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PREDICTION OF RADIATION EMBRITTLEMENT OF THE
KOZLODUY NPP UNIT 5 REACTOR PRESSURE VESSEL
MATERIALS
NRC “Kurchatov Institute”
D. Erak, D. Zhurko, V. Kochkin
17 June 2016, Varna, Bulgaria
VVER-1000 Reactor Pressure Vessel
The temperature and neutron flux influence during operation
Radiation embrittlement (RE) and temperature ageing (ТA)
of the metal
WELD МETAL DETERMINES LIFETIME of REACTOR PRESSURE VESSEL
welds
С Si Mn Cr Ni Mo P S Cu
BM 0.13-0.18 0.17-0.37 0.3-0.6 1.8-2.3 1.0-1.5 0.5-0.7 0.1-0.12 ≤0.01 ≤0.08
WM 0.06-0.12 0.15-0.45 0.65-1.1 1.4-2.1 1.2-1.9 0.4-0.75 ≤0.01 ≤0.02 ≤0.08
To determine the mechanical properties and fracture toughness parameters of steels
exposed to the operating conditions it is required to test specimens made from the
same material as a reactor pressure vessel and exposed to similar neutron fluence
and the temperature.
a b
Charpy impact specimen (a); tensile specimen (b)
3
Charpy Impact Test Procedure to Determine Ductile to Brittle Transition Temperature
(T) = A + Bth[(T-T0)/C]
f - absorbed energy (J) or
lateral expansion (mm);
T – test temperature (°C);
A, B, C and T0 – fitting parameters
A = (upper shelf level + low shelf level)/2
B = (upper shelf level – low shelf level)/2
Parameters A and B in (2.1) should be related to the upper
and the low shelves of the trend curves and defined as
follows:
kfT
RPV materials properties have
Ductile-Brittle Transition Region
4
Lead factor К=0,5 – 2,0
F < 6,4 1023 neutron/m2
Expose time
T=310-320oC
26 000-200 000 h
≈27 years
RADIATION EMBRITTLEMENT (RE) & THERMAL AGING (TA) of METAL
Most representative data of RPV materials degradation are results
of surveillance specimens (SS) investigations
Surveillance program of VVER-1000 RPVs
SS Location
SS Location
5
WWER-1000/320 surveillance program
RPV material radiation embrittlement is controlled by surveillance program
6 surveillance sets
Each set consist of 5 assemblies
Each assembly contains 14 capsules with surveillance specimens
Surveillance
assembly
RPV
Surveillance assembly design
Each level of
surveillance
assembly contains 6
capsules with 12
Charpy specimens
and 1 capsule with
tensile specimens
Upper
level
Low
level
7
Surveillance Specimen Sets WWER-1000/320
Material of the Specimen
Base Weld HAZ
Number
of SS in
one set
Ch T CT Fat Ch T CT Fat CH CT
Type of the set Номер
комп-
лекта
Number of specimens
1К 18 12 15 9 18 12 15 9 18 15 141 Reference
2К 18 12 15 9 18 12 15 9 18 15 141
1Л 24 24 12 18 24 24 12 18 24 12 192
2Л 24 24 12 18 24 24 12 18 24 12 192
3Л 24 24 12 18 24 24 12 18 24 12 192
4Л 12 12 6 - 12 12 6 - 12 6 78
5Л 12 12 6 - 12 12 6 - 12 6 78
Irradiated
6Л 12 12 6 - 12 12 6 - 12 6 78
1М 12 6 6 6 12 6 6 6 12 6 78
2М 12 6 6 6 12 6 6 6 12 6 78
3М 12 6 6 6 12 6 6 6 12 6 78
4М 12 6 6 - 12 6 6 - 12 6 66
5М 12 6 6 - 12 6 6 - 12 6 66
Thermal Ageing
6М 12 6 6 - 12 6 6 - 12 6 66
Total 1332
9
WWER-1000/320The capsules with surveillance specimens are located above the core
baffle in a place with high neutron flux gradient
29
8
Surveillance
10
0.50
1.00
1.50
2.00
2.50
3.00
3.50
4.00
-180 -120 -60 0 60 120 180
angle,deg
Lead
fact
orLead factor obtained by RPV fluence calculation and investigation of different surveillance sets L2 & L4 positions (preliminary estimation)
Upper level
Low level
Lead factor = ФSample/ФRPV wall
11
The reconstitution technique enables to provide the representativeness of the WWER-1000 surveillance programmes
12
The CONDITION: it is necessary to measure fluence in the positions 1/4, 1/2, 3/4
Neutron metrology in RRC KI
evaluation of the fast neutron fluence for
each Charpy type specimen in positions
¼, ½ and ¾ using results of 54Mn
absolute activity measurements;
three-dimensional calculation of neutron
spectrum, taking into consideration
global power history of the core and
effective time of reactor operation at
rated power. Detailed data on geometry
and material of reactor zones are used
in the calculations.
13
Standard neutron dosimeters set
Aluminium
gasket
Aluminium
capsuleAluminium
plug
Cu dosimeter, Ethreshold =7MeV 63Cu(n,α)60Co T1/2=5.27 years
Fe dosimeter, Ethreshold =3MeV 54Fe(n,p)54Mn, T1/2=312.2 days
Nb dosimeter, Ethreshold=0.5MeV 93mNb(n,n`)93Nb, T1/2=16.1 years
15
BM SS of Kozloduy unit 5 RPV. Collecting of specimens into testing groups
16
0 10 20 30 40 50 60 70 80
0
5
10
15
20
25
30
Группа 2
левая половинка ША
правая половинка ША
центр ША
Флю
енс,
х1
02
2 м
-2
Порядковый номер
Группа 1
0 10 20 30 40 50 60 70 80
0
10
20
30
40
50
60
70
80
90
Группа 3
Группа 2
Группа 1
левая половинка ША
правая половинка ША
центр ША
Флю
енс,
х1
02
2 м
-2
Порядковый номер
Set 3L
Set 2L
WM SS of Kozloduy unit 5 RPV. Collecting of specimens into testing groups
17
0 10 20 30 40 50 60 70 80 90
0
5
10
15
20
25
Группа 2
Группа 1
левая половинка ШВ
правая половинка ШВ
левая половинка ШБ
правая половинка ШБ
центр ШБ
Флю
енс,
х1
02
2 м
-2
Порядковый номер
0 10 20 30 40 50 60 70 80 90
0
10
20
30
40
50
60
70
80левая половинка ШВ
правая половинка ШВ
левая половинка ШБ
правая половинка ШБ
центр ШБ
Флю
енс,
х1
02
2 м
-2
Порядковый номер
Группа 1
Группа 2
Группа 3
Set 2L
Set 3L
Ageing time, h
TF
TK
T
K
Fluence
TT
)(.)(),( tTFTtFT TFк
8.0
0
F
FAT FF
Existing normative approach for prediction of VVER-1000 RPV
weld materials embrittlement (based on data base of SS )
%5,1,18inf NiifCT o
t
),,( SiMnNi
W M
F CCCfA
%5,1,2inf NiifCT o
t
18
OTOT
TTt
t
tth
t
ttbTt exp)(T inf
T
The existing approach allows
-to construct a normative curve for particular vessel
weld based on chemical composition of the material
--to construct an individual embrittlement curve for
particular vessel weld based test results (min 6
experimental points with not than 2 durations of
irradiation)
РД ЭО 1.1.2.09.0789-2012, Положение 1.3.2.01.0061-2009
B. Margolin, V. Nikolayev, E. Yurchenko, Yu/ Nikolayev, D. Erak, A. Nikolayeva /International Journal of Pressure Vessels
and Piping 89 (2012)
45,1BM
FA
SS test results of base and weld metal ofKozloduy Unit 5 RPV
Матер
иалКомплект
Время
выдержки, час
Флюен
с,
1022×м-
2
Тк, °С ∆Тк, °С
ОМ1
Контрольный 0 0 -68 0
1Л 26016 6,9 -60 8
2Л 65208 6,74 -56 12
2Л 65208 20,03 -53 15
3Л 149496 21,28 -59 9
3Л 149496 43,72 -46 22
3Л 149496 60,72 -40 28
МШ
Контрольный 0 0 -47 0
1Л 26016 5,81 -26 21
2Л 65208 5,56 -29 18
2Л 65208 14,53 -16 31
3Л 149496 17,64 -25 22
3Л 149496 31,45 -15 32
3Л 149496 45,33 -9 38
CONCLUSIONS
The representative experimental surveillance specimens
test results for providing forecast of Kozloduy unit 5 RPV
materials radiation embrittlement have been obtain
Development of the irradiation embrittlement curves for
Kozloduy unit 5 RPV materials have been done
Elaborated prognoses allowed to extend Kozloduy unit
5 RPV life time up to 60 years of operation