQ)S= 2
iU"iir cooe Num:-ER.: i=L.Fs,2=(ips TJ
P~ESSI)RE ( 01; 0 3.5
CON~SrA.-Tr3 'jj O PTION: 0=,'0 1i=y ES TORT= 1
NO ToHE-:'. S3'.EEV-VE OR \In3 1iERN460L SI-ESN/S I-JADS 4PPIOF
rH-=rA- Ami ATF ,Hrr,,- T-4; mAWMT-mu-T1MA~
ST4=eSS r~r=-NsITY
7- 131S T a,\C' r: O0M S A' i:-:9\ ) 0 r-N 0 Z Z E T0 POIN4T 0'f- 4MwIAYSIS
c Y 9~~~>T -9.784EV.Nn. R y r)" faTE SH Z" _______
CBT NUCLEAR COMPANY
8-C'245 DUANE &RNOLr RECIRC.- rNLET THERMAL SLEEVE STRESS;S
0ISr. FO! SAFE ENO OF NOZZLE TO PT. OF ANdlYSIS Z= 24.12 1\ - aq~ssn = Do= ry ,
ntITY o ll o r;) \e nm .-I , :yI= Q IJ A N 1 I T Y UNITS SURFACE SUR=ACE SURPACE
TH TA r) =i-l , Ta qr)
FXI $1. '1,,
7 pr -1 7 44 7
~4 (TN-IAR -/d&rcy0 -diA -IAAll
Y;H TN4R 7-R!-, 4z -=' nRCZrn,101
7l T - A7 7 , 'A1 0, -> 7 , ONG.- Sr~I=ggCoqESS;Jq osT 197 TRQ TR
R- 64 S7T Bf 9 + TORIT007 -1 - 1
53 !3,zr7 ,
sq ost0, -sy 7 itq
rv t \i i O T AM TE- (r-NI) r i-)= 9- 7cn 0')TSIDE DA, ETE (IN) 00= 10.250
MS r. ; - OT. Qf APP , n A ' nan -sP= \i n (r m 7-= e a CL0, INSIDE ON.Y (IN) C'= 0.0
joR srFNi A 1 1l noA m r Mc r r) im c,) =(7 A ' ORRSIO' ''.O'iCE OIJTSIOE( I') Can= 0.)
SU Ji iCT CONIT. F)AT Y Rw Y<0A R LP r)7 T -- R 9v oI A AT= ,r
CBt NUC'yda flO'~og'y
3--:N245 D'JANE A:'NOLrO RECLC. INLET THERidt SLV ST1;SSES
o tST. RO SAE ENO O NOZZI.E TO T. F 4NILYSrS Z= 22.44 TN
ni iT:y nc Tyc p NIIre 1 r oC QA \
0 IU 4 N T I T Y tJNETS 5Ji4'5 SUJ AGE SJAE
4 AXT M S T MT NT rTY T r\ 7C4, anT
-7I ca4
5AR IZ0-T -2nOO -AT
,--I~ r Xl' A T (TNHI .IC 4fl r)1 a4 M# MR -TyA TAA 17000Q 1; SI)RT - ToI 0 I gi UtM), S ) R 0A0) . D:T -1ON.1 7T(T1)T 1 T g S \ISTN r r. f( N( cTGI Ty -c5 y ( 4, 7S H; AR ';TR P 9 R C ='S +Tn9 In) I' Q NJ I Tr , ZTR= ;,{OqR - I lp )1 0< 2292 Tm -4 '1
07 DrT -fom 74A,1. - 7q
02 D;T 1&AT -A7.1 Q -.
TNls(O) lTAM =T=q (TNI) Tr-, Q - ne OUTStaE O([AMETE-3 (IN) 00= 9. qe0 rOT'T, OT.s 07 - AP O Mp t = InAncs Tri zAp= q.a n T NI> 7n= on
(.0, INSTOiE ONI-Y (1 .. 4= 0. OR7:O ri to sNe ra yn r Nj1 T.7 Pon- n CO rROS[014 kl-lO dNCEilr OUTSIDE( I N) C1A0= 0.-1
SUBJE-T r rl",T . -)AdT= J5 5 7M J3 CHECcRO A )_,fAT= 9-g-7g av ian. ARGY sy
alC I NCLEAR COMPANY
'8-C4245 DUdNE ARNO1I0 RECIRC. INLET THERMAL SLEE' STRESSES
tsr. FROM SAF- E10O TO O NIOZZ .0 PT. OF A'aL-YSTS Z= 20.06 rN
ro\11;T = o y - A =.iR 'Z
0 A N r I T Y UNITS 51RiACE - SUJRFCE SURFACE - - -- - - - - -- - -- --.4..4
T7 =1A11 q -A 0() 1 -Anil I
"Al .1 /" 01
'4 y q4
A 7
Si T R q.\1 .- 1=5 T1;Q 1X I I 7 Ty-tA q c f 1 q T T1N ONG S:. T'R 1;l_(qcOR RJ Iq AO \ 7 - ,S Rs I2 ONG, rT ed'T6 1 D n 7T 7, -Yo 7o
S3
I ON- , RTR -irr ~ M~ IPfalrA .:)Df r -g
T \StrOm 0 6 y= f r r t,= I n 117 OtUTSIoE OTAMETER (IN) nlo= 10.750
oTsr. Mf PT, O APP' mF 6 TOgi-I; rn q =rm (r) .) 7p P)
AL0 , 1IS I0 ONLY (IN) L= 0.0 ^nR R nS T rl \4 I rl d %Ir C y yp f,\,; )a f TN) I1 = -ORROtSOSI 3 1OWINCE OUTSIrE( IN) CAO= 1I.0
5 JJf-CT COMT. AdTE 5b175 y <=0 rY RfDTA 4-R-7R~ Vn my 0.17 Tr 15
(
CSI NUCLEAR COMPANY
77s-P o=776 0- Rbr - -w
cre p'tZ. Arms -414, 2 A-l AV- - 3 o 771,- COvd 7z
4.1 C, ,,z $.E. Sp~a .2 -A <'/ 4f.~ StJ(ce -n. 'o7e _ ___
A4Lg 23, 0+A*fe77/ /5-%'YAPAs / r is o,-3 s 7-7r
A/- 4/4. 2- s5 775/e-& 'K A/- 4/4(. J? C4/ &' 1 f IvA' oats a-r- co -furt 2/ s -- 7,;= /4-Y> or=r
P odz,9 77' /ss 7- - 7
CA-4. C.4.4+*es - cE=S 1,0 771,41 W 4yL zD A- 77s. s4Fe aF 'Z
o"no4 s =C 7= 7> swer. 2=&4 ,4 suFA-cZ LS7A7.s. Z7-. S
.3 e.J aw' az.-SVA-Lc. swerL 7m7Ag5/ ,4vb A7s 7nve cZw=*4S-en/r/ aF
De-rs-m7a 7:/td r er sn-r= 1e A-ed a-~ 77//d4v'(see7?, nv AVr-R AOlz 74'. 4WL .f- 1 J A 'r A5 WA-S 7-r . . 2=.rcZ
7-F-/ usZ L . P + 70/f.f .^0, 1 4 o k=
suBacr CNy aARGE NO.
-Yr OE8 * :S:: 4T 24 = F
GO 64 CoINC
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CSI NUCLEAR COMPANY
VdLv.=- 119:-.
7a~~%/z7' 777__ A 7,, *
3) L-,+m s nE.AAPL 7-V 77A 'o iv'~4/ A hJS
~~4-~7- '-vZ - ,a~7' /is7- .s. IW7~-Z /VW/ ,-Y
WI7,1 77~ -Z5A 4 7791.S r/A WO L. j
P4~2.9 77/,,E- z,4 . ~~t. op ~ 2 2
77I"jE Z-0a*L7-/c0./ S d/ 1,Va-Tc'- ,4 '77 Sl* ,-lZ~ SZ
4/ 3 oF Th77S ?4 FE5POR~7- 77v I S 77/ S/f+/4! h
Th'74-r 7:;V, W 4. coj m~ wo~nA'j
Is oi/ E/-/It g A-
SUB.JECT ByCHRG P0
7 ? 77 SHT 2 OF Z)' MM &1A e d-A ft -. --- ----
CSI NUCLEAR CCMPANY
Co, -4-Fe& 7,TI
I IE CHOCHARGE NO.SuIaJECT
GO 64 CSINC
-8CI NUCLEAR COMPANY
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)( 46i/ 7.,= .c red 22-As 4z).
4s ~ 4-5 a~f 3/ - EAz, 7 o -S74F5Z
/4o /4o*TrF i. 39 Z' - .-~g~z(#)- -
A ,9
- - -
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CSI NUCLEAR COMPANY
.4AA?-Y i "6~ 37eS~S~-Z;;/ES
~~~~7~~~~~~SSZd;V /A -ZWr7e ~~'-'/A7J-.lE
ThY~~~~~~ L-c 7 SzcIWLw*A-7,,oW,
P 4Oq-. 1,4-7-_
z&,- Z67 -- T- 3 4 4 + 4.3( .-. 4 9 V3 k
s I2 / .
Su58JECT AO V 5 KOC HAAGE NO.
c FOAT1iel SHT Opze
CSI NUCLEAR COMPANY
Location________ ___
'RO//7- E
e0U7-, z/
A/z'e7? e~j3 } d,64 J 3.14~
Sd D. 4
Zr= 492.194
a,- 3. ! ks ;
9 1= /,2 7 7- 2
Z = S5/- S =7.-7-C .az)= 1r. r ~-A~7 <6,.&S>
~~Wr
-4,32z-13, 4-Y'
4;.A:I
-a/ Z-7 (4-1 - 4.z) /z- 2A'S
33 - r/..7 As I
S = z s2 -S 3
-7.7 Azli
aX
SUBJECT.
ac 6 Cal NC
,7Z& 7 + 7,4kJ17e. L4 -A 43Z7~
.~vs. OUT.
4<
.1=
As
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CSI NUCLEAR COMPANY
dAZI4d 770d,/ 72:A- "f,1 7es w
Fzos1 Z2,Y4
,Y= Ir /se It /,v7f
ot2p 04P4e -7- 7740 +,ID® ~ ~ 47/L/ Sf
-771szs AbZ,770^/A-L. J54~~7ZS 1,ld,1Z:;,FV
AJ:,-o7 r7Lz '57=EZ9t-& -S1 2- S / 7/ ,
SUBJZECT BY CARGE NO.
ccC- K 9~ ~ V 7OA
064 CSINC AEO
CSI NUCLEAR COMPANY
/ ,A- , /.,-
~Obfv'2Z~ A2/
.~q ~
e2oA( ~ i7Th~iIS = 'PE ~Vz
/ ~c -
P113a 2774~7 ~9og 1~~~
4
Aij=z/?( V1171
A1= V/7r
73o/749=r2o
3o~4A/4024>,74/s-S
= /S~~'-v Z?7~ 3 &~
AI4
-1 ZZ3 3
SUBJECT
CSI NUCLEAR COMPANY
S3e) Wo
-w. 9 -
.3g3~?~.4~
7A~- 3V)
?+;2i7- &)
77,-- 7)
=
7f 4.
S (LaovI r)
-4~ =
=
)
) *i.9
SUIWECT 1 p '1 C)4ARGE N0.
GO064 CSINC i
,e,4Lw11'.1s
2. 0, (z:
lo = .?/ c-(4-6-314,19
-, q/ Is.,
0 A 3,FP = 2, 3,ps "
Ph fl- 7 - J) r =,
S-IY.. o EVOJI ON POO GR Am RY 6A I-NITNI-S Y ArI I NIT -\1=1 W I-'/ NI *rfINIt
fIIANII AQ&nfl-r1 *, RCC e T\ii -=7 Of - Q001z
ON~ , I- MXTI 6HL, S~rm!:\ITS
1-\''4- UIN'-T10N Gy'FJEzRTrR Po- 7-?)
S 1.0 1593*y*) 12.00 i q. n(1
DART 3 0 A 1\1 s~ -H L., 1 1 5 .TS
c~ y 'I1)Z; = 5.600~ OHI= 9.(v) r= .5* ST= r?. n S;= 51~
'-4Yli 1. 7= t."3?5C) TO 1.29431f el=73l="1. 3')& ==
I-Y I Z= -1.2500) 70 ..200 =413T1=01 n iJ3 A 120
I-I
I N E R, ~~NC T I m G T -1 + 4 TOR N2 Z
S=.1 3. 74111 1 7&9.1 1511
USA Ur-.2-m" -0.2=A~3R-W0 Z.r
0 0 0 n.9150 I1.75n0
). 27o00 0.40000) 1.40011
P VT 5. 14 Niri:-+ SH~L P (~\T
-- I &.9n0 PHI =2 86,.00 T= '0.4nOO ST= 0).1 5R= 1.631
'--,A y Z= .33TO .4070-10 r=Z9310-1 1\1)= 3') S = Fa73
Z=f 1 .1 TO~f 0.3700 ;Mt3"sJ=o 'd3#1 A~'
P'v4r 7. '4AIJ SHELL., 3 SMiNTS
ycY'AOE' R - 4..90r) P~= 90.,)o0 T= i.q70') Sf= 1Q S4= '. 30
I. Z= -1.7700 TO 1.6000 P=2930000. Nt=3 LA
UN'EA4 =UNCTIONI GENJERATrN 904 Z(l)
S= .0 1.6250 1.25'00
r, NI-11.?7010 -0.27000 -I1.lY)1 -1. Soo
44ll'- IP3/?3e
Okt E 1ARNs o Ir)0 ,ITIRC 1IlI=T o + O q g pa
tINIEdR tUNCTION GENERATOR FR 7(2)
S=.0 2.6300
odT 8, MIN SH4EI.'.. 3 SC M;NTS
:y I rie = 4.900 R== 90.101 T= 0.7010 sn = 0.0 = 6,1
1,4YER 1 Z= -0.16n0 TO 0,5400 r=3103100, MI=.O Af=.'
LOVO P NRAMiT=-4S (F =OURIER HRNInNITC CoS 0 T-4PTa
S.C STAIT 1. 0 .0 (t3. .
3.C ENO 0 n. N1 3.9 80)+43 <1 ".o
'.C. EO '1 0.0 NI 1 l233e)-+)3 41 0.
GRT~ ti mSC 0 G. I00 M.0 S '=150.11 o 0.0 of 0.1 yj ').0 Tig 0
PART 2 Oi o .0 N1 0.0 M.0
O'= 1250.000 PM= 0.0 P0 '.1 Tt= 1.0 TO= 0.0
DART 3 O) '3 0.0 N1 0.0 M1 0.0
= 0. PM 0.0 SO= 0. Tr= 1.0 Tn= .1
atT 4 )Se Q 0.0 N! 0., y
pO= -315.oo Pm= 0.0 t= 3.1 Tr= 1.0 TO= 9.0
PART 5 )0 0 a 0.0 NJ 0.0 m 1 0.0
Pj= -315. 000 PM= 0.0 pl= 3.1 Tt= 1.0 TO= 0.1
RT 6 OS( ' 0.0 N1 0.0 MI 0.0
O= -315.000 PM= 0.0 o= 0.' T=.0 In=
otRT 7 DSC 0 0.0 N1 0.0 M1 '.0
P-= 1565.n1l P4= 0.0 DO= T.1 Tr= 1.0 TO= ".0
Z LDJ
OtJANE ARN~sa Re 0 INJIJET Pl. OR A-CN2?t-5
PART 8 os 0 0.0 Ni 0.0 M1 ' 0.0
PN= 15"5.000 PM= 0.0 o= o.1 T[= 0.0 TO= 0.0
LIOAD OA'AMETES f= FOURISA H4AIMONtC CnS 1 THT
B.C. START W 0.0 UI 0.0 1 0.0 U2 0.0
*.0 ED ' 0.0 Ni. 3.5500 +03 M 0. N 9000,12
3.0. ?N11 0 0.0 Ni -&.3400F+2 MI fl.0 N-250+2
0 Q osC M *..5 Al 0.0 0..
= 0.0 PA= 0.0 PC= 0.0 TT= 0.0 Trl= 0.
44r osc a 0.01 _Ni .. o -A
0\ TC0 P= 0.0 0.0 r= M.,) T.l=
P44r 3 OSC Q 01.0 0-i1 0.0 1 0.0 MT 1.0 T 1.0
0N= P PM= 0.0 P0= 0.0 Tt= 0.0 Tn= 0.0
r 4 C 0 0.0 N . M1 0.0 0.0
= .0 PM= 0.0 on> 0.0 *TT= c.- 7rn 0.
!a A T 5 OSC 0 0..0 NJl 0.0 1 0.0 N 0.0
PN= 0.0 PM= 0.0 oC= 0.0 Tr= 0.0 Tn= I.0
PAT OSC I 0.0 Ni 0.0 Al 0,0 N 1. 0
nN .0 PM= 0.0 PC= 0.0 TI= c.0 Tn= .
avr 7 OSC 0 0.0 1 0 I . )441 1. 1, .0
0.0 PM= 0.0 oC= 0.0 T= 0.0 Tn= 0 044 3 oSC 0 0.0 N1 0.0 41 0.0 0.1
PNI= 0.0 PM= 0.1 0= 0.0 TT= 0.0 Tf= 0.i
7 7tw, 78'
A-NLET P., +
__ 3 ( QHI S THETd6 S SHEdR si-S2 I1-s3 S
PAr TI 53 INCLDtJD
S= 0.1
0.0 L.994E+03 5.983=+02 040 1.396_4=+03 1.9349E+03 3.244E+03
0.0 -6.149E+02 -1.845E-+02 0.0 4.304E-02 -6.14+9E+02 -1.845E+.)2
5= 3.'
0.0 .1.578E+03 6.66.8E+02 0.0 9.113=+02 1.91t7E+03 2.8 2E+03
0.0 -7.157E-f-01I 5.211E+01 0.0 1.237- -+02 -7.157E+0l 5.211E+01
n. 1, I 57qE-+-3 6,6 8 +; ? =-4- -'177 0.1 1,77 -3> a 5= 1.'
1 1 -7 1 59 + :T R 71~AO 7 -61 e) 1 717=-'17 17 y g A7 1 y:
PA CE= 1.
S= *6.3 S ~~~r =-i,
1.0 ?.t82E+03 L.516E+03 0.0 5.654E+ '2 .7 56E-03 3. &32 +03
0.1 -4.400E-+0 5.813=+02 0.0 1.021S+03 -4.'-OE+02 5.813 --02
S= 9.5
'.) 4.603E+03 3.608P+03 0.0 9.945E+02 4.451E-03 5.853-i-O 3
1.0 -;3.457-+02 1.975F+03 0.0 2.q20E+03 -3.47E+02 1.975 -13
S= 9.5
;ACE= 1. 0.1 -ASA +17 1,971i=+01 n 0.1 .7 a as 7=
5= 177
7_ 7L w/ 8/78 -
0UANIF dNIotei cryfgR yiP -T o1 + OR A-rNies
S00 0 5 PHt S THETA s SHqAR si-52 S1-53 S'-53
ArT L, S3 tI'CLUIJOEO
PACE= 1. A I -T ?qt7jn-( 9 - &n 2 S1 1 30qqq53 0 Z-03 1 12 E-
S= 12.7
0.0 3.369E-6+03 6.800E-+-03 0.') 3.431E-f-+3 4.19E+03 8.0506+03
0.0 1.125=+14 9.2'.7E+03 0.1 t.999-:;+3 9,247E+03 1.1253+14
,= 15.3
0. 0 7.144c,+03 7.7 19;i+0O3 0.1 i.753 -7+4I1 3 .29 + 3 .953 4A f !- 1
0. 0 7 .5 3 8:+4*,3 7.670I5+03 0. t.3 2 +2 7, 539E+13 7. j 71:'-03
4ACE=-1.n l, 7P +M9 7 m (n (1 n 77: no 7 c &P 2 0 cme n
rAGc= . f. 7.79P1 7 .90 0.'A' 1 517 3 7. 01C 0 7 79i13
<- 1O 1
-. a , A.7485 0 7. 0 1. 49 7 .73-=+ 7 go
FACE= 1~. 1~,A A,54r+4 7,7 q A I 1 777= am 7 ~77.&ry a aea
0.') 5.A4VE-+03 7.009E+03 0.1 1.1705+.13 7.0)9f5+03 8.295+'-3
5=1.0)
0.0 5.54-E+03 6.236E+03 0.1 5.9925+02 5.794-+03 7 .'3%,*+')3
0.0 -. 711:+03 6.859E+03 0.1 1 . 92+13 5.15-+)3 3.711.+.13
= 1 3 9
'~ " +<A 4/7 L wP~ 3/7 F s2 7r.IA
U)IJ4E ARvOIJ) RCI C I\1YlT a. + a7R q3-"IP45
S PHT S THETA S SHEAR 51-S2 St-S3 52-S3
PART 2. 93 INC'.iO'D
4GE= 1. 0.0 q,711 +i9 + 0 1 1 A lp=-&.0 - 711: .I
rACE=-!. 0,0 9,707'+T ,0-; 0 7-7 Om g5j 7 - 1 77=-a
9.~ -. 1 17-+-0l li q~l + 'A q'7&.V qnl=-4n2 I 1 17=Z-n
S= 2.'
0.' 6.Z7,1+03 5.305E+03 0.0 9.213E+02 6.555E+03 7.377E+03
0.0 .117=+4-13 5.500r+03 0.0 2.7e+a3 5.500E+03 .197 E-+3
5= 3.1
0..') 8.923-+103 4.805E+03 0.0 ,119*+O3 S..055E+03 1.017-+,4
1.1 5..359E+03 3.24-7E+03 O.0 2.- 12 +03 3.2'+.7E+n3 5..359E-403
-ACE= 1.
4G7E=-1. ) 7-=-n
I 5564 +,l 6,177 n 0' 0.1 1,TT +j, 7 177=-;-2 1 7-= z
ZACE= 1. 6. 719 O iAq +n7 1, 1 7F 1 -ll -1 1a: a 1 ss
S= 4.1)
0. 1.554E+0 6.127E+03 0 9.411-+03 7.377E+03 1.'795 as
. L097E+( 6.554E+02 0.0 1.753E+3 -1.097E+3 6.554-+02
5=5.1
* +* 1.W15,1.1 1.340E+04 2.951-+04
.1 5I=+ 2 5150 0.0.232E+0)& -1.259E+n4 -2.51PE 02
1)tJO'A ARNO)D ME IRC t T + f: N. I 74
C: Ofs rP S THT S 1-THa S SHPAR 51-1
PA1T 3, S3 INS3 UDFO
S=
0.) -4.t5AE+03 0.0 0.0 6.156E+03 -6.156E+03 0.0
0.1 1.399E+04 0.0 0.0 1.399E+04 0.0 1 .399E+I/4
S= 0.7
0.0 -t.398E+05 0.0 0.0 1.398+05 -1.398E+05 0.0
1.1 1.493E+05 0.0 0.0 0.0 1.493E+05
I - Z mI ; 7 7E7 46 f, /l "Z 7 -7 1
90.0 7.225E+02 5.4-81E+03 1.961F-02 4.76q-+03 1.032E+03
;SCE= 1. n T QA7-+-" 4 g77=-l 0 2-011 1 9A7=s1 4 (7747 :
90.0 4.065 +03 6.484-+-03 3.3)0C-+2 2.511E+03 4.1qE+03 6.530e+03 1R V1I ATRA4-.r 9 AQAC.A.1 192O 1 o77< AT 4. 14 AT4SQCA
CE=-1.
90.0 -1.450E+n1 5.170E+03 3.712E4+01 5.115=+,!3 3.012E+02 5.4-5E+103
1CE= 1.
90.0 4,4q5P+03 6.5195E+03 1.905P+02 2.070E+n3 -4.457E+03 6.537-+^3 1 !,0 7,A09=+01 -A7y+ -5 377e-1: 1 1rcil-6 7 0 =-6n 2 - =2 1
5= 0.3
10. -3.723E+03 2.443E+03 0.0 5.16,,+03 -3.402+03 2.75R2+03 9n0 -1 ,41AP-nT ci,170=+Il 1 719 LOl I A4 AT ;=G >? IR l
1.100 3.694E+,13 7.896E+03 -1.153E-05 4.2nqE+'3 4.009-03 8.211z+03
0.0 1.160E+03 4.077=+n3 0.0 2, 195+03 1.15E+03 .n77 +03 c;;- 1- 4 2 :L -67c4'nZ 7 =,;.J~ 137~.
. 130.0 7.909E+3 8.962=-+03 -5.925P-n5 1.153-+03 7.009E+03 9.9S2=+'3
g/79L Z/ n7,
OUI'N'E AAMN0L REC INLET OL +OR -CN1245
H00o0 S H S THETA S SHEAR S-52 S1-53 52-53
od:kT 4. S3 IINCLUDOE
5= 0.5
0.0 -2.997+-.-03 2.148E+ 03 0.1 5.145-+03 -2.532-+03 2.+3-+03 9 .r) -,7 ,4=+,17 9i117 +r -1 9; - Ja c 1 -6n I Id/ A=AAA
L30.0 2.485E+03 8.087E+03 4.2-15 5.512=-+03 2.R00.+403 .42,+3
0.0 4.194E+12 3.404r)+03 0.) Z.915:-+03 1+.94:+ 02 3.4047-+03 90, -1,18P+n2 A ,9 G 7. 1mse 7.1,=4.+ I I, AF+n I ;, I C-n LiO.0 8.307-1_+03 9. 543E-+03 - 2.-2 74i- 15 t.215 +03 3. 307E-+0-3 9.543z-+03
5= 4 0 = -1.
90.0 -2.060,E+02 5. 117=-+03 - 15 5=+.: i. 330=-+13 1 .0543E+02 5 .+3, + 03 10' ,4A85E+n3 An87=+nl f 12 - q,9nI 17 7, np+n. 1 .4'.7 a.n
G= "1, 30.0 4.398E+13 6, 4-399=+ 03 7.313=-+,! 2.1960 4. 39iE-+03 's. 50 1to
90.0 3.924E+03 6.454E+03 -4.165E-4-02 + 4.172-=+03 5.135=+03 180.' 1 ZATC+67 1-7AI A- 79 - c'n T-.-'ta 1 72&4and --114n
RACE= 1.
91.0 2.433i+03 6.007-+03 -2..172+02 3.501+-13 Z.420C+3 .. 0 20+13 7R - A,0 CA 7 77 7 t;4 7 a--/) 7 1'2'1 -6n I ljn=.&n 7 - n77C
0.0 -7.941E+03 2.4466=+02 0. 3.27+ -7. 54-5E+13- 5. 5 1 =--I 2 91.1 ,9 24F'-1 O7 aga~ -a 12+M 7 ,4AIeson- , 7;+ as -4 ,a~
L .0 .51+4 1.256c+.34 .1.29'+4--04 1 .L47=+13 t . 2995+- *0/ 1.5 L 2,+14
0.0 4.32iE+03 4.136E+03 0.1 1 .91590 e. 136+ -3 4.329=+0)3
130.0 5.383E+02 7.877r-+03 6.763;-')5 7.339E.+)03 5.389E+02 7.377-+03
91.0 -. 22+34.154.=+02 0-1 i.197+13 -5.967=+03 7.301+2
. L30.0 1,474E+04 1.239c+04 1.239i-04 !.955l+13 1.321E+-04 1.50h+i4
</r t?( ew 4
OIJdNe dRN~flo R'CIRQ INP'4T or +~ onq~gp
5 pHi S TH=TA S SH=4 s1-S7 si I53
aR r 4. S3 INCLUME0
0.1 >.LOfv; 9 4,72 A.j t1 8 To=q 7 anac as 3 Anata
90.0 1.753P-403 5.912S+03 -6.302=-+02 4.345=-+13 1.6i0 .015z+.13 141j, 91.IR no-I3 =-Mn.'+0 I,9.at. 7 -707=a-n A a.r i7 - 1 nA
1.0 -6.292E+t3 4.154=-+I? 0.1 7.A975+3 -5.9q67a+3 7.3) 1+12
L 30.1 1.474":-+04 1. 239E5+04 L.-2 39 -4 1.351,=-03 L1. 321 =+-4 1.505 + 0Z6
0.1- 2. 903,'-+03 3.4 23 + 3' 0.0 5.19 -3z-+12 Z. 903 r=+:.3 3.'* 3 +13 1 9 - Poy -A ;--zc1 +njeCo 4 --an 1 21 1 rAni.nV 4 4-11 aV
LA0.3 .035E+,12 .. 4-11LE+40 3 1 . -5 9514 7.7q7=-+03 5. 133E+12 3 4.401I=+13
S= .3 Z.117p-l .
0.0 -54480 5.6 0 6 +2 0.1 .0 5'+13 -5.17+ 3. .7 5 6+2 9. .j 4.7479+03 A s~n .4 mpcn 7 777Csom 4 Q7CneseT 7 74
91-~=1 z -1A-i ' L1. 14996 1 .31 3E+04 1 . 3 62 1 .9 50z+03 L .3 44;--+ 4 1.5 zq=-+14
0.0 ;2.179E+03 3. 125E+i03 0.1 q .457=-+02 2 .179 =+ 03 3.125=-+03 QA .'1 1 .747?-(1T 4,70 cA -1 OR7C 7 i TRCtL12 1 e1 1 ag A
L30.0 3.1549-+02 3.464E-+-3 3.2725i-14 3.t596+-03 3.054=+234590
A C
.1 r0 7 170p&a1s 7 r7o.ze3 (0 * 'f '/"7j+%' 2 179c5+ ? 3.29$
1 0.0 1.425+03 44&fV 5.757+3 -. 95 +1 .15 +03 1.11170 Q.0293+03
MACE=-1.
*17, -1r'?7- +'V 7,A77C+A7 A,'8 4 AQ=+t' -4 7970a2 T g7c&.nq 90.0 5.723E+03 7.0715=+03 -4-. 3871 S+ -2 ?. 27+0-3 5.49t+Ol372 .533 + )3
TAS i 1 T. -J/,a 1,TWACiAA 1 4=7.-t. 7 :1 1=r , 1 247C.. 1 4eA &
2 C 1 C) 1n=.ay 1 n 1 ,g r- -1; 3 17 I 6 "7 I ... 1 -C5.f~ 7- 74.7 q qQ& +M -Z r7~j~ A.. 7 =. n 7 1-7
5.433-+03 -1481=+13 .
SZ)41.? fl/7 WL wP 3/7 L 4
')UANE ARMfl'J R.EIR rNJLET 9', + DR9CNL
09 ~C7OOD S PHI S THETA S SHEAR S1-S2 ST-S3 S2-S3
PA-T 4, S3 INLU08JO
5=.5
0.1 -5.LORE+03 7.822E+02 0.0 5.!R41E+03 -4. 737E+03 1 .097S5+03 4, 5 57713+nl 7.07I=+Il -&. I;A4R-'.oVP !; aQ10 1 7 s;A=-Il
190.0 1.S55E+04 L.336E+04 1.457E-0-- 3.197S+O3 1.357E+04 1.686E+04
0.0 1 .975-=+03 3 .123E+03 0.0 1.2 49 +3 1.'7 5 P+03 3. 12 3+0 3
19. -1.351=-+13 7.742=-+03 4. 603P-- q9.0,931-+03 -1 .3515+0,13 7.742q-+13
S= L .8
. 75'88+03 1.068=+03 0.) n4.15S+3 -4.773E+03 1.3;3-+,3 qn 7 a -6m 7 771-- -4 11, -"n R - 47 - 7-nll*j-'2 7 q '-n
. 1 94 1 3+8 )1.379C-0 4 5.925E+03 1.379E-+0- Iq72=-+0
0. 1.972E +3 3.392E+03 0.0 1.z21E+03 1.q72E-+-n3 3.392F+)3 a, 1 7 1 7-.~3 .. -61 'A 7 0~ 1 7 ,: .i 7 ; -2 Z I,
19. 0 309 6 li 505E-0 4 1.0'47i+r0z -4.319?-+03 6.!55=-+.'3
A T . -- TN H
90.0 7 7.69+03 7.276E+03 -4.531E+02 q.126 +02 7.091E+03 7.q94=+03
I C = 1. --- -
O ,A9 49=+A 1 . "1.n A 1 90.0 -1.1 79;-+0 3 4.621S-+03 -1.916E+03 5.952S+03 -1.755E+4-3 5 . 1'47
90.1) 4,977E-+03 5.842=-+03 -4.293E+02 1.219E+03 5.115E+03 6.334;-+13
91.0 1.246E+03 4.457=+03 -2.369E+03 5.7-23=+03 -1.02E+01 5.713=+03
S= -. 4
').0 -266+32.293=+03 0.0'.weo -2.3915+n32A 0 '- I1, 4,977i+nA R 8 7+ 3 -,9R+ 2 iv a a ,1 5 o ,9 = m 190.1 1,5+0 9.391E+03 1.33,-s 3.259l=+n3 9,715=-+03 1 . 2 QA+
e/78
* o -rA s PHT 5 TH T a SHRAR ;1-;7 11-5-
PART 5, S3 INLUDED
Ace= 1.
90.2 L.246E-+-03 4.457-+-03 -2.36q+03 5.723S+03 -1.022E+01 5.713E+03 1I c Pk6fAl 4/47=+ni 7 1A- 7 L/-7=.1
90.0 13.13 6i,+113 4.247F+0 3 -4.919e+0 1.AA4 +,13 3.2 55 E+ 03 z-.74A P+03 Ig 1 7,471a+ c n C gi-I 7 4 7 C)49 C)' a g 7 71 z:
QCE='
6.
9e).0 .3.Z77;-+,13 4.0 00 1-+0 3 -2.463r-+,03 q.97q95Z+43 1.1'+96 +03 6 .12 q z *03 13rL.) 7 7' fir, a m+C)' 7 Qq=-.4 -4 -A7 e I- 4 2 =.2 7 47 :13
S= 0.3
1.) -1.152E+03 3.419E+03 0.0 4.57V-+03 -1.359E-02 3.734E+03 4-:~~ 2',A,+C)il' -Zl A j r,4-0 1- 4. "3 3 265='3 Z"
13'0. 7.'+23E+03 5.075E+03 1.529E-04 2.30+03 5.390 E-+3 7.73,89-+03
0.1 -1 e99E+03 3.650r+03 0.n 4.74Q+03 -1.039E+03 3. 652-0+O3
13).-1 7.(,522+03 4.351E+03 7.659S-04 3.371=+-13 4.351E+03 7.6529+-)3
'.' 4.619E+01 4.395+03 0.0 4.34qE+A3 3.SL2E+02 ..71 2+03 0Q .) 1 AAC)-a..' 7 AlQC+1T -R ~ACA-& 7 1 Oj.C)A ?2 1 7 7 TT
130.'0 2 .191+4-3 8.4342+02 1.A22F-04 1.1 7E+03 1.159E+03 2.46 E-! 3
0.-1 -1,3992E-+03 3.872=+03 0.'1 5.74E=-+,-C3 -1. 122+03 3.9 72413 C).C - " AQ T - 71&--II -; 7 7c7C+1m I 0 q; A 7 174Z8 7 C74l - -7
13,' 1.?97-+04 3.555E+03 7.017E-04 9.3142+03 3.555E+03 1.247E E+')
1T 7
90.0 1.068E+03 2.619E+03 -5.860S+02 1.q44=+03 1.197E+n3 3.131li-'03 14As. 7.91+)' AC4BAP+* 1 77nq p4 1 47yj.C 1 i 7
.ACE= 1. A -1 997= C) t A C)1 S : . -1 2o7~C) =4 2r0Z
90.0 5.419E+n3 3.714+03 -2.257F+1-3 4.R5!=-+03 2.176E+03 7.225-+3
D1-t rr LWP 47 3r. 4 4
O~dNE ARNOL RECIC INLT P!- +DR -^1
* 0040 S PHI S THETA S SHE&R -52 -S S2-53
PART 5. 3 INU090
5=
0.0 1.106E+03 5.147E+-13 0.f 4.015+03 1.421E-+03 5.462E+03 20.11 -- l_77 yp-nI I IA9=+ l -7 4, gl -n 1.T B - R R ' 4 R +
130.' -4.i80E+03 -2.968E+03 2.313e-04: 1.713E+03 -4.355E+03 -2.553C+.03
0.0 -2 . 552r+3 3.9705+03 0. r 5 - 370S
131.0 1 .96+ . 551-14 1. 5 +4 . + .=' 5 +6 3
AT 4.ST NA uc
FACE=-1. 0.01 , 7 +0 n.0 e0 -,4 -775 ml c; 7a 72 9 Ay 46 91.0 -1 .796-c+03 1.081E+03 -7.125=-+02 3. Z11+0 -1. 649+ 03 15's2 E+0I3
FACE 7 ,c
90.) 8..465,E +03 4.158-+03 -1 .24+03 i.6429+0 3 3.439E+03 q.13130 3
74
2
7&
90.0 3.351E+03 3.803E+03 -6.5929+02 1.319E+13 3.483E+0-3 13
SCE= 1.
90.0 2.314643 3.492E+03 -9.255E+02 1.9715+~03 2.157E+03 4..13AE+*-"3
= 1.4 d= =-7. 0.0 -3.144+2 4.958 E +03 0.( 5.272S+03 3.952E-01 5.273=+03
130.0 8.014x+03 2.648E+03 2.050E-04 5.365E+03 Z.953E+03 *'1.3?20C+03 -'C?= 7. 0.0 -6.491E+02 4.692E+03 0.0 5.341E+13 -6.41e+02 4.6929+n3 41.1 2.4155+n! 3. &%11 +.T -9 741 1 , 71= ? 7,1 4 .T I TRO n - II= L. %
130 .0 5.27 9,!+l3 2.293E+03 2 . 77q-0&)/ 3.9Q,9=+03 2.293E+n3 4.79+0
S= 2 .9
0.) -4.959+0 4.634F+03 1.11 5.1339+3 -1.94E+02 4.940Qc.+3
130.1 3.171E+13 4.821P+n3 1.225E-0 3.390E+13 5.136E+O'3 P.496E+03
/t a 7r 4w' /79&,-.4 - z W P
OUAN 4M NOLD RE:Ic INLE- T c'.+ 9-Cv2\ 4,
COrD 5 PHT S THTA 9 SHPAR 51-52 51-53 -157
PVIT 6, 53 INGILUOC0
;4C5= i.1 -1 1290 -+r 4,70; -A 1 4 7-7 - nO; I4. 4 7
90.0 2.929E+03 4.4-25=+03. -9.271E+02 2.447=-+03 2.404E+03 4.850E'-03 13(ri 5.7,19+o2 4d.TA~.e 13 7 3A'-14 I 4azn 19=a a 4:0
I -3 15 ~ if .. 797 rv 1.. ; n 1O~L.' 1. C4&l $1 2 - A -AC V97
5~= i. . 1 1 -5 .10531+0 4.634E+03 0.0 5.134i+03 -.. 955E+02 .
13-0.0 . 169E+03 4.8215-+03 1.225E-Oz 3. 34-3:+f!3 5 .13 ' E+f)3 9.4134E+13
.0-1. 119 E+02 4.670P+03 0*0 /.772'=+03 -1 .019C-+r2 z. 670IE+03
13,').1 5 .76 Z +03 4.182S+0 3 2.9A3 C-0)4 1.5,q15E+ 03 4.1382E+0-)3 5.752E+03
4.1
7.)- -2.913E+02 4.5,50-')3 0.0 4.957=4+03 2.35E01 4.9 90E+03 4n,., - 3 -7q =+PN- 4A 52 + l ' - - - 1 =-6 'I I ' I - -A-f .. 1 A :
1-30.0 7.049E+,13 4.772=+03 I.M52E-04 2.279+E--03 5.03cSE+n3 7.3,4E+)03
0.1 3.127-.+o1 4.593=-+03 0.0 4.563E+,a03 3.0Z8E+01 L-.5q35+03 qt,., 3 , q-'i 4 ,nl -' ~ .' - = I7 -1 .17(-6-1-4 7 , 49P7'=rP -69- 7 7ql. -n : -1.fA12.
130. 6.541-+03 4.6884c+03 3.130e-04 l.853r--+03 4.69E+ 3 9E.541+.03
90.0 3.378c+03 4.668-+03 -3.-385e+0-2 1.457=E+03 3.60 -'+03 5.0537=4+03 140 I 7-1t+ 4 7771 a12 1 *ae-aI n ;77=-,n l n 7 =-1a
* CE= 1.
90.0 3.Z97+13 4.641-+,03 -1.OO7E+03 2.425+03 2.751+03 5.177-+03
0.0 - 4 q74P+0 0 1 1-1A A- 7 1-.e 9 - . qZ
91.0 3.30l15+03 4.584E+03 -3.333E+02 1.450:+03 3.532E+03 /.q3E+n3 110.1 ').74+Al & 941=+11 1 19 7e-1 7 1gqe1.2. J A q:; I age
C4E= 1. 0.1 1, 44.+9 4,7 4. 0A -. c4i7- 2 1 =+n -4 n .1.t7;;
91.1 3.363E+n3 4.603P-+13 -1.m31E+03 2. ZE+13 5.7.+3 5,19+3
v4 Z/7 7-P /M9
OIJANE IRINO-0 RECTRC IMI-;:T 0o + 09 !-CNI745
YOGOO S PHT S TNETA S SHRA4 Si-S2 S-53
4dRT r IS S3 INGLUJOED
0.0 -7. 300E+07 4.574E+03 0.) . 547=+03 2.'+20P+O2 4.119=+03 9.0 3 + 4,98&P+01 -1A 197+02 1 ,a &5 s+n ' i7 A, 9 q I ,
L30.0 6.673E+03 4.5344E+03 1 .0 5 2 a-0 4- 2. '79-7-+03 4+.9095F-+0*3 i.9 1 '=+-)3
AC,9- 1, Q. 0 1.-15E+12 4.576E+03 0.1 '+.414+3 3.23552 4.5778+-*3 L91. 0 568E+13 4.631=-E+03 3.206-0- 1.937=-+13 4. 5 31E+03 .5ii7+13 S= 5,9
0.0 1. 176;--+.(2 4. 5-3 2E+03 0.1 4. 464-..+ 3 +32 4. +0 4.997:+03 .'A0 3 77 1O Z, -7S &E- - - 176 E+A7 I 1 eis, n I MSCZ n ; t -6,
L.00 6 .53IE+013 4.5566-=+03 1 . 03 +P--l4 t.9 655i +03 '+9 3 +3 1.'46+')33
0.0 3,.23 3 -+,12 4. 577=+03 0.0 Z.5'4-+-+13 3.235-=+0? 4.577=-.13 9-n T Th m n R g s -1 AmocA/ /-o - 7 P4 cT -a- M''- a7nt"lL .. 1 .3 571--+,o3 4. 5 831 E+03 3. 231S-04 !1.7765+03 4. 5 3LE+03 S.-3 37 +13
90.0 3.323E+03 4.574E--+03 -3.32=+?12 1.417=13 3.555-+-03 4.972-=+13
Aci= 1. I , .46 j Pc4 47.a-~ 7%. C; P -7OCm
9.1 3.3432+13 4.5905+03 -1.039+03 Z.6419.+i)3 2.751-+03 5.173+03 16 . . 5 q. + Z 1=+ I 7 4 1,-7' 1 . 4 qIo- e c a..,I a
.1 ,9+9 P 4P5 81 =+OTn I nfl.P qC -n? I I9=n q 0 C On
90,o 3.335E+03 4.579=-+03 -3.223E-+02 t .4) 2 =+I 3 3 .571,-+ 03 473=+:13 I 01 71 7- +O'A 9,79 =+02- InRa ,7= osane nl 4 P96m -4
1,9 5,);:+n7 I Z 979G A 4-M n 4 o, n9 0 1qy =S4 70c- Ls 90f.0 3.330E+03 4.579=+03 -1.143i+-13 -2.-3q=-+03 2.735 Z-03 5,173=+13
1400 .144+4 5A +n I-2sc-n4 1 9qq=+.nl 4 97fno414=n
0.0 Z.973E+-!2 .5i35-+13 0.1 . .9 9 . 23-+0'2 3.94-1+13
*9 1 3 ,i 3 A + In ? & , :579 r- n, n I -62+ 7 , n = n I5 0= a & , q7 pe s-n
L3. 6.699-+.13 4.375E+)3 1.002=--04 1.7949=+-13 .9905+1 '.57 +13
DMAZ rl ff 9w /7 2 s--
00JA'! fANIr)M Q 4 TRC TMl y C T + ; oR -ra
* 'Jli) S S rHCTA I -H~ 5; A -57'
AR T 6. S3 VNC.JOEFe
40.v;= 1.
90.0 3.331 +03 4.578=5+03 -1.!41E+13 .433 +33 2.73iP*03 5.171!4+03 190.-,+ A177=6n e477=so' , I a 4 I77eiem A rANA.
0-7
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90.3 3.334z+13 . 5 41+03 -3.!22,+l2 1 39+ -3 3.575i+! 4.7 -4 6+33
= 1. i'1 A,A7C+a07 1,lCAAC+tV A 2 017-z.i0 447CaOT 4013
:= 9,7= I 0.' I ,577+02--f 4.5A303+3 0.-1 3.913:+13 6.677=-+2 .53-0=+.3
g'n ' _1 & _Cfj r61 -1 C'A .zjfn2 7 - Z-Z; = -i z 7 2mr'*- a 5 Lin.0 3 .996E+03 4.50 +023 3. 287=-04 1.4t33 . + 5.9'46=+-3
5=11.1 q. 6.509p+12 4.5333+03 0.2 - 32+3 .53 +03 '.49.+13 130.0 6.006E+03 4541.r-+3 9 .2-5 12 25 +4 '+.95 2 g.321A+)3 0.1 9.369'+02 4.510P+03 0.) 3. 7-43+3 4.3695+I2 . 3 Z3
I -,g1 Ca+ -A ' -,;A C a n, -I '; &77 A2-M 2A 7 2 M 1 q 3 LS . 5.9 26E+03 4. 512E+13 3 .3 155=--04 1.244,+13 '4..53:!C_-03 5.i2i:_+03
iO .',401 ;+M7 4,_SATP+f0l 0 97= 7 1 sq xc 91.1 3 .33 2z+03 4.532=-+03 -3.129c-+02 t .3 q- +)3 3. 579E+03 4.9 4 + -3
1As, .104E+21 .,5AO9+oq q Z'o I s e C; I C.6 -1 0 10e Am
AC= I.
q 1 1 77c-:17 A I = -,I a Z.a y, no a m y a z a E 90. 3.333Ez+-)3 4.5i25:+03 -1.16i=_+13 .47 1=+13 .722=+"13 'i. 143- + 3
M 1 212
zA </vt *P 8/78 #*nt
g, 1- r 319 :!r
0)1NE ARNOO RECIRC IMJLT PI- + lR 9-CN1245
OO5o S TrHTA S SH4- Si-S,? S-53 S2-53
ART 6 , 53 INGLU-IOED
5= 12.4.
0.0 3.479-8+-2 4.53 5+03 0.0 3.737E+)03 L.163-+03 4.900=+03 93 dn@+ & RA.(so +n -4A..gV I -A77:anyt ' c;QP.n /. qAcAn
L30.0 5.932E+03 4.544-E+03 9.154--05'- 1.2483+03 4.399=+03 6.'75+03
0.0 1.1002E+03 3 4.579E+03 0.1 3.577=+13 102+03 4.5790Z+03 90.1 3375 +nl 4.9 9R0r--l- ,r% +n- 75, A 2 Z- 7 717P.vol G, q70 o
L30.0 5.547E+03 4.530E+03 3.342-14 t.1)7=+13 +.5380p+03 5.54.7 +3
AGOE=-1.
1,1 A,7G4 4gBARG+t~ A," 3 77CP 1 1 -7.(V7 4 Q900 '1
90.0 3.339-+03 4.534E-+-3 -2.,44 4+2 1.371E+03 3.533E+)3 4.9,55+13 I. - el 5 ,81 0 0 ,?3c o 'A1 =- 7 467 = +C'4 PwOE n -1,A&/n=+6nl
91).0 3.326e-+03 .531- -03 -1.175=+03 2.49+03 2.70q=+03 5.19+..13
5= 13,9
1*1 1 q=.a.( l &,70=J-6n' fl~t ":zV 1, C4 ( 4.i 'A
. 90.0 3.352:+03 4.576 E+03 -2.59=+01Z L .35t +03 3.604-+03 4-.955+--13 19 q.'1 5, P-!A c; 471r 4R71 P-11 1 Qnl=> 4 q C 941 Q
ACE= 1.
90.0 3.312E+03 4.,534E+03 -Z.350 25025+4-13 2. 687E+03 5.t1495-+13
5= 13.3
0.0 1.03-3c+03 4.579r+03 0.1 3.5427-+13 1.3535-+-03 4.4-E-13 91.0 3.151 E+4l &,576P+nl -7,q9000 5,s=o =-,-n 7o ,ae
130.' 3.665E+03 4.573i+03 8.377=--05t.0929+33 4.385.93)=-+)3 =CF= 1,
0.0 1.164 +03 4.559E+--03 0.0 3.405E+H3 1.164 +03 4.i9-4+3 90.1 3.3148+03 4,94"q3 -1 -,,;lta F +F+OA ;,ofz-.m
I 3r),0 5.463E+0)3 4.561=-+03 3.36.3i-04 ,35+24. 561=-+O? 5.46i337+133
S= 15.2
0. .1 0 + 3 . 43 + 3 0.1 3. 3f3:-+03 !.4'995 +13 4. 35 +13
91,1 3, .914+ns 4,571=+ml -2 , 7R=+n7 In=n ,~co ~c o
193.1 5.407-=+ 0 3 4.513=+03 3.57i--05 .13'+4+"2 '?.919 +'3 5.7Z2E+13
Zab' Lrv WP t/78 -
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AT S, S3 I1C0.UE D
90.' 3.371E+03 4.547P+03 -1.183E+13 ?.474E+03 2.72E+03 5.194-+03
-:i 7 -17=-M - 7C t
0. 1) 179C-+"3 4..5,1!.F.0 3 0.1 3 3 5i+ 13 t.37+Z4E-+-3 4. 17 i.i13 L e)..1 5. 49 R +-,-+. . T e e 5) 3 Ei- ) 3 8 9 7 5 5 2 4 3 r an 1 m:-g -1 a 7Z0-:,)
OI I 1794+3 4.534=+03 0. 3.3 =-+-3 1.. 3 9 0 3 4.359z-+"3 QA 1 4 - 797-A - - 4 . m~e -r6 = .rl -1 ') 7 - 4 q .11 ? 7R'i99 tl 1? 9 q7 -6
L30.1 537!=-+03 4.533E+3 3.3975--4. 1.334-+-12 4+.533,:-3 5.37te4+3
fG~= 1
-0.0 .1.74+03 4. 5573+3 0.1 3 . 3 =+1+3 1..7' ++-3571+0 3
-1.0 176 3 4. 4-3 6+03 0. 3. 32+ 1. 48--+5 4. 1-j+03
0.Y 1.729:+13 .4.652E+03 0.1 Z. 933-+13 1.729+3 4. i2 +13
qn I 77'afl ,7 AT ."4i -1 aC (7 7 2 .. z 7-ACJ T 77a:: iZ
3e.01 5.571E+03 4,7'+0'+03 3.36- ' 4-3 .3 0i+12 4.7C+ 3 5 5 7 1 + 13
'4C= 1 , 90. 3 0 4E+03 4. 5 11 f :0 -2 75O4-1 9 -13 3 7V;-3 4 1 75-1 90.0 3.651=+03 4.7023+03 -1 185+13 2. S=-+-3 I .4 735+3 5.3104+13 7. 1 2 4i7la- Z -74 111 - 2 f a OONe 7 . 7 - ' n a A72= a
:4= 1 1 1 1 7Q6nj a pts: my ti 16 2 o1 1 -77qP7,n-A 5-260=4 90.1) 3.149E+03 5.14+3=+03 -3-I575-+O22? 95O 3.1t'+E+-035.1+3 1M I2C n q -lA7=-6ns .q -y n Q co7 n 41 a 4 ee 1 <7=>
30.I 3.517E+,13 5.2535+03 -1-18S+13 2.7q!-+03 2.995E+'3 5.775:+13 1gf 1 4 1c.aetx 4 7AC+v 74yge-m 7 Ro my 741CpIc7sa47c
A /e LWP 8/7' - -
0 UdA ARNL &' 14 T 0LT L 9 A -C724
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5= -18.1
1.1 L.46ZE+03 4.954E+03 0.0 3.491+f%3 1.777E+03 5.2 9F5-+-13
190. 4. 331E+03 5.331E+03 9.915E-0 ... 5,0n 5 +2 5.1146E+13 5.646;+-3
0. 1 .793E-13 5.0315+03 0.0 3.23R=+03 1.793E+03 5.031 e-13
130.0 5.?436--+3 5.477=-+03 3.375E-0.. 7.333q-+12 5.243E+03 5.477+413
S= 1 9.4
. .46 +3 5.8914-+03 0.0 1.745P-+13 4. 61 E-+03 6 . 2015=+--13
13.1. 9.554E+03 7.429S+,13 1.042 -0 7 22-*+3 7.7+4E-+-3 9.q69=-13 4. = 1,
O-wl -5.-9915i+o2 et.490=-+03 0.0 .951 50760 .950
131.1 3.939E+!i 4.549E+203 3.91E0-f4 4.511 E+3 3.93qE4+A1 4.549i+13
4-A C E= I .V2
408= L~
9).0 -7.332 +"? 4.520+03 -1.2483+03 5.3 6+93 -5.407E-02 &,829 +13
II ,A 4,09 +Q I7 +=-+ III =-671= --2 1, 5s 7,;= *,= 7. f . 7;=-'
91.3 1.333X-+04 2.073i+03 2.171S+n2 1.127=+n-.- 2.334E+03 1.3,59+n4 13.1 1 1. 95C,-+4 ,+7:It' 1 -A7747=-1: 1 71 & T, 7 1. 0
;AGE= I. jj ~ 17~--Y~~0.17.1 4... -~1~ 71 ?7
1 ,lI - 7g944 4.1 A 774og -ewom n 1 7,y ans -s~ 7 an ~. 177.. -V 9-1.03 -6566F-+03 -3.926E+03 -1.667!75+03 4.316= +n3 -7_.4 +03 3.
me. / r wP / na73
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1.0 4. 31l).-+n3 7. 5.5 9.') 3 0. 1 3. 125-+13 5.,945-#.-03 q .171T-J3
0.-1 5.937E+1~3 3 .07 2E+113 0.1 1~3 5=--13 5. 937=--n3 3 . 3 72-;--'3
n. -- 319n 1 5!
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C31 NUCLEAR COMPANY
Thermal Analysis
The thermal analysis is performed using finite element computer program #1606A, "Heat Analysis Program" (HAP). Given nozzle geometry, mateial properties, fluid temperature transients and heat transfer coefficients, the computer program calculates the nozzle temperature distribution as a function of -time. The most critical temperature distributions will be used to generate thermal stresses in the stress portion of the report.
Thermal Model
A finite element was constructed using the safe end geometry shown on page 78-2. The forging part of the model was based on the geometry of Figure 2 of the Design Spec (Ref. 1). The model mesh is shown on pageTf-%.
It should be noted that the corrosion allowance of 0.010" on exposed interior Ni-Cr-Fe surfaces have been neglected. This will not have any significant affect on the results.
Water elements are used in the gap between sleeve and nozzle.
Because of the relatively small width of the gap the water elements are given a special conductivity reflecting both conduction and natural convection.
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Selection and Description
of Significant Thermal
Transients
After an evaluation of the.vessel and nozzle thermal cycles
(see Ref. 1) the following events were judged to have potentially
significant thermal effects.
Event 3-4 Start up
Event 11-12 Loss of Feedwater Pumps
Event 14-15 Safety Valve Blowdown
Event 18-19 Sudden Start of Pump in Cold Recirc Loop
Event 21-24 Shutdown
All the above events were analyzed with the exception of
shutdown which was deemed to be less severe than Safety
Valve Blowdown.
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00 64 CSlINC
CSI NUCLEAR COMPANY
Boiling of Water in Vessel or Nozzle
In rapid cool down transients where the bulk fluid is at saturation temperature and pressure, boiling is assumed to occur adjacent to the metal which is at a higher temperature. This condition is assumed to-exist until the bulk fluid falls below 2120 F.
It is known that the high heat transfer coefficients accompany the boiling process. From past experience it has been noted that for most cases when the heat transfer coefficient exceeds 10,000 BTU/hr-ft 2-oF, it has very little additional effect upon total heat transfer. Consequently, the following conservative heat transfer coefficient will be used for boiling heat transfer:
h = 10,000 BTU/hr-ft2 F
In other words, when the heat transfer coefficient is high enough to drop and maintain the metal surface temperature near that of the water temperature,"very little additional heat transfer can be obtained regardless of.how high the heat transfer is raised.
The only transient judged to have a high potential for boiling would be the rapid cooldown of Event 14-15 from 5220 to 3750. Forced convection is assumed for the remaining cooldown of Event 14-15.
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CSI NUCLEAR COMPANY
Selection of Critical Times for Thermal Stress Analysis Thermal gradients were checked at various locations during each of the thermal transients analyzed. Maximum thermal stresses can be expected to occur at the times when the most severe thermal gradients exist.
Gradients are represented by the temperature differences between node pairs. Page73-34shows the node pairs used. Times having maximum thermal gradients are considered for thermal stress analysis. On pageT6-37thermal gradients are tabulated for the transients analyzed.
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PROGRAM =1.6664 CRITICAL TEMPERATURE DIPFERENCE REV JAN. 1975
START UP
TEMPERATURE DIFFERENCE OF NODE PAIRS
SEQ TRAN- TIME NODE NODE NODE NODE NODE NoDoE NODE NODE NODE NO. STENIT PAr AP Tq rq R oAy T DA 03A pa A r!Z
I 2 3 4 5 6 7 8 9
49 168 231 363 183 40 120 120 437
54 169 216 359 177 120 196 203 500
2 53.521 2. 4. 3. 3. 2. 5. -4. 5. 3. 3 17.04 7. , /,. I, 1 . -4. 8 '
4 160.560 2. 5. 4. 4. 2. 5. -5. 4. 2. 5 ;,14. 1190 1. '5 . 4., 4- ;. 5. -8. &. 7. 6 267.599 3. 6. 4. .4. 3. 5. -5. 4. 2. 7 77g.999 7,. 7, 7, 7 , 1 7 -,
8 289.199 2. 2. 1. 1. 1. 2. -2. 1. 1. 9 299.999 2, 7. ? , , 7. -7 a 1
MAXTMUM OTFrFNlc- 5- 4
MENIMUM OIFFERENCE 0. 0. 0. 0. 0. 0. -5.. -0. -0.
SIJRS 0OUANP AqNm I R)(AA TIMI MT r T ' r m2T.\10, 4r149 1Y:'.WP 0ATE: 7-78 CHECKED: efOdTE: REV: SHEET37 OFYT8
yoss~- JAAJ 1- 37 "j3
1.3- 4 59 7 3
4-3 163 ?31i 3 C3 i*3 14 0 120 iz 437
Z 0. 7601 -22. -25. -21 -7" -.- 2. 1.7. -5. . 3 1 .51 n - &7. - , -11. -,A, - - A ~7 - .1
4.26 -45. -64,. -5:-) -47. -ts. -55. 94. -3,1. -4 F1 1. i n =77Z~c - -C;7 -72- -. 7;4
63. 139 :: .4 -77 -51 -5 -23 -79. ',9. 3. 7 .7 A -41 -7a. -:54 .- 7. -.
3 3.395 .- 37. -7:? -53 . -50 -35 -. 6A . -i~ ? 3.
3 7690 -.- 65, -/-3. -45. -?5. -. AA3 .
it 'f4. f1 -7.1, -e495 -&A 7, ~ Q.
U? 4.260 -li3. -57. -4?. -41, -2-5 . -. 32. 553. -35 . 2
1-5.261) -1.0. -47. -34. -33. -74. 72. 43. -:53 . 0.
15 3 A 4. 2f. -7g -1. -i-, -3A.
17 ~T*0'. -1 ..
13 39.6 5.1 15. t i. 1' e. 1.3. -13. 3 . -1
23 39 -260 4. 14. 9. I. i . 13. -11 ? 2 3
24 40.510 3. 11. 9. 3 . 1.6. -1. L? 1. 25 & 51. n . -4) 51 4, 4. 3. -n 7
26 5.510 1.. 4 3. 3. 2. 5. -3. . 2
I.r\I.iI'~ 0~N;~ -&Q. -79, -1. -:57 -7. -.- q.-1. .
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- ROGRM E6664 CRITICAL TEMPSAT1URE DRFERENCE REV JAN, 1975
SAi--ETY VV..vE iAow0OwN
TEMPERATURE DIFEENCE OF NODE PAIRS
sEo FRAN- TIME NODE NODE NODE '\IE NODE NDE NODE NOOE NODE 140, STENT PAIR P 4r Z 0t r 1 arra a1r 24A oa Z c rp o31rq ATrI
1 2 3 4- 5 7 - 7
4-9 168 231 343 1C33 40 120 12-I /37
54 119 2116 358 177 120 196 213 500
*) 0.001 1 2. . , , ,--0
2 1.251 - _. -. -7. -". -1. -5. 6. -3. 3 7,501 -3. -Ts, -11, -i9, -2, -'2. 1 -n
4 3.751 -9. -19. -15. -14. -A. -17. 16. -13. 5 5.000 -10. -23. -17. -16, -7. -71. 19, -17. ,
6 6.250 -10. -26. -19. -1.. -9. -25. 21. -20. -D. 7 7.500 -10. -27; -121. -70, -1 -77. 7. - q T
J3 8.750 -10. -29. -22. -21. -11. -24. 24. -25. -1. 9 43.000 -1. -. -7-3. -. -77. -o. 3. -5. -5.
1v) 43.000 --3. -3. -7. -5. 3. -5. -5.
12 10-9.001 -1. -3. -3. -3. -1. -4 3. -4. -3.
14 175.000 -1. -4. -3. -3. -1. -5. 4 . -4. 15 TRA,000 -". -7, -1. -7,. -' -3 - -4. -4
1t 8 5.000 0. -1. -1 1 -. - . -:2. -3. 17 189,999 1, -0 -0. -1 -- -1 -2
18 1.94.999 0. -0. -0. -0. -0. -J G. -1. -3.
-AX M 14 N r R. . 1C- N P 12. 1 . -. .
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PRIOG-aM =16664 CRITICAL TEMPERATURE DIFFERENCE REV JAN, 1975
EVENT 18-.9 SUDDEN START
TEMPERATURE DIFFERENCE OF NODE PAIRS
SEQ TRAN- TIME NODE NODE NODE NODE NODE NODE. NODE NODE NODE NO, STFNT PAR PATR PATR q Ar 79 0 1 A oT-Z mAT p a T!
1. 2 3 4- 5 6- 7 8 9 ** ** ~ ** * *- --- ** - . M aa~. ~a...~a - - - -' a~. -- -------- a
49 168 231 363 183 40 120 120 437
54 169 216 358 177 120 196 203 500
1 0.001 2. ?. 1. 1, 7, 1. -2, 0, -0, 2 0.002 -7. -11. -13. -14. 1. 1. -2. 0. -0. 3 0,038 -141, -147. -147, -147. T, -3. 1q, 0, 0, 4 0.073 -208. -206.- -199. -198. 1. -LL. 48. -0. 0. 5 0.109 -244. -240. -224. -271. 0. -23. 77, -2. 1, 6 ., 0.144 -265. -259. -234 . -0. -35. 102. -4. 1. 7 0 0L179 -275, -7,9, -239, ,-?3o', -I. -- 7, 1 2,7- 28 0.215 .- 79. -27-5. -237. -227. -2. -54.- 141. -10. 2. 9 0.251 -791 -, -233. -;)1. -3. -70, 155, -14. 3.
10 0.286 -275. -276. -229. -215. -5. -q1. 166. -18. 4. 11 0.322 -270. -?73. -224. -207. -7. -90, 17z, -23. 4. L2- 0.357 -263. -270. -219. -200. -9. -99. 181. -27. 5. 13 0,392 -255. -765. -22 -193 -11, -11, 186 -! 2P. 5 L4 0.428 -246. -261. -206. -186. -13. -114. 190. -37. 6. 15 0.464 -237. -256, -201. -190, -15, -17I. 193, -4. 6,.
16 0.499 -227. -251. -195. -174. -18. -123. 194. -47. 6. I7 0.535 -218, -246, -190, -1.68, -70, -193, -f -51, 6, 18 - 0.570 -209. -241. -134. -163. -23. -1'. .196. -56. 6. 19 0.571 -153. -161-. -99. -73, -23, '-139 79J - , 20 0.602 100. 68. 120. U'dg -25. -135. 160. -59. 6. 21 063; 146. T10, -17 13.. -77. -129. 113A - 7. 22 *0.663 159. 108. T7. 157. -28. -117.. 83. -64t. 6.
24 0.724 'f65l 05. 118. 131. -31. -95. 35. -65. 5. 25 0.755 163. 104, 109. 179, -32, -16, 20, -4. &. 26 0.785 160. 100. 101. 106. -32. -73. 8. -63.. 3. 27 0.816 155, 95, 93, 96, -33, -70, -1. -5T, 3. 28 0.847 150. 91. 87. 86. -33. -64. -8. -59. 2. 29 0.577 145. 86. 81. 78. -32. -58, -13, -57. 2, 30 0.908 139. 82. 76. 70. -32. -53. -17. -54. 1. 31 0.939 133. 77. 71. 64. -31. -49. -?0. -57. 7 32 0.969 127. 73. .67. 58. -31. -44. -22. -49. 1. 33 1.000 121, 70, 63. 53, -30, -40, -24. -47. . 34 1.062 110. 63. 56. 45. -28. -33. -26. -42. 0. 35 1.125 100. 57. 50, 39, -'6, -27, -27, -37, 0. 36 1.187 91. 52. 46. 34. -23. -22. -28. -33. 0. 37 1.250 83. 4.. 41. 30. -21, -17, -29, -29, .
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SUAJ: OUANE ARNOLD REIRC IN! ET. CONT.N0. CN245 BY:LMWP D4TE: 7-78 CHECKED: WL1rDATE: ? 7 REV: SHEET 4 0 OF Tg
-? POGR.AM 6666A CRITICAL TEMPERATURE DIFFERENCE REV JAN, 1975
EVENT 18-19 SUDDEN START
SEQ TRAN- TIME NODE NODE NODE NODE NODE NODE NODE NODE NODE NO. SIENT PAIR PAIR PRTR a4tR oaTR oAIR pATr PAlI PAIR
L 2 3 4 5 6 7 8 9
38 1.312 75. 44. 38. 26. -19. -12. -23. -26. 0. 39 A1.375 68. 41. 34. 24. -16. -3. 1-290 -23. 0. 40 1.437 62. 39. 32. 22. -14. -5. -20. 0. 41 1.500 56. 35. 29. 20. -12. -1. -28. -18. 0. 42 1.667 44. 30.. 24. 17. -8. 5. -2?. -13. 0. 43 1.833 35. 27. 20. 15. -4. 10. -27. -9. 0. 44 2.000 28. 24. 17. 13. -1. 13. -25. -5. -0. 45 2.167 23. 22. 15. 12. 1.. 15. -24. -3. -0.. 46 2.333 18. 20. 14. i. 3. 17. -23. -0. -1.1 47 2.5 00 15. 19. 12. 11. 4. CL3;-22. 1. -1. 48 4.500 4. 11, 7. 7. 5. 14, -12, 7. -2. 49 6.500 2. 8. 5.. 5. 4. 9. -7. 7. -2. 50 8.500 2. 5. 4. 4, 3. 6. -5. 5. -1. 51 10.500 2. 4. 3. 3. 2. 4. -4. 4. -1. 52 12.500 2. 3. 2. ?, 2, 3. -3. 3. -0, 53 15.833 2. 2.. 2. 1. 1. 2. -2. 2. -0. 54- 19.167 1. 2. 1. 1. 1. 2. -2. 1. .
MAXTMUM DTI ERENCE 165. 110. 141.- 163. 5. 18. 196. 7. 6. 4INIMUJM OIFERENCE -279. -276. -238. -230. -33. -134. -29. -65. -2.
(1)
SiAJ: DUANE ARNOLO RECIrC INLET CONT.NO.9CN245 SY:LWP OATE: 7-78 CHECKED: /LrATE: 217 REV: SHEET 4 OF 73
CSI NUCLEAR COMPANY
Primary Plus Secondary Stress Analysis
A finite stress analysis was used to evaluate stresses for all the critical transient times determined in the thermal analysis. Stresses from concurrent mechanical loads are determined separately and superposed with the thermal stresses. The finite element model used is identical to that used in the thermal analysis except the water elements were removed. Stresses were determined at critical locations shown on pageSS-4.
It was shown in the thermal analysis that event 18-19, Sudden Start of Pump in Cold Recira Loop, is by far the most severe thermal transient. Consequently only the five critical
times for this transient (See pageT-40W will be analyzed for stresses. Concurrent at each of these times are the following mechanical loads;
1000 psi internal pressure
Adder pressure of 315 psi or less
Safe end and sleeve piping reactions per Table 1 of
the Design Spec (Rev. 1) except Mz (see Page /3 )
To facilitate the analysis mechanical loads -are divided
into seven cases as shown on pages 5-5-61l. The design hydrostatic test, event 2-3, was also considered because of its
high pressure load. Thermal stresses were set equal to
zero for this condition.
Two dimensional finite element programs (1992 for axisymmetric
loads and #1037 for non-axisymmetric loads) were used to
generate stress components for all loads. All stress components
were then input to program #1684 which determines the stress
intensity ranges. For each selected temperature distribution
(see page 4;) the model nodal point temperatures were punched
SW7C T.-A Mace~ * J I.vL
OA4KC S? / GOP
Ca NUCLEAR COMPANY
on cards. These cards were used as input to the 992 program
in which the thermal stresses for each distribution were
printed out at pre-selected cross sections (see pageS34) and cards punched for later use. The program assumes an
initial temperature of 700. The 992 program was also used
to obtain stress component cards for a 1000 psi internal
pressure, a 315 psi adder pressure-:and axial pipe loads
on both the safe end and sleeve. The 1037 program was used
to obtain stress component cards for shear and moment load
on the nozzle safe end and sleeve.
The 1684 stress range program was then used to calculate
the stress intensity ranges for primary plus secondary and
peak stress categories (used in the Fatigue Section). This
program, using the previously punched cards from the 992
and 1037 programs, works on the principle of superposition.
For each combination of events the program independently
determines the maximum component stress range due to pressure, mechanical load, and temperature, adds the resulting values,
and determines the stress intensity range. The program
accommodates pressure and mechanical load "scaling* factors
for each event (see pageSg-12). Additionally, the program
determines these stress intensity ranges as'a function of
circumference (0 , 900, 180o. and 2700a) and prints the maximum
value at each preselected location.
The resulting stresses were then compared to the 3 Sm limit
as prescribed in paragraph N-414.4 of the Code (Ref. 2).
For points which exceeded the 3 Sm limit for primary plus
secondary stress intensity range the program performs an
additional stress range calculation with thru wall thermal
bending stresses removed in accordance with paragraph NB-3228.3
of the 1977 ASME Code. This process is permitted by Para
graph 4.6 of the Design Spec (Ref. 1).
S8j CC T ~c~rY j C ~G~~
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C8I NUCLEAR COMPANY
The results of this analysis are also used in the Fatigue Section of this report in order to arrive at fatigue usage factors.
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I 3A5 13', (0 Be
3176 I, ' ',
0t 73 ', 1a T r=
397 C,, ', ' ' s
-9A) H~c gp eyg m= em u nT n
S(JOOENI sr AT 0 .215 MINI.
U-) C 4r I rl NS-tI G-A 41- StGA1d ZZ S(',;+ TT S t 'M41A ~Z SEtGMA RT SI;AA4 u
43 11 3'A 7 97Qctq.
14t 7'85-9. 57770* I~7.
13 . -75615. -73377, ~7 .0
13 ) ~ ~ 0 556,4.1~57f) 7.A
31 0) 39777. 3r14A 7~ -A
31' A. -38813. -~74 1 ,. 734 ,'
13 1 -497. -479n.A~.
3:37 -4,AA no~
rt~I )(JA.NIj AR,'\flY) 41- I C T'\it§E=T cAi-- ;\Ifl \jrl..
MEEqI-4ij Av,)Anpj T -EMAI- STRzssi S
L-Oc4r1'TI SE[G-4 R-7 SEGM4 ZZ SrGM'A TT STGAiA RZ SCGVtA ~R S rG-i '3Z
179 171
CL. -575 T4 3 71, ' 5 ~ ~
I ge
I -
- - -~
***MEMA4ANE ANDO AENGOING THETM4GL STR"5555 *** 500Ne START ; 0.663 AFIN.
IOCATI ON S-1GA li SIGM A ZZ StGMA4 TT SIGMA RZ SIGMA IT SIGA UT
45 -i 187 -7Tq. o
49- . 1515. 17 ,c n ,a
141. -29455. -&q21. .79713, '
136 0. ?851S. 32q73. 373. ., '
191~-!, 5. - 512. -13303.1 5 . .,
17, 0. 25915A 3.10, 1o5A, *
21.4 1. -19906. -190qr43, ' , ,
215 . 78891. 7590 349, ,n
310 0. -. 7 77. -74135, -63A, ', 1
* 3(30 '. 23192. ??%6v64, . - * ' 1.
130 0. 5889. -2231. -1 55. . '.
135 0. -A294. -15&45, -1l95, ,
391 08 8304. 5177, T5, 5, 0.
- 397 0. -7875, -1297i 551,.
SU .I O AN R~t, R CIC TMI,=cT !;A== amn ray OmT.mn,. 9Y:L-.q OATE:13/7-i CHEC-KED: e/,; rDAT=: O/71 Z=-v, S 4=B=T O5
t.s't-.
MEMARANE AND RENGING THil;A4.. STRESSES
/.377
UOC4T -\ SIGMA '44 SIGMA 12 SIG4A TT SIG.4'd IZ SCGMA rT St 14 T
14 0. -747, -9005 , 13)
136 957,,
91 M. - 5 . -A T , 772,0,
176 0. 9309. 5524, 217, (, .
?14 M, -7 7, -'s77 n 771.
7199. 714-. 273. .
IS 3e) -71, 7 q74 -71-2
3 91 7, -Z-60 , A ,
397 ,- , - @ 0 - A ,,
9Y:y'-Do DATi:0/79 CHECKED: /2.;r ')ATE: 7SHi T 25-''JS'
0 IPDOIMQ. ST, AT ~ 2.5 o*.4IN!.
L'IJCATTrIN SIGM4A R-1 SEGi'4A ZZ StG-4'l TT Sl'A,,A RZ SP 4 1 T S 1G4A 4 T
4.5 -17 7. 3 , I ~ AT
136 0. -173 i 0 5
17A) np5. ~ 73 ~ 4*0
2) . 3479. 1641.. /-9.n
31) ;) 070. 2q 5
130 0. 77Q5* .4
i.35 0. 743 . ?756, -7.)'
3370. - 7f'97 -171q q
- ---.----.- a----
Mp** MEAANE+BEgI)NG+oEAK 1N RMAI. STRESSES ~ I OIFSfr HYORO] TegT
LOCAIrON SrGM A -R -SIGMA ZZ SIGMA TT SIG.1 RZ StGMA RT SEImA ZT
45 0,
141 0n n, n
136 n.. o.
317' 0. 0. 0. 311 0
301 0. 0.n 0,. n, (, .
131 0. n. ....
135 n, 0 An n.,
3.97 n,0 ,0 ,n 337 . 0, C., C.. 0, .0.,
SIRJ: r)IJ AR\if 0 RFCT'nr'is cT m n-. enMT, n.
93Y:'_.;4 OAT!E:09/78 CHECKED: Ar -TE: ?/.7f lEV/, SHiET 27 ( Sg -9
___* MEM~AR ANe+8NOIN.oK THEiRMAL STR=SSS *** SUoooN~ STr4T 1 0.215 MINm.
LCATION SIGM4 R- SEGMA ZZ SIGMA TT SIG-MA RZ SIGMA RT SIG4A T
45 ri, 85379. 87330, C,. n, n
49, 0. -50631. -29503. 0, C,
141 143:. 4f1?9. 72342, 75C,.
136 -2076. -1140. -13357, -. 9nn n, a
180 0C - n 197, 16F,99 . 'I ,, f
176 0. -56655. -2471. 0. m, I
21.4 0, 55549. 54TST, A. ',
210 0, -51941. -. 39EA C, ,
311 Z- 51639. q59qA. 0 m
300 0. -31183. -339Q1. C). C. *
130 7399. 1;323. -2825. -11475. ".
135 -879. -5281. -T074,. 15z, m) a
391 0 5030. 7Q6. 0. m,"
337 0. 3285. -?A46, C, C, 0
S[JA.I: )gIJAN- ARNfI r) -FI1RR JMl r F ICt rntit. Mfl,
9Y:Ly4P OATe:03/78 CHC'-,KED: )0g-rvOATE: P/7f 45V, SHrT } (1 )- =- r I
si~r~.i~rr** MEMBRANE+A NO[NG(oi TH9ERMAi4 .STRESSES. S91100 i N ;TA4T T) 0.57ti NTNI,
LOC4rIoN SIGM4 - SI GMA Z Z SIGM.A TT SE'.A4 RZ S[G-A RT StG.d 4
45 7177n, ezT7l 2 q n
49 0, -59934, -77920 IQ ,,
T41, 480 13461, 67nl0, n5s n,0
136 246, T43, 7I, o0&
13()0 44h439. ',034A, I. *,
17, . -48337. -9Q7, 0,
;p4. n 4494. 4.5TA, z5 7q
". 8 -4893. -31394, Q, '. 1.
31i 0 396-15. 'A02p1, nn0,
TTA 11734.. 7971, -1971. - n'54 n
135 -7 n91. -A,69. -5oA;A9 1A7A. n. a
391 r, 1 0 &T, 7 17Q7-, n,
317 (1 -0AAIs , -71 2c.;,8,
9 .: ta e ARaInt 0- Rar-C Rr TNf all = -r r ty v ntay, M,m AY:2.4Lo OArT:)/73 CHCK: ;r DAE: P12f k V. T O
-TiI
****MEMAANESENGNG+>dK HZERMAL ST-RESSES * SU0D9N STAT ) 0.663 -AIM.
LCAriO SIGA R SIGMA ZZ SIGMA TT SIGMA RZ St GMA4 RT SIGMA U
4-5 0, -78735, -34 ,. ,.
49 ti -17771. 50746 0. n
141 -1828. -51236. -75R47' -Q67.q. " 0.
136 3157. 18467, 1.L5, 765, 0. 0
1.83 0. -37681. -76757, 0,
176 0. 18025. 26160..
214 0. -30396. -3107 . n, ,,
21.0 0. 10425. 16732, 0* 0*
300 0. 1367A. 19977- *r'. n,
130 6497. 16179. 2t57. -10751. 0, *,
135 -387. -7374. -7723.q /_A n,
391 1, TA 45, 7. n, .n
387 n, -1737. -l4q. 0
SUL.: UAEN rN- 7 CHRt (E0 R,='TRC T;\/1-=T 2 "n.uT, 3o . 9Y:L-:4 rATE:09;./78; CH=ECKED:: rf DTE:/? P1,P -\. S L4z-T-30 0 5
~IJD~I ~ *MEM94ANE+9+i"JO1tN'+P--A< THRAf ST ESSES
/.-37E'
IJCATroN SIGMA R4 SIGMA 7ZZ StG;IN TT SIGMA~ RZ SIGMA RT StG.AA .
73'6 -177 77q 72.77
37 T. 71~%, 46%,. -A.
S'Jck.1 : QUANI= ARNMI-0 RC' TRr T.,,ti-=T ;Ar-= =:\in roNIT, flin,
3y:!-,40 DATE:13 I /7R CHE :KEO: o A r P/7-F i=v. S T,3 1-3 5
MEPi9 4NE+BOt1N G~1 H~ aSrI=ESSC
0 CA T ION S. G M . StG4'A Z Str(GMA TI T S M Z STG-iA -RT UEA .
45357 1. .
49 . -919. 3"(3* ..0
1*36 -440, -2572. Tef. -04
131 0. -?733. -5147,. *1
t76 0. z 3785g. -4', I .. 0
?IJ9I f )Jlj ~ r) .~ 1R 19~ AT 7 T77n- n.IO
311IA n&E1/3CEC,:~rvr: /8v ~
*** MEM4B-ANE + *BE0ING STr*SSES x***
UNIT MECHANI(:AL fLado R ESIUITS FOR r;;m cA mn771 P qwr-ce
LOCATION SIGMA R4 SIGMA ZZ SCGMA TT SIGA4 R Z StGrA RT SErG7A . T
45 n, 35 174, -o(,
49 0,Tys5 , Iay -. ,.m,
T141 , 394, -7, -7Q T -7
136 0, -_A m v,- 76, -7-413131.
176 0, -19,
0 -37. -Q -7,- T
31n n-721100 T a , 7 c p 310 . -71 , 7,A
TO . > , T 7 ,A T
391 14. A1
317 n7&, , i 749
SIjq.J: nji\m 64.rNji 0 7=rTyr TyI =T c = =o rnrNIT NIn, qY:-4P OTE:T3/79 CHECKe): 4,)TE: /7d' 1/. S HT 3 *JAp)
a - -.
** EM8AN5+ E'llNrN ST-7,,iS;*=
iNI T MeCHAfNI>A1L 1O4 RESUL'..TS FOR CASE 6/NnZZ',-r AnmrENIT
LOCioflN SIGM4A 4 SIG;-1A ZZ SIrM4 TT Srr.iA RZ SIGM A T SI-.4A r
450, 1977, T /5 7. -715, -"7, -A ,
49 - 0. 1706,4, 41 , -7A95 -47
141 0. 4374. -417, -57n. 57, -947,
36o. -Z-088. -3 63, -57m. -275 - .
19 0. 1839. -133. -337
176 0. -177r) -74-1T, -33R T, d@
214. -71
310 - O. 927, -13o, - 7, -1, 7
30 TT7. -1
130 0. C,5271 43 -41,
1357 0. 3RT, -&5. -1. -A7,.
'317 , 07 5 o -47.
nUA i Am r: ARA R \ 4F-I R r Tl ET SAP= =:Mo gn.\T, n, A Y: O ATE1 1/7,3 C HRzK'D: 0 -)AT=: /VIX IiV.SHT -
L-OC4TtO" SIG-Ma RA SIGM.A ZZ StrGi4 TT srrima Rz S CGMA ~RT SEGAA Zr
4.5 1154. 725 Q. -7C57. M 1.
-757
17( If)t 7 -7
27'.A -1Tm37 titinO -Al -1?i c Hz 3c1-3
FOR CA~r:2/315 OST 100ER01S
'.JA T I 1\ S(GM4 S SIGM 4 Z Z SEGM TT SIr;A4 RZ SEG-44 RT SrE-44 U
4.5
49
141
i.36
7 7',
74
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855.
17
171 fl.
2 q 1
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'>7L.. 7
41 ,
4,1
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I,
I-'
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C,
I,
3111~* 99 17-4-4.74
3111 E35. 23z1.
13n~ n4Q 74
131 74q z7.
w q!
I,
I,
I, -A.
MEB'4N'\- + 3~)'J rs~
UITr MECHANIt~l- fi) n~ U9T A,;~1 -A /rNin7 7 1r A YT A I i ri,,
'.JC4TM'N SIG4~ R' SIGM4 ZZ SEGM4A TT SIGMA 4Z SCG-M4 RT S r -7-4 7.,r
4-5 'a10. TI 40
49 Cl. 599,
141 n, 767,. ~
(1,. 10
176 .- 4 -1. 1il ..
304, -2. A. -7 , 0
371) T. 7 50 ,g.
317 0 19. A9 9K
FRY:I'-,,40 !)ArE':1979 OH'( :0Ti: S/) EiSL4 T 30 z
*Z MEMF3RA'Mlr + E'.n STRESSES **
LO C AT 113N S G~A A SIG-44 Z~Z S t'7AT~ TI .slf.'AA RZ StIGM~ A -Z S G14 77
415 11, 77&. .. 7t5or IT ~
4q .I-'.
136540. 311, r 1?5.
: .0. -1.5;3 417*' 0
31. r. 191L&. -1 7q M
135 .1773. ' '
391r Sv W3.2 iv T ..
O A E 0 3 7 3 CjI4 A = ' 2 = \
*;*~ ME14ARAN=- + 3EAiOINIG STIESSE-5
141 0- /77774, r,
7,1 1137 - -67
176 1 9 q- -17 77
2135 &;7 -- A 1107 -70 -Ic7
r))').I ArVJ !i\ ARNIM-I ') U=' TRC T-\I,- amr r Z\),\fliT. "0
l')T=:;4/;3CH=-,KF) Rrmr!: F/2h' 1=/.1; Tr
MEM'idNE + 81(N + PC-dK: STRESSES
UNIT M'CHdANIAL 6040 RESULTs
0~O -AST 1/,3Zi Sr.i R-1
LOCATION SIG.A R SIGMA Z1 SIGM0 TT SIf'41 4Z StG4A T s144 zT
45 0. 61. 137. ', . 403,
49 0. 1392. 44R. . 437,
141 15, 407. -97, 77, -Q. -49.
13"A -9?. -536, -a1,. -7 ,. -II ,
1r1 -. 13. -17. 0. 0, 10
30. -. 13 0. n, 7 301 4.0 207,1 . .n
30 1347. 7. 7 , -- A0 -. A A
135 . 9-9 ,-2 -7n. I7-.
391 08 91, 09, m, 'q
317 0. 77q, 1, .
SUi.j: 0:T~/73 1C IRC vt SaF N/0 aOT an. \n )471A 3Y:L-4 OdTz-:14/78 CHCe: Oz AE ff E.SHE a5
**~ ~ + DE'~~J,4 E'A< STlrSSES
UNIT MFHAIE -.4 1-1040 RzSlj'TS
L-OCATJO S[G4 RR SIr'4a \zz stGM'A TT SIGMA~~ 4Z S CGMA R T SE' T
450. 17T77. 1 51
14- 163 4.8 C; 'A
2114 -9 -. -3 A R & 111
31(0 15,5, -7 T
391 0. 32 2-. 0
317 -. 4.f:.f
*-- MEMR ANE + 9ENI)INq + PEt STrESSPS *- *
UNIT MECHANICal_ I~lOAO liESULTS PrOR CASE 1/1000O o)S PRESS
LOCA r lo SIG-A4 R4 SIG.A ZZ SIG:.A TT SIriA RZ SIG-1 A -.T SIGAA ZT
/45 -T070, 11 717?,0,0,
49 fl 5593. 75qq, n. I'.
141 -969. -i&5. ?',00'. 1 All
136 -779. 293. 23q3. 535.
LAS -1 nno. 696 137. .
176 . -641 797, ..
. -17W00. 13. -59. e
31A -i10. 119". -132. '. '. _,
310 -1000. -1112. -1921. 1. A. '.
32343. 732 . 5 -5775, n, '
135 -,. ,-1270. 17,f, 51g, R, '
391 -700, 3996, 4,. .Q7
397 ,9 54(79 5. &7
SUn.I: fliJi)ANr dRNOl-1) %ECIRC TNILET 56Fr -Nf eflMT, NIn AY:L-4 O AT=E:,D/78 CHErCKED: &r -)AT'=: If SEV SETz
UN~IT *,i-CANJV:AL !-fnl'r) Si
L-OCArEON StG-44 R- SIG;44 ZU S[--,;1 TT St;4 A 1 S TGM A ~T S EGA 4 Zr
49 0. 127 1 77Q r.
176', 770l3, ZQ4
214 -115. -. qq
2Q4
UNIT 1-0,111~~ yJ'V SJI-TS
I...rJCA~~~lfJN SE4 E 3 /1\10 Z Z I-GF A T tM SE,04 A~ 0E A 7
4 5 ' 144. I'. .0.
147tO.777 . -- 7. s5.0.0.
1 3',
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31115. , .
130 156. 3.97. 3-p4' 0
135 3. 15. -05.'.*'
3Q1' 279. el ' '
337 ' 2(10. -. I.*
C3Y:'..40 OaTrE:r/79 CH'EO(EO: D~~ ~E
*** MEBRAr'E + BENflING +- 0'V4 STrESSEs
UNIT MeCHdNICAL Ll04) TAS1iJ.T) C09 rVR £&/'I cave iVTAI I ('An
r-OCATION\ SIGMA RR S IGmda. Z Z S EGMA TT SI.GM,-A RZ SIGMA IT SI174A T
49 0, 7A 27 ,0
14.7 35, 9AO, ,
136 119, 695, 132,07
19,1 0. 41. 940 , ,,
214 0o. -126. 44 ,0
211 71T,
31 1 0 'T ,-A ,
30 0 0 . ~-77-, -7
13---90 -777, -'"
131T , 75, TT1, -4T,
317 An-?Av
51)T.t: TI6Nc *R\I1 g qFCyg( T\'I CT SAF ;:\0 fn.,iT mn,
9Y:!.P OdTE:m3/78 CH CK D: I ATREV, S4 T 4 -
4EM4A1E + AeSI T + S SS ES
UNIT M4CHANIC'.. I.Oda RUSillT FOR CASE 7/SL~E'Ev SHR P mnm
LCAtlN SrG.d R SIGMA Z SIGM TT SISMS RZ SIGMd RT SE;44 T
45 0. 1561. -977, 0, 0, 243,
49. 0. -1l57 . -1937. 0. 0. ?
141 180. 5052. 2444. 954, 153, ATi,
136 839. &907. 757q 09. -23. -57
130 0. -&73. 2734. . -177.
176 0. 13585. 6651. . 0,
214 0. -1192. 2296. . i
210 -0. 13091.
310 0* To 55,- -son, 00 - l7 ,.
300 0, -3/0. -37&3. 0, .0. -1OT3.
130 -1315. -3774. -q2-3. 2075. -7-7,
135 30. 183. 355, -75, -27, 7
39t , - 9 .- T,0 ,? I
337 1. -1262. 21. r. ,.
SUJS.I: m)if\I s v Or 0 R TRC TMI"Y T S;Ai =-\If Cr.\'T . \n. 3Y:l4P -A'Tr:a3/73 CH;CKED: e-r i)DAT=: S/y =.!=T -
CSI NUCLEAR COMPANY.1Fatigue Analysis
The fatigue analysis was largely performed with program 1684. The primary + secondary + peak stresses shown on pages -E were obtained from program 992 and 1037. These stresses, stress concentration factors and fatigue family data were input to program 1684 which calculated the fatigue usage factors for each point checked.
PagesFf-fo are computer tabulations of the partial and cumulative fatigue usage factors for each point. Page F-7shows how all the significant stress cases are grouped into fatigue families for program 1684 input. Cases within the same family may not combine with each other.
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*** A~ttiEtJS~'~AT :)r[-\r 31.1
TnT- A Al f v~A
t~IZ
TR MStIENT' SAL-T Nn, AL-LOW MO.* DESIGN PaTt;UE
SS-1.56b3 49.0Q4 7-Z265.13.
r7E-f;H'..O 70T0
***ArTG1JE ISAGE AT OnrMT 31c)
TOTAl- IJSrr= n~'.
S131,71 5 21.2 >L!663 731. 0.0
P-ATr~t;E IIS4(-, AT OflTNIT l3r
T RAS IENT SA-LT 41--O Ayl 0) [E-tG\I
SSO~.570 37.52 99613. 155.
SSZ. 5 1.2.4-1>10.;,- 1.55. 0.0
PA*GJE rieIISAGE AT OrITNIr 135
U TfTAI- II;ArP=01
TR -4S T E-NrT s4 i-r NIO 0a 41-1_0W -\I 0. ) ES t GNFT
S91 .571 S S2 5 9 73 > 1~*r 731. 0.
-0E1173 0
**:: 4ATIrmlC A~; T OOTNIT 3- 1
T RA14S EN TIr SA4IT \JI 4 -1 . 10. 1) -S G, I TG T T ;, K U 11 C- r(
SS.6 3.15 11 * 731. 0.0
~,:.. O AT=-:')/7.;3 ?1~.(0 47'V~ '7,f --)zo1.
F=ATIGUE USVE AT 0flINT 3;;7 *'
*~N) TiTA' U;Sa'= n.0
TQANSIENT SALT NO. ALLOW Air. '5fGN PAT('UE TTMES (KCT) (71 =s : p7 Y<- p
SS2.5 6-57 >1.i f 731.. 0.0
SUA.I: nipsNi A va\in 1.lg T 4 SA;= ;=:\n rnaIT, imn.
RY:L ATE:04--/793 C:HEaC-K=: X-7r AT: f0 M. H1T /
C31 NUCLEAR COMPANY
APPENDIX C 3
TEER4AL ANALYS IS G=F
944ISJ CCT
=HRM AL ANALYSIS APPENIXhAcS. my C"Ka AT C)45G 0M.
DLR DAra MeS ,.1
6/73 AT. ~ 1 *orC3
APPENDIX C3 - THERMAL ANALYSIS GUIDE
CS NUCLEAR COMPANY
Revision Log Sheet Rev Date: 74
This sheet contains a list b2- page number of the current revisions
to Appendix C3 The most recent revision Cs) is denoted by a
"' "mark..
PAGE REV. NO E. EFTE CTIVE DATE
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1JE A A THERMAAL ANALYSIS APPENDIX
9-21-73
6-15-73
6-15-73
6-19--73
6-19-73
6-15-73
6-15-73
6-15-73
9-21-73
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9-14-74
liiiCC BY C.KC at. ?A~~IO
DRE w FCV?~xC
I
~0 0
-........----. -,~-- -"c.~* - -
CSI NUCLEAR COMPANY
TABLE OF CONTENTS
Subject
Introduction
Definition of Variables
Material Properties
Conductivity of Water in Water Gap
Heat Transfer Formulas
Guidelines for Determining Mode of Heat Transfer
General Methods for Determining Flow Rates
Graphs for Determining Heat Transfer Values
Page
C3-3
C3-4
C3-5
C3-7
C3-8
C3-11
C3-14
C3-18
r______ n___OEM&
III.
IV.
V.
VI.
VII.
V11.
[us~~T '4 ?~7 V
. . w
ow c7 -cn ,
CI NUCLEAR COMPANY
I. INTRODUCTION
This appendix describes and defines common properties, formulas and methods used in the Thermal Analysis Section
of a stress report. In many cases this appendix can be
referred to directly by the T Section. In other instances
the procedures used here can serve as examples whenever
further analysis is required.
SUIBJECT
THERMAL ANALYSIS APPENDIX VDLR m IC3-A& e
CBI NUCLEAR COMPANY
II. DEFINITION OF VARIABLES - dimensions shown are used throughout the report unless denoted otherwise.
N Nusselt number (hL/k)
Pr Prandtl number Cc l/k) r p Ra = Rayleigh number (Lp 2 3gdTC /,ik)
Re = Reynold's number
b =,denotes bulk properties
C specific heat (heat capacity) at constant pressure, p BTU/lb--F
D = Diameter, ft
f = denotes surface film properties
g = acceleration of gravity, ft/hrZ*
h= heat transfer coefficient, BT/hr-ftz eF
k = thermal conductivity, BT/hr-ft-*r
T = denotes liquid properties
= volumetric coefficient of thermal expansion, 1/*7
AT =temperature differential, *7
p = density, lb/ft 3
I= dynamic viscosity, lb/ft-hr *
Gr -- Grashoff number (D 3 p 2 T/U-L
* Notice that many tables report these dimensions in seconds
L SJECGT MAGC mY CM C)ARGE MO.
THERMAL ANALYSIS APPENDIX DLR OATE I I C"ED
6/73 # 'r 4 o' C3
CaI NUCLEAR COMPANY
III. MATERIAL PROPERTIES - the following are values of various
heat transfer properties for commonly used materials. The
source of this information represents a compsite from
several sources. The three most frequently relied on
references are:
1) ASME Nuclear Code, Section III, 1971 ed.
2) ASTM Special Technical Publication No. 296
"Report on Physical Properties of Metals and
Alloys from Cryogenic to Elevated Temperatures",
E. A. Eldridge and H.W. Dean
3) Steels for Nuclear Applications, U.S. Steel Corp., 1967
The properties are reported at a temperature of 300*F. This
represents an average temperature experienced Crange from
50* to 550?r) and the variation of the values were found to
be quite insignificant.
A. Carbon Steels - SAlD5Gr.2; SA516Gr.55, 60 or 70;
;SA508 Cl. 1;
. = 29.1
C = 0.121 p
p - 0.283 lb/in 3
B. Low Alloy Steels - SA508 C1.2; SA 533Gr.B Cl.1:
SA540 C1.1. Gr.B23 or 324
k -29.1
C = 0.121 p
p = 0.283 lb/in3
.5 5J x T
THEIRMAL ANA-LYCATZ
___.i~73t ~ 3SP~5 a C23
C31 NUCLEAR COMPANY
C-. Stainless Steels - SA-182TP204 or 2Q4L.; SA351
SA336 CIP8 or F'8M; SA213, 249, 312, or 376TP304,
304L, 316 o=- 316L; SA2.40TP304, 304L, 316 or 316L, clad
J. = 9.35
C O. 2-7 p
P. 0-O.290 lb/in3
D . Nickel-chrocme-Irzon Steels CInconelj - SBl66;- SB167; SBI68
It. 9.50
-- C =- 0.120'
p = 0-305 lb/in 3
-- THERMAL ANALYSTS APPENDMIX
. .... ... . ..
CSI NUCLEAR COMPANY
IV. CALCULATION OF CONDUCTIVITY OF WATER T WATER GAP - Analysis from Reference 7,
Nu = C (R a . s a) CI . = b L/
let ht = special heat transfer coefficient across the water gap, BTU/hr-ft 2-*F
substituting:
h3L 25AT q 0 3 3 Q M74 hiL =C SqTC .s (9 aa
2~~ ak ](1r)
where: L .= distance across water gap,
AT - temperature differential between thermal sleeve - surface and nozzle forging surface
C. =- 0.049-, the average value from reference 7 from heating all around the annulus
let ik', special equivalent conductivity =htL
then:
L. = h -L = L kz926gAT C ] 13. 71 4 (pr)
2 Q.3%30,97 kr = 0.049 Lk - AT (Pr)
A Value of the conductivity of water in the water gap can be determined by estimating values, based. on previous experience, for the average water temperature and AT. These estimates should be compared to the results obtained from a thermal analysis program in order to determine their validity. If necessary, modification may be required.
O
THERMAL ANALYSIS APPENDIX DLR OATE 0. E g C D
6 73 V 7A "Z OSNr. 7 Ov C3
C3 NUCLEAR COMPANY
V. EAT TRANSFER FORMULAS - the more common formulas used for the calculation of heat transfer coefficients in a thermal analysis are presented below.
A. Natural Convection of Water - inside surface of vessel or nozzle
he L 0.14 Gr r .3s
substituting and rearranging:
h 0.14 kc (Prj Z)O~3
The above formula represents a conservative approximation of a number of equations from different sources. For the case of a vertical wall, page 339 of Ref. 14 shows
the above equation with a coefficient of 0.13. On page
340 of.the same reference the condition.of a flat plate being heated from below (this is analogous to the top inside surface of a nozzle) is represented by the same formula as above. Other orientations of a flat plate are found to yield smaller heat transfer coefficients.
Page 180 of Ref. 6 relates the.dimensionless quantity -
2r= Gr. aPr.to-various-formulas- for .natural convection.
Again the equation presented here was found to result in
larger heat transfer coefficients.
The above formula can therefore be conservatively applied
to represent the entire.inside surface of a nozzle.
THE -RMAL ANALYSIS APPENDIX
CSI NUCLEAR COMPANY
B. Natural Convection of Steam - inside surface of vessel
or nozzle
h = 0.14 Gr Pr .33ar --- L 1
substituting and rearranging:
ha 0.14p ggC k2 s
Vo '7 here: S = =.(T o ) T
To= actual temperature (saturated conditions)
ve = unit volume at actual temperature
r'- incremented temperature
v,. unit volume at TI. with To -pessure ._superheated cond-Itions1I
C can be determined from the chart on page 293 of p
Reference 37..
The discussion in Section V. A of this appendix applies
to this case as well.
C. ForcedConvection of Water or Steam - inside surface of
vessel or nozzle.
hLD = 0.023(DG ea0
b
(p. 219, Ref. 6)
SUAltCT
* ........- -c.~.--. -----. - . -........
CS1 NUCLEAR COMPANY
wbere: D = hydraulic diameter, ft.. Csee VI for specific descriptions)
G= mass velocity, lbs/hr-ft7 C= Q/A where Q is the flow rate in lbs/hr and A is the crosssectional area of flow in ftzl
rearranging and substituting:
b= 0.023 oD s Pr
D. Condensation of Saturated Steam
1.- Inside
. =
Surface of Vessel
0.943 PI g~T - 5 k J 1 sv s.
(p- 464, Ref. 14)
where T = temperature of saturated vapor
T"s surface temperature
p~ = density of vapor
yextical 1entLth4. moemmand using 2 ft..
h' =h + 0.375 C (T - T fg fg p s7 S
If it is
0.375 C p
equation
hi~
assumed that p is small relative to p, and that
(T 5 - T.) is small relative to hfg , then the above can be simplified to:
4 [p g hfq k 3 -*.2 0.943 1 f I -o&T s
L.
SUr THERMAL ANALYSIS APPENDIX
I
CBI NUCLEAR COMPANY
2. Inside Surface of a Nozzle
1 1 l-v) g h;C k3 h 0.725 1 T7 s
Making the same assumptions as in V.D.1 equation reduces to:
h 0 -725 L i 1ID[22 g i 0q k3
(p. 465 Ref. 14)
above, the
(AT) -0 .
where the definitions of the variables are the same as for those in V.D.1 and D is the diameter of the condensing surface.
THRMAL ANAM VqTs APPETifIX .DLR & CAT E I 3Z T I
9/73 ~
- .........
Ca1 NUCLEAR COMPANY
VI. GUIDELINE FOR DETERMINING MODE OF HEAT TRANSFER
It frequently becomes a concern whether natural or forced convection heat transfer coefficients should be used to represent conditions of a particular thermal transient. This section presents some guidelines and a procedure for making such decisions.
A. No Plow Case - whenever there is no flow present along a surface exposed to waternatural (free) convection should be assumed.
B- Flow Cases - the attempt here is to determine a water flow a.ove which forced convection can be assumed. 1. Flow of Water Along Inside Surface of Vessel
Assume a 251" 9 vessel with a 21 inch annulus spacing operating at 5000F.
let hL = free convection heat transfer.coefficient
h2 = forced convection heat transfer coefficient
From equation V. A of this appendix
ha 0.14 x 0.349C15.3xl0 x0.87)*.ss (AT) 0 - 3 3
h 115.0 (AT).a 3 3 s
From equation V. C of this appendix
0.349 ( 350 a0-s -* o8a h . 3.50 105.4x0.00071x360) (0.87)
h 2 = 0.000424 Qa.s
Prom observation of TGRV computer runs, an extreme value for AT during free convection cases would be 25*F.
Then,
hi = 115.0(25)0.333 = 336.0
In order for a forced convection case to be more critical
than a free convection case:
CSI NUCLEAR COMPANY
0.000424 Qa.s > h, = 336,0
(33 6. 0'l S0.000424= 23,653,08a lbs/h.
= Z'''~lbS. ft 3 -h= T____ 23,653,000 x x -dec 10.4f t' = 1. 27 t
Analyses were made for different size vessels and annuli confirming the velocity of flow as reported here. =t can. therefore be stated that,
any flow of water along the inside-surface of a vessel L excess of 1.3*ft/sec should be analyzed with a forced convection mode of heat t-ansfer.
2. Flow of Water Along Inside Surface of a Nozzle
Assume a 10 0 nozzle with a 40.P flow-.
From equation V. A of this appendix:
k. =0.14 x 0.325 2.3xl06xll.6).** CATM. 3 3 3
.- l3.5 CAT)*. 3 3 3
h= 0.023 0.325 a.s.33- - a 4.83-3 \0.545xG.00l04x3600 (11.61 Q
ha 0.0117 Qa.s
An extreme value of AT would be 500*F
h-= 13.5 (500)o-3ss = 107
In order for the forced convection case to be more critical than the free convection case:
ha > h,
ha = 0.0117 Qo* 5 ha = 107
* Note that this value is based on aA&T of 25F*. There are some cases where AT may be considerably larger and caution should be used when such case arise.
THERMIAL ANALYSIS APPENDIX DLR
6/73 277" OAr * 12 0' C3
~i~a- -
CSI NUCLEAR COMPANY
- (9.0117 ) = 89400 lb/hr
=89400 lx ft 3 hr 1 f 0.73 t hr 62-41b 3 600sec 0.545ft se3 c
Similar analyses of different sized nozzles indicated a range in the velocity of the flow from 0.58 ft/sec for a 4" 9 nozzle to 0.85 ft/sec for an 18" 9 nozzle. Further analysis of a particular nozzle may be desired but it can be stated that:
for a nozzle 18 inches in diameter or smaller, any flow of water along the inside surface in excess of 0.85 ft/sec should be analyzed with a forced convection mode of heat transfer.
3. Conclusions and Other Considerations
The results of the above analysis may be used only when the flow velocities actually experienced by a nozzle are greater than those reported here.
The procedure used above could serve as a guide for detemrmining the proper made of heat transfer when a flow velocity is similar or less than the velocities determined in this section.
Calculations of the Reynold's number corresponding to these velocities shows them to be well into the range of turbulent-flow (Re > 4000) and illustrates that turbulence should not be used as an indicator for forced convection.
R- = vd e U
R (vessel) = 1.27x3.5x49 = 3,068,000 e 0.000071
R (nozzle) = 0.73x.833x62.4 = 36,500 e 0.00104
UBETMADE V C a CHARG5 MQ. RMAL ANALYSIS APPENDIX DLR 1 C3 7AT3 0/ 1
73 7 A1 3?13r'C
CBS NUCLEAR COMPANY
VII. GEERAL METHODS FOR DETERMINING FLOW RATES
A. Region between Normal Water Level to Top of Jet Pumps
includes reedwater, Core Spray and LPCZ Nozzles. The
flow in this region is assumed equal to the total flow
through the jet pumps. The cross-sectional flow area is
that of an annulus. In general, it is described by the
inside diameter of the vessel shell and the outside diameter
of the shroud cylinder. This is not always true and
reference should be made to the Internals Assembly Drawing.
B. Region of Vessel Shroud Support Junction (Below Horizontal
Plate).. The flow in this region is equal to the flow out
of the jet pumps. The cross-sectional flow area should
be taken as the average of the annulus area (between
the vessel wall and the shroud cylinder at the shroud
-support) and tht total surface area of the openings
between the shroud support stilts. The hydraulic
diameter is computed by the following equation:
1H o3 1 a
Where:
D O.D. of shroud support stilts
Do = 4.I/w + Ds'
A the cross-sectional flow area
C. Bottom Head - inside the shroud supports. The flow in
this region is equal to the flow out of the jet pump
diffusers. The cross-sectional flow area is equal to the total surface area of the openings between the shroud succort stilts, less CRD tube housines.
SundE£CT MGEC UY CAKO VU. C)4ARGE NO.
TERMAL ANALYSIS APPENDIX DLR JF I
OAT6 O oT£ Cl4*C
16/73 _ /7 OAKsm-14 as,3
C81 NUCLEAR COMPANY
D. Recirculation Outlet. Nozzle
1. Inside Nozzle - the heat transfer coefficient for any flow.-in this nozzle must be modified to account for
- entrance effects according to the following formula
Froan page 382 of Ref.:14:
h he + C]D/,L)a.*
where:
D inside diameter of the nozzle
Z length of the nozzle from the inside surface
of the vessel to the end of the safe end
2. Inside Surface of Vessel - the flow in this region
is given on the nozzle thermal cycle drawing. The
cross-sectional flow area is described by the inside
surface of the vessel and the outside surface of the
shroud cylinder, and is bounded on either side by a
line drawn through the center of the adjacent jet
pumps (.see. sketch. belowk. The hydraulic diameter is
defined -as--fou times the area described aBove divided
b. the wetted perieter (see sketch belowl. Vessel Shell
Shroud Cylinder
'Flow Area
Recirculation Outlet
Wetted Perimeter
Jet Pump
AU8J4G T ftsOc 15T C fteG N.
THER.MAL ANALYSTS APPEDTIDX DLR OATZ 1 A 0171C3 6/73 --r3
I. a
Tgr,'MATANATVqTSADDET'K
CSI NUCLEAR COMPANY
E. Recirculation Inlet Nozzle - It can be conservatively assumed that the inside surface of the vessel in this region will experience the same flow conditions as described in VII. D.Z for the Recirculation Outlet Nozzle.
F. Region of Steam Outlet Nozzle - the flow in this region is given on the nozzle thermal cycle drawing. The crosssectional flow area is that of a circular segment defined by the inside of the vessel and the steam dryer assembly (see sketch on page C3-17). The hydraulic diameter is four times this area divided by its perimeter. Notice that two nozzles are located in this region and that the flow.through the vessel in this area would necessarily be twice that for one nozzle. The nozzles themselves should reflect entrance effects as described in section VI.. D.1 of this appendix.
Q 2 i
CS NUCLEAR CCMPANY
-Locn
..............................................
A0
LO W .
MAC 3 CHRG NO.
6 73 - -1 t ..l . c
@0 4 caINc
CBSI NUCLEAR COMPANY
VIII. GRAPES FOR DETEMINING HEAT TRANSFER. VALUES
On the following pages are a number of graphs which may be useful for determining the values of various heat transfer coefficients. The graphs are based on the formulas presented in Section V of this appendix and are consistent with the units described on page 4 of C3. The specific values indicated at 1006? increments should be useful when using the computer program "HAP".
I U. . -
4U CC T y~ IT '' ~ IITERIMAL ANALYSIS APPMMZT 'DLR ,
OATS I D~r 18 -w C3
I
0/2
f'
0
f 9
= _______ ~ ~=i-4-~ -~ - ±_____
_______ -~ - h- 6 _______ _______ _______________ _______________ _______ _______________ = _______________ 4
- - -1 _______ _______________
I4-~ ± -~ - ' +-~4----- -~-- r - ________ 4-,-----.t-------- _________________ 4
___ ___ ___ ______ ______ ______
4~t~ ____ _______ _______ - _______ * _______________ _______________ _______________
4 __________ - a
~ -,-~-'___ ______ ______ .. -~ _______________
__________________________________
___________ ___________ ________________________ _______________________ 2 ~-~-- __ _______________
=6 __ __ __p__a 4 ~ 2 - __________ ______________________ __________ 2 ~ __________ __________ ~ __________ 2 ______________________ ______________________ ______________________
_4. ~ 2 __ 4 6 :..........................,
P - 4 ______________________________ I 4 6 6
a: - _______________________
_______________________
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a a S a . a a a 4 *
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4 = -_ ~ = F =~ -p-- ________ ~1 _ - -_
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'4 _______ ± . A ______________________________ .9.
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_______ _______ _______________ ~ 4-.----.-.------4..--..--..-..-.-*-.*- 2 __________________________________ __
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-a _______________ - -. - -.-- ~---
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- ., 9 .-. ~ . - - - r - 5 4 - -. -- 9.- -p.-- ~ -- -p.--.-- -. -9-- - - = -, 9 p.- - __________
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a700
____ I ____
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4 ________
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6 6 ____________________________
_____ __________ 5 ________________________________ ___________________ 4
u-i ________
A ITs 1n Fr, Ls.) +PZS, BM o F . P.2.3 o=4 C-3
CSI NUCLEAR COMPANY
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APPENDIX C6
LIST OF REFERENCES
RECIRC INLET NOZZLE
SAFE END REPLACEMENT
DUANE ARNOLD NUCLEAR PLANT
CBIN CONTRACT NO. 8-CN245
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CSI NUCLEAR COMPANY
Reference Documents
1. General Electric Company Documents
1.1 Design Certification DC22A5645
1.2 ProductDrawing 112D2504
1.3 Product Drawing 137C7284
ISVM.aLC T I MAOCp alY I ~~f
REERERCE DOCUMENT
L. General Electric Drawings and -Specifications with the
Acceptable Interpretations, Clarifications, or Exceptions
as agreed to by CSE Nuclear Company and General Electric
Company. See ___o__.s______
2. ASME Boiler and Pressure Vessel Code, Section II, Nuclea
Vessels, American Society of Mechanical Engineers, New York,
New-. York. The Edition and Addenda are listed in General
Electric Purch ase Spec 4 cation Data Sheet as specified L=
the contract documents.
3. Peterson, R.E., Stress Concentration' Desian Factors, John
Wiley and Sons, Inc., New York,1953,
4. Tentative Stuctural Desin -asis vfor eactor Presure Vessels
)andirectiv Associated Comorents. (Pressurized, Water Cooled
Svstems), U.S. Departet of Comerce,, Institute for Acld
Technology, PB 151987, Decembe 1958.
5. Gied!, Warrean E., Princi!les of Encineerinc Beat Transer,
D. Van Nostrand Co., Inc., Priziceton, New Jersey, 1964.
6'. McAdams, Willia E., Beat Transmission, McGraw-ill Bcck Co.,
Inc., New York, New York, Third Editicn, 1954.
7. Dropkin, D., and Somerscales, B.,."Eeat Transfer by Natural
Convection in Liquids Confined by Two Parallel Plates Whic.h
Are Inclined at Various Angles With Respect to The Earizenta1".
Reprinted in Appendix C.
8. Jakcb, 4., Heat Transfer, Vol. 1, Wiley, New York, 1949.
9. Sabersky, R.E., and Acosta, A.J., 7luid Flow, MacMillan,
New York, 1964.
.- % I. ': M&Q, 1r 8, 1 1 a--C4A G
e
... ..
10. Keenan and Xeyes, Theriodvnamric Promerties of Steam,
Tohn Wiley and Sons, New~ York, 1963.
11.. m"How to Evaluate Coefficients for Eea.t Tns Calu !a+--ion~s"r
Lauae=r; B. E. 'Reprinted front Vie Oi a -nd Gas 7ou--=a-l i n
Appendi-x C..
12- xarks' Mechanic.I Enci~ee~rs' Eandhook, Theodore Bai~eiSt,'/
Ecitor, Seven tb.E dItion, McIGraw-Hill. Book Compa-nV, New Yor-k,
1964..
13. Welding Research Catci-l Bulletin N\o. 2.07
"LOCalI Stresses in. Spheric;(al and. CvldriJcal shells Due tMO
External Loadings" X. R - Wichm=an, A. G. -c lp er, an-d Z..
fMe-shon, Welding Resear-c. Council, 345 East 47th tet
New. Yor!-, N,\ew. York% 10017, Aaust 1965.
14. Xreith, Frark, PrLncimles of Heat Transfer, Seccnd. edi4to n,
rnte~aticnal Textbook. Cc~paay, SrnoP~yvna 36
13 Sretr, V.L., Fltid vec!hani-cs, McGraw-=ilI Bcckz Compar,,
Inc-. , eq To r%, 1958.
1S- Weldinq Research Council Bulletin No. 106
"Stress Analysis of a Cir-cular Plate Co ~icaRctnur
A-.ay of Hroles", by Z.B. Mahone-. and V.L. Saler--c, Wel-4in
Research Cocncil, 345 East 47t6h- Streetl, New Yr, New Ycrk
10017, CJuly 1965.
17. Zudans, Yen and Steiglemann, Thermal Strs Tehius mr
ican Elsevie. Publishi.,ng Co. , Znc. , New York, 1963.
18. Craze CoMpany Techni4cal Paper ;No. 410.
19. Timoshenko, S. and rqoinowsk-rieg'er S., o fPae
and Shells, Second Edi-.con, LMcGraw-Hill- Ecck C^omprany, New
York, 1959. W10aY~~
O
~S&a IF. GOP
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CArZ I - - .I- .3 0
2C
v-I
21. Citerley, R.L. and Yamahara, St- T., "Stress Analysis of The
Killside Nozzle, A study conducted at the Anamet Laboratories, Inc. ,J San Carlos, California, for the General Electric Companv,
Atomic Power Equipment Department, San Jose, California, January,
22. Tagart, S.W., "Plastic Fatique Analysis of Prassure Comrcnents", ASME Paper No. 68-PV-3, American Society of Mechanical Engineers, United Engineering Center, 345 East 47th Street, New York, New York, 10017.
23. Chapman, A.J., Eeat. Transfer, the M.ai1=n CCoanV, New York,
1967.
24. Unified Screw Threads, ASA 31.1 - 1960.
25. Snow and. Langer-- "Low Cycle Fatigue of Lar e Diameter Balts", ASME Paper 66-PETS.
26. Diamond Pcwer Speciality Corcraticn of hazcaster Chic
Technical Bulletin 2606.
27. Test .Results, Model 2-5039 Tensioner, Biach industries, nc.
report of June 10, 1966.
28. Report No. 2 of New York Shipbuilding Cororation, made :or
General Electric - Exrerimental Stress Analysis Quarter Scale
Model - Penetrated Head - Dresden Nuclear Pcwer Staticn ?ressure Vessel.
"~'
Corn, J~.M., "A Theoretical and Experimental Investigation of the Stresses ina Circular.Cylindrical Shell With. An Oblicue Edge", published in Nuclear Engineering and Design 3 (1966), pp. 254-28i, North-Eolland Publishing Co., Amsterdam-
3.
29. Boley, Bruno A., and Weiner, Jerome H., Theory of Theral
Stresses, Wiley, New York, 1960.
30. Esu, S.T., Eineering Eea.t Transfer, D. Van Nostrand
Company, Inc., Princeton, New Jersey, 1963.
31. Reactor Eandbcok, 2nd. Edition, Vol. 1.Materials, C.N. Tipton
Ed., Interscience Publishers- New York, 1960 - Procerties for
Heavy Water.
32. Albrecht, W., "Eow Thickness And Mat-ial Properties Influence
Thernal Shock Stresses in Flat Plates and Cylinders." ASME
mamer 69-GT-107.
13. Langhaar, Henry L., "Foundations of Practical Shel Analysis,"
Dept. of Theoretical and Applied Mechanics University cf Ilinois,
April, 1962.
34. Glasstone, S., and Sesonske, Nuclear Reactor Encineerinc,
D.. Van. Nostrand Company, Inc., Princeton, New Jersey, 1963.
35. Roark, R.J., Formulas for Stress and Strain, McGraw-Bill Bock
Company, New York.
36. Advanced Product Co. Drawing 52013-1, Dated 1-12-G8
37. 1967 ASME Steam Tables, ASME
38. Peery, D.J., Aircraft Structures, McGraw-Eill Book Company, New York, 1950.
39. R.L. Daughterty, Fluid Mechanics w/Engineering A=olications,
5th Ed., N.Y., McGraw Hill, 1954
I LC. 7.AO elf)RG P
__ 0 j ,7)J 5 ~C6 swearc-9 C rct av -m at oMwse
40. AST4 Special Technical Publication No. 296
w'Reort on Physical PCperties of Metals and
Alloys from Cryogenic to Elevated Temperatures",
E.A. zldridge and S.W. Dean
41. Steels for Nuclear Appl.ications, U.S. Steel Corp., 1967
42. R. L. Roehrich - "Trquing Stresses in Lubricated bolts." Machinre Design, Jun-e S- 1967
43 Unified Screw Threads - ASA B31. - 1960
44. Square and Eex Nuts - ASA BI8.2.2. -196
