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THE 4TH INT

MAN

4 International Conference on Water SuppMakassar Indonesia 16-17 Juli 2012 ISB

Water Cooling S

Storage of Spent

ation Safety Asp

Gunandjar

Sugeng

Natio

Kawasan

Phone 021-7563142 E-mail

The Installation of Interim S

of spent nuclear fuel (SNF) usin

Multipurpose Reactor of GASi

uranium fission product element

and radiation decays of its radion

or more On that cooling the SN

by transfer channel (TC) containi

has the pool construction contai

For maintaining of the water qual

performed by ion-exchange proc

cluding control rod The IISSNF

air temperature of 20-25oC and r

present the IISSNF contains 20

radioactivity contamination on t

targets The assessment of safedionuclides analysis of water sa

ion-exchange resin from water p

nation of the facility Based on t

system can be concluded that the

and safe in accordance with appli

Key Words interim storage of s

1 INTRODUCTION

On the operation of the Multipu

ERNATIONAL CONFERENCE ON WATER SUPPLY

GEMENT SYSTEM AND SOCIAL CAPITAL

Makassar Indonesia July 16-17 2012

ly Management System and Social Capital 978-602-203-124-6

stem For The Installation

Nuclear Fuel (IISSNF) And

ct on Contamination of Rad

1 Zainus Salimin 1 Lucia Kwin Pujiastuti 1

Purnomo1 and Dwi Luhur Ibnu Saputra1

1Radioactive Waste Technology Center

al Nuclear Energy Agency of Indonesia (BATAN)

uspiptek Serpong Tangerang Banten 1530 Indonesia

gunand-mbatangoid zainus_sbatangoid lucia_kp

urnomo_sbatangoid Ibnu_sbatangoid

torage of Spent Nuclear Fuel ( IISSNF) is a facility fo

g water cooling system The SNF is generated from

abessy (MPR-GAS) The SNF contains radionucli

s activated corrosion products and transuranium The

uclides which is stored in temporary reactor pond for

heat was decreased the SNF was then transferred to

ng water for its keeping on the rack on floor position o

ing water for cooling and the pool water quality is d

ity from radioactivity contamination the continuous

ess using resin The storage capacity of the IISSNF i

as the ventilation and air conditioning system for mai

lative humidity of 40-60 room negative pressure of

8 of SNF elements and 37 control rod elements fro

e IISSNF is coming from the SNF and the transpor

y aspect for contamination of radionuclides has bee ples of the TC and IISSNF facility radionuclide a

urification unit analysis of I131

in the ambient air a

e assessment and analysis of the contamination level

safety aspect of the TC-ISSNF facility operation is in

cable safety standards

ent nuclear fuel radionuclide contamination spent

pose Reactor of

GA Siwabessy (MPR-GAunloaded from the reactor if

been reached and then bec

74

f Interim

Its Oper-

ionuclides

batangoid

r temporary storage

he operation of the

des ie remaining

SNF generates heat

cooling of 100 days

the IISSNF passing

f pool The IISSNF

emineralized water

ater purification is

1448 elements in-

taining of constant

100 + 25 Pa At the

MPR-GAS The

ation of irradiation

n performed by ra-alysis of the spent

d surface contami-

n the water cooling

ery good condition

uclear fuel

S) the nuclear fuel isits economical life has

ome spent nuclear fuel

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754 International Conference on Water Supply Management System and Social CapitalMakassar Indonesia 16-17 Juli 2012 ISBN 978-602-203-124-6

(SNF) The SNF contains radionuclides (radioactiveelements) ie remaining uranium (U) transuranium(TRU) and radionuclides of fission products as well

as the others activated products The SNF generatesheat and radiation decays of its radionuclides whichis stored in temporary reactor pond for cooling of 100

days or more On that cooling the SNF heat wasdecreased from 47590 ndash 3772 W per element of

SNF12)

The SNF was then transferred to the In-stallation of Interim Storage of Spent Nuclear Fuel(IISSNF) passing by transfer channel (TC) contain-ing water for its keeping on the rack on floor positionof pool The TC is also utilized for transferring of

irradiation targets from MPR-GAS to the Installationof Radioisotope Production (IRP) and transfer-

ring of SNF from MPR-GAS to the IIS-SNF andfrom Installation of Radiometallurgy (IRM) to theIISSNF The IISSNF has the pool construction con-

taining water for cooling radiation protection andradionuclides containment of the SNF for avoiding

its release to the working area The pool water qualityis demineralized water For maintaining of the waterquality from contamination of radionuclides thecontinuous water purification is performed byion-exchange process using resin

Based on design of the MPR-GAS normaloperation there are 8 replacement of SNF per cycles

and 7 cycles per years Therefore The storagecapacity of IISSNF is 1448 elements including con-trol rod the IISSNF can be utilized for storage of

SNF generated from 25 years MPR-GAS operationand one last core unloading The heats generated at

that capacity is 35 kW and heats from lightingsystem and that others is 5 kW Water cooling sys-tem of the IISSNF was designed for that heat re-moving by circulation of 6 m

3hour water pool to the

cooling system for maintaining of constant water

temperature of 35oC The IISSNF has the ventilation

and air conditioning system (VAC OFF GAS) formaintaining of constant air temperature of 20-25

oC

and relative humidity of 40-60 room negative pressure of 100 + 25 Pa radiation exposure of 2-5

mrem hour by air renewal of 5 times per hour 123)Since start MPR-GAS operation on the year

of 1987 until last year of 2011 the quantity of SNFhas been obtained 443 elements According to the policy that all of SNF containing uranium fromUnited State of America (USA) has to be sent back tothe origin country therefore up to 30 July 2009 it

was sent back (has been reexported) of 198 SNFelements to USA

4)

At the present the IISSNF contains 245 elementsconsists of 208 SNF elements and 37 control rod

elements and the TC was utilized for transferring243 elements of SNF from MPR-GAS to theIISSNF 231 irradiation targets from MPR-GAS to

the IPR and 2 elements of SNF from IRM to theIISSNF

4) The heats contamination of radionuclides

and radiation on the IISSNF are coming from the

SNF and the transportation of irradiation targetsAt the present on the normal operation of

MPR-GAS there are only 6 replacement of SNF per

cycles and 4 cycles per year In the condition of 1448SNF elements capacity of IISSNF the IISSNF can

be utilized for 60 years MPR-GAS operation Con-sidering the long period operation of IISSNF inwhich the population in the location will be increasedso the operation of IISSNF must be not on the con-dition of any problems excited The safety aspects of

IISSNS operation must be assessed to assure the long period of its safe operation On the analysis of op-

eration safety aspects of the IISSNF the qualitativeand quantitative assessments of heats contaminationof radionuclides and radiation will be performed

In this paper will be presented the assessment ofoperation safety aspect on contamination of radio-

nuclides in the water cooling system of the IISSNFincluding its working area surroundings and worker The assessment will be performed by analysis ofradionuclide contained in the samples ie watersamples from water cooling syatem of the TC and

IISSNF facility ambient air samples (containing thegases of radionuclides such as I

131 Kr

85 and Xe

133)

the spent ion-exchange resin samples (from water purification plant) and samples from surfase areacontaminated of radionuclides Monitoring on safety

of workers was performed regularly The analysisresults releted to the contamination of radionuclides

in the facility can be utilized for the evaluation of theoperation performance of the IISSNF according tothe existing regulation and for technical action planfor optimization of the IISSNF operation

2THEORY

(1) The TC and IISSNF facility

The SNF generates heat and radiation decays of

its radionuclide which is stored in temporary reactor pond for cooling of 100 days or more The SNF wasthen transferred to the Installation of Interim Storageof Spent Nuclear Fuel (IISSNF) passing by transferchannel (TC) containing water for its keeping on therack on floor position of pool The main objective ofSNF management is that the SNF can be storedsafely economics and conforming to the safetystandard regulation to ensure the public safety andthe environment until the SNF are transferred to re- pository for final storage or to reprocessing facility torecovery of uranium and plutonium (Pu)

567)

There are two systems in the interim storage ofSNF namely wet and dry storage systems The wetstorage system is storage in water pond that it can

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directly received the SNF which just unloaded fromnuclear reactor which still has high heats The fa-cilities for the both of storage systems must have

main functions are as follows8910)

a) To remove the heats from SNF (as cooling of

SNF)

b) As radiation shielding to protect the radiationand to maintain the limit of permitted radiation

level at the working areac) As containment of the radioactive elements for

avoiding its release to the working area

The heats removal is utilized the cooling medium

such as water or air The shielding of radiation can beobtained successfully in SNF storage pool on the

water deep enough or in the close facility withshielding equipment using lead (Pb) material

The IISSNF is the wet storage system using

water cooling system the SNF from the MPR-GASis transferred to the IISSNF passing by transfer

channel (TC) containing water for its keeping on therack on floor position of pool The TC is also utilizedfor transferring of irradiated targets from theMPR-GAS to the Installation of RadioisotopeProduction (IRP) transferring of SNF from the

MPR-GAS to the IISSNF and transferringirradiated fuel targets from the MPR-GAS to In-

stallation of Radiometallurgy (IRM) as well astransferring the irradiated fuel targets from IRM tothe IISSNF The site layout of these installations (the

TC and IISSNF facility) are shown in the Figure 1Containment and confinement of the radio-

nuclides (radioactive elements) is accomplished bySNF storage in water or in close shell with shieldingequipment or in container to avoid the release ofradionuclides if occur accident condition The ac-cident condition can be caused by damage of the SNF

cladding There are three main reason caused thedamage of cladding namely physical damage at thetime of transferring the damage caused by chemicalsand the damage caused by the temperature too high789)

Figure 1 Site layout of the TC and IISSNF facility

Material of cladding utilized in fabrication of MTR (Material Testing Reactor) nuclear fuelstandard are Al-Mg and Al-Mg-Si alloys These

materials have neutron absorption cross section verylow very resistance to radiation chemical andmechanic collision 23) These alloys have the critical

temperature 193

o

C and melting point 650

o

C Ontemperature 100 o C these alloy can be oxydized to

form protective coating (protector layer) The pro-tective coating will disappeared at temperature about150 o C Disappearing of the protective coating causedecreasing of the resistance quality of radioactiveelements (radionuclides) in the SNF 5)

In the wet storage system of SNF is carried outcontrolling of the purity and temperature of the water

(coolant) chemical and physical effects to thecladding of nuclear fuel The temperature at externalcladding must be maintained lower than 100 o C by

storage in water The system generally is designedfor normal operation at temperature lower than 40 o C

and abnormal operation at temperature 67oC so that

the damage of cladding caused by temperature effectcan be eliminated and containment of radioactivematerials in the SNF can be guaranteed

5)

The IISSNF facility containing several racks for

placement of spent nuclear fuel is shown in Figure 2Dimensions of the ISSNF facility is length x width x

depth 14 m x 5 m x (-65 m) and the amount ofcooling water in the IISSNF facility is 455 m

3 The

maximum capacity of the IISSNF is 1448 SNF

elements The installation can accommodate SNF for25 years of operation of RSG-GAS plus one core

unload where there is a 7 cycles per year of the NFreplacement with the amount of fuel that replacedare 8 SNF per cycles But at the present on thenormal operation of MPR-GAS there are only 6replacement of SNF per cycles and 4 cycles per year

so on the condition of 1448 SNF elements capacitythe IISSNF can be utilized for 60 years MPR-GASoperation

Figure 2 The Installation of Interim Storage of Spent NuclearFuel (IISSNF) containing several racks for placement of spent

nuclear fuels

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The IISNF was designed and equipped withventilation of air conditioning (VAC) system which

has a function to 1)

a) Renewal of the air in surrounding of the spent

fuel storage pool with fresh water replacement

5 times per hour b) Maintain the room temperature 20-25 o C

c) Maintain the room relative humidity of air40-60

d) Maintain a negative pressure of room (100 plusmn 25Pa)

In normal conditions the VAC system inoperation and the pool water is maintained at a

constant temperature of 35 deg C through by coolingWater with a temperature of 35 deg C was circulatedwith 6 m3hour flow rate into the cooling system so

that the temperature to 28 deg C and then returned to the pool As the cooling water it is used with the initial

temperature of 17 deg C and final temperature of 23 deg Ccooling water is cooled by cold water from thechiller

(2) Contamination of radionuclide in the TC and

IISSNF facility

In the normal operation contamination of ra-

dionuclides (radioactivity) will occur into the watercooling system of TC and IISSNF according to thelimit of permitted highest content (LPHC) The

analysis of radionuclides in the spent ion-exchangeresin (generated from water purification unit) will

shows the presence of the contamination in the watercooling system before purification process Whereasthe analysis of radionuclide contamination on theambient air by direct measurement on the filterlocated on the VAC OFF GAS system using detector

will also shows contamination in the ambient air ofthe TC and IISSNF facility The contamination ofradionuclides consists of three types of contaminantsare radionuclide of fission products radionuclide ofactivated corrosion products and radionuclide of

actinides (uranium and transuranium) Contamina-tion of uranium and transuranium (TRU) into water

can occur when the fuel cladding is damaged (brokenor cracked) so that leaks and release into the watercooling system

(3) Radionuclide of fission products

Radionuclides (radioactive elements) fromfission products consists of all radionuclide produced from fission reaction (primary fission products) and radionuclide from neutron capture

by radionuclide of fission products (secondaryfission products) The fission reaction of nuclear fuelcontaining U235 according to the equation as follows

11)

92U235

+ 0n1

Z1LA1

+ Z2HA2

+ x 0n1+E hellip (1)

where Z = atomic number A = mass number L andH are light and heavy nuclides of fission productsrespectively The light nuclides have mass number

between 72 to 118 and heavy nuclides have massnumber between 118 to 162 x = quantity of neutron

produced from the fission reaction In this equationZ1 + Z2 = 92 and A1 + A2 + x = 236 The averageheats generated from this fission reaction E = 200MeV The heats produced from fission for 1 g of U

235

equal with heat produced from 1 ton of coal

The example of the primary fission reaction are asfollows

12)

92U235

+ 0n1 38Sr

90 + 54Xe

143 + 3 0n

1 (2)

92U235

+ 0n1

37Rb96

+ 55Cs137

+ 3 0n1

(3)

Radionuclide of Sr 90

and Cs137

are the main fision product elements There are about 200 fission product elements having atomic number between 30to 65 with mass number between 72 to 166 Thereare 16 main fission products with high yield are

given in Table 1

Table 1 The main fission products and its half life (T12) withhigh yield (gt1 ) 12)

Fission product

Half life Yield ()

Tc137

Cs90

Sr 90

Y85

Kr147

Pm144

Ce95

Zr 95 Nb

91Y

89Sr

103 Ru

141

Ce143Pr

140Ba

147 Nd

131I

133Xe

21x10 years

3017 years28 years 64 hours

10 years265 years282 days

6535 days61 days

530 days

398 days

331 days137 days128 days

113 days

81 days53 days

60

6258

152761

6454

48

30

606263

26

2965

In Table 1 90

Sr 90

Y and95

Zr 95 Nb are in equilibrium

of parent and daughter radionuclides The fission product elements contained in the SNF in normaloperation of IISSNF only Cs

137 Sr

90 I

131 Kr

85 and

Xe133 can be released into the water of reactor pondthrough diffusion process and penetrate the cladding

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of SNF If in the water containing the others conta-minant of fission products this shows that haveoccur indication of SNF damage The illustration of

composition of fresh nuclear fuel and spent nuclearfuel utilizing in Nuclear Power Plant are shown inTable 2

Table 2 The composition of fresh nuclear fuel and spent nuclear

fuel utilizing in Nuclear Power Plant (NPP) [12]

Nuclides Fresh nuclear

fuel

( weight)

Spent nuclear

fuel

( weight)

U238

955 93

U 45 1 TRU - 1

Fission Prod-ucts

- 5

In Table 2 shows that the content of remaininguranium in spent nuclear fuel still high with additionof high activity from fission products andtransuranium (TRU) The TRU consist of Pu (gt09 ) and the others TRU (Np Am and Cm) is

lower than 01 Whereas the composition andspecification for fresh nuclear fuel utilizing in theMPR-GAS ie type of nuclear fuel is U3O8Al orU3Si2 (MTR) with enrichment 1975 U

235 (and

8025 U

238

) and cladding material is AlMg alloyIn the burn up of 60 so the SNF contains about78 U

238 8 U

235 and the others are Pu

transuranium (TRU) and fission products

(4) Radionuclide of activated corrosion products

The radionuclides of radioactive elements can be produced from activation reaction with neutron

capture by elements contained in the cladding ofnuclear fuel There are two metal alloys utilized forcladding material of MTR type namely Al-Mg andAl-Mg-Si Activation reactions by main elements

contained in the cladding material are as follows12)

13Al27

+ 0n1

11 Na24

+ 2α4 hellip (4)

13Al27

+ 0n1

12Mg27

+ 1 p1 hellip (5)

12Mg26

+ 0n1

12Mg27

+ γ hellip (6)

12Mg24

+ 0n1

11 Na24

+ 1 p1 (7)

14Si30+ 0n1

14Si31 + γ helliphellip (8)

Radionuclides produced from activationreactions by elements contained in the cladding of

nuclear fuel showed at equation (4) to (8) are Na24Mg

27 and Si

31 In the cladding material also contain

low quantity of some metals such as Mn Co Fe and

Zn These metals can produce the radionuclides fromactivated corrosion products namely Mn

54 Co

60

Fe59 and Zn65 respectively If the cladding occur

corrosion so these radionuclides will contaminateinto water that exist in the reactor pond of

MPR-GAS and it can also contaminate in the watercooling system of the IISSNF through TC Activa-tion process can be also occurred after corrosion process

(5) Uranium and TRU elements

The radionuclides of uranium and TRU

elements are included actinide element groupUranium in SNF consist of U

238 (major element) and

U235 (Table 2) Whereas radionuclides of TRU are

produced from activation of neutron capture byuranium in nuclear fuel and followed by activation

from TRU its self The main TRU elements are Pu Np Am and Cm In general the radionuclide of TRUare long life alpha (α) emitter as are shown in Table3 In actually there is radionuclide of Np

239 but has

very short half life (235 days with β emitter) so that

decay very fast to become Pu239

having long half lifealpha emitter (Table 3)

Table 3 TRU radionuclides half life (T12) and its emission inspent nuclear fuel [1213]

Nuclide Half life Emission

Pu238 877 years α γ

Pu239 241x10years

α γ

Pu240 656x10years

α γ

Pu241 1435 years α β

Pu242 375x10years

α γ

Pu244 24x10 years α γ

Np 21x10 years α

Np 21 days γAm 432 years α γAm 141 years β γAm 737 years α

Cm 1628 days α

Cm 181 years α

(6) Radionuclide in irradiated target

Production of radioisotopes are carried-out byirradiation of target in MPR-GAS The radioiso-topes produced are utilized in several field such as innuclear medicine (eg Mo99

Tc99m

I131

) industry(Ir

191 Co

60 Sr

90) agriculture (S

35 P

32 N

15) and Hy-

drology (Co60 Cs137 H3) etc Several targets prod-uct of radioisotopes and its form of chemical prod-

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ucts are shown at Table 4 Target irradiations arecarried-out in the MPR-GAS then the result ofirradiated targets are sent to Installation of Radioi-

sotope Production (IRP) passing transfer channel(TC)

Nuclear reaction occured in production of radio-

isotope through target irradiation in MPR-GAS arefission reaction or neutron activation The example

of fission reaction is Mo99

production produced fromuranium oxyde target (enriched U

235) its fission

reaction is follows 14)

92U235 + 0n

142Mo99 + 50Sn136 +2 0n

1 +200 MeV

helliphelliphelliphelliphelliphellip(9)

Whereas Tc99m

is produced from decaying of Mo99

Mo99 99mTc+-1β0 helliphelliphelliphelliphellip (10)

The example of radioisotope production by neutron

activation is I131

radioisotope produced from tellu-rium oxyde (TeO2) target its activation reactioncontinued by β-decaying as follows

52Te130 + 0n1

52Te131 + γ (11)

52Te131

53I131

+ -1β0 (12)

The irradiated targets in the container is thentransferred from the MPR-GAS to RPI through TC

The condition of container is closed tightly to avoidthe contamination of radionuclide (from irradiated

target) into water cooling system in TC When in thewater cooling system contains the contaminant ofradionuclide it indicates the presence ofcontamination caused by the damage of container(broken or cracked) so that the radionuclide release

into water cooling system of TC

Table 4 Products of radioisotopes from the targets irradiated

in MPR-GAS 14)

TargetsProduct of

radioisotopes

Form ofchemical products

U (

9315 )

U235

(9315 )

U235

( 9315 )

Ir 191

( wa-ferdisc)

Ir 191

( wa-ferdisc)

Zn metalTl metal (Tl

203)

MoO3TeO2

Xenon (Xe124

)

MoI131

Xe133

Ir 192

Ir 192

bulk

Ga67

Tl201

Mo99

I131

I

125

P32

S35

Na2MoO4

NaI

Xenon gasIrIr

GaCl3

TlCl

Na2MoO4

NaI

NaIH3PO4

H2SO4

SulfurKCl

Cr metal (Cr 50

)Fe2O3 (Fe

58)

SrCO3 (Sr 84

)

HgOSn metal

(Sn112)

Yb2O3 (Yb168

)CaCO3 (Ca

44)

Fe2O3 (Fe54

)

Sn metal(Sn

118)

Cr

Fe59

Sr 85

Hg203

Sn113

Yb169

Ca45

Mn54

Sn119m

Na2CrO4 ampCrCl3

FeCl3

Sr(NO3)2

Hg(NO3)2

SnCl2 amp SnCl4

YbCl3

CaCl2MnCl2

SnCl2

Assessment on the operation safety aspect of theISSNF facility related to the contamination of radio-

nuclides necessary to be performed by analysis ofradionuclides containing in water cooling system of

the TC and ISSNF Facility spent ion-exchange resin(from water purification unit) the ambient airsamples and analysis of surface contamination Thisassessment is very important to evaluation andoptimization of the TC and IISSNF facility op-

eration

3METHODS

(1) Materials and equipment

The materials utilized consists of a) standard

radioisotope materials (standard sources) as followsCd

109 Fe

59 Co

60 and Am

241 b) the sample material

by sampling in the TC and ISSNF facility namely pool water spent ion-exchange resin air filter and

filter paper of wipe test c) Whatman filter paperliquid nitrogen and chemicals such as nitric acid and

hydrochloric acid The equipments utilized are as follows

a) Gamma Spectrometer with High pure Germa-nium (Hp-Ge) Detector

b) Detector of NaI (Tl) for detection of iodine (I131)

c) Survey meter FAG-40 FZ

d) Sampling equipment for cooling watere) Intelligence of Continuous Air Monitor

(I-CAM) for air ambient activity monitorf) Detector for temperature (Thermometer)

g) Detector for water conductivityh) Centrifuge column adsorption pH meter digital

balance and laboratory glassware equipments

(2) Work procedures

Assessment on operation safety aspect of the TCand ISSNF Facility concerning the contamination of

radionuclides were carried-out by radioactivity

analysis of water samples from TC and pool ofISSNF analysis of spent ion-exchange resin (from

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purification unit) analysis of iodine (I131) and theothers gas radionuclides (Kr

85 Xe

133) contained in

ambient air All of sampling was carried out regularly

once a week The steps of data collection analysisand assessment are as followsa) Analysis of radionuclide contained in the water

samples and spent ion-exchange resin samples Taking of water samples at the TC and ISSNF

pool and samples of the spent ion-exchange re-sin from purification unit using a sampling tool The analysis of radionuclide in these samplesusing Gamma Spectrometer with Hp-Ge detec-tor

b) Analysis of the contamination of radionuclides inambient air

The contamination of gas radionuclides (I131

Kr

85 and Xe

135) in air was analyzed by direct

measurements of the activity at the site of VAC

OFF GAS Sampling of air in pool of the IISSNFand measurements (counting) of the activity of

ambient air using I-CAM the measurement ofcontamination at inlet of the air filter on the AirChannel System (ACS) using detector of NAI(Tl) and measurement of contamination at theoutlet air stack (OAS) sampling of OAS using a

filter and its activity counting using alpha-betacounter

c) Analysis of the surface contamination activitiesin the TC and IISSNF facility The analysis of surface contamination activities

consist of measurement of surface activities atseveral locations (room or area) in the TC and

IISSNF facility The measurement of surfacecontamination are carried-out using filter paperof wipe test and its acivity counting usingalpha-beta counter

d) Monitoring for safety of working area and

worker on contamination of radionuclides per-formed by measurement of radiation exposurein working area and radiation dose received byworkers in the TC and IISSNF facility

4 RESULTS AND DISCUSSION

The assessment of operation safety aspect oncontamination of radionuclides in the water coolingsystem of IISSNF including its working areasurroundings is based on analysis results of radio-nuclides in the water cooling system spention-exchange resin ambient air and surface conta-mination (in arearoom) of the TC and IISSNFfacility

(1) Analysis of radionuclides contained in the

water and spent ion-exchange resin samples

The analysis results of radionuclides activity in

BqL (becquerellitre) contained in water samplesfrom pool of IISSNF TC and OPU (outlet of puri-fication unit) using Gamma Spectrometer with

Hp-Ge detector (sampling on February to April2012) are shown in Table 5

Table 5 Maximum activity of radionuclides in watersamples from the TC and IISSNF facility

(sampling on February to April 2012)

Sampling

times and

watersamples

Maximum activity of radionuclides

(BqL)

Cs137

Sb12

4

Ru103

Nd147

Y91

Feb 2012

Pool 148 none 8142 none noneTC none none none 1188

4

none

OPU none none none none none

March

2012Pool none none none none none

TC none 444 459 none noneOPU none none none none none

April

2012Pool 37 903 3101 none none

TC 148 none none none 2398OPU 326 533 none none none

none = no detected or lower than background ac-tivity

In Table 5 shows the presence of radionuclidecontamination generated from the release of mainfission product radionuclide Cs

137 Sb

124 Ru

103

Nd147 and Y91 These radionuclides are included the

main fission product elements having yield more

than 1 (see Table 3) In this water of the TC andISSNF facility are not detected the presence of thefission product radionuclide such as I

131 Kr

85 and

Xe133 these radionuclide are main fission products

in gas phases so they can released to ambient airWhereas contamination of radionuclides generated

from the activated corrosion product of elementssuch as Fe

59 Co

60 Mn

54 are also not detected

Radionuclide of Cs137 is fission product element

having long half life ( T12 = 3017 years) and highabundance its decaying to produce radionuclide of

Ba137

Almost 85 is β decay to produce Ba137m

together with photon emission of 662 keVRadionuclide of Ba

137 also emit X-ray and convertion

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electron Solubility of Cs137 in water is high so Cs137 easily to be transferred into the cycle of watercooling system In high temperature Cs137 is volatile

radionuclide and it can caused inhalation danger toradiation workers The Cs

137 is strong gamma emitter

so that very easy to be analized using Gamma

SpectrometryThe radionuclide of Cs137 and Sr 90 are the most

important of fission products having high activitiesand high yields and also they have long half life(3017 years and 288 years respectively) so they aremain contributor contained in radioactive wastegenerated from SNF In Table 5 the radionuclide of

Sr 90

is not shown because this radionuclide is pure beta-emitter so that it can not be detected using

Gamma SpectrometerRadionuclide of Sr

90 is fission product element

with pure β-emitter (Emax= 546 keV) having high

abundance and very potency to give high contribu-tion in contamination inventory Decaying of Sr 90 to

produce the equilibrium with its daughter of Y90

(T12 = 641 hours pure β-emitter with Emax= 227 MeV )Based on the decaying Sr 90Y90 with high β energyso that dosimetry monitoring and doses control can be performed by β-detector of Geiger Muller

Counter The analysis of Sr 90

is needed the radio-chemical treatment and its analysis using

β-spectrometer but Sr 90

also can be determined byscaling factor method using Cs

137 as radionuclide

standard

The comparing between the maximum activity inBqL (becquerellitre) of radionuclide (Table 5) with

the Limit of Permitted Highest Content (LPHC)[15]

isshown in Table 6 The maximum activity of Sr

90 was

calculated based on scaling factor of Cs137

Table 6 Maximum activity of radionuclide in water

samples of the TC-ISSNF facility comparingwith LPHC in the environment water 15)


Radio nuc-lide

(half life)

Max concentration inwater (BqL)

LPHC(BqL

)TC Pool OPU

Cs

(3017y)

148 370 3256 7x102

Sb (603d) 444 903 533 7x102

Ru (3935d

)

459 3101 none 4x102

Nd (113d) 1188

4

none none 1x104

Y (61 d) 2398 none none 1x103

Sr (288y) 141 353 3108 7x102

none = no detected or lower than background

activity Calculation based on scaling factor of Cs

137

In Table 6 during the period from February toApril 2012 (12 times the measurements) the activity

of Cs137 and Sr 90 in water samples (TC pool ofISSNF and out let of purification unit) were lowerthan LPHC Whereas the activities of Y91 Ru103 Nd

147 and Sb

124 during that period were obtained their

activities only one time (from the measurements of

12 times) higher than LPHC respectively and theothers measurements were obtained none or lowerthan LPHC

In the high temperature Cs137

and Sr 90

are volatileisotopes and relatively easy to diffuse and it can pe-netrate the cladding of nuclear fuel so that both of

the isotopes can release into the primary coolingwater of reactor as contaminant and moving up to thewater cooling system of TC and IISSNF Theirdiffusion can also occur at the time SNF has been inthe IISSNF In Table 5 during the period of Febru-ary to April 2012 from 12 times measurements

(every once a week) showed that only the presenceof Cs

137 found in the pool of IISSNF and only one

time during the second week with the activity of 148BqL is much lower than LPHC in the environmentwater namely its value LPHC = 7x102 BqL 15) then

the next 4 weeks indicated no presence of Cs137

Whereas in the water of TC there are no Cs137

The others main fission products are Ru103 Nd147

Sb124

and Y91

They have half life very short Theiractivities some time higher than LPHC and some

time lower than LPHC even are none ( no detected orlower than background activity) The fission product

of Ru103

(T12 = 398 days) having its behavior asCs

137 and Sr

90 Ru

103 is also volatile at high tem-

perature (easily changed into the gas phase) and eas-

ily defuse to exit from cladding of nuclear fuel and become contaminants in the primary cooling water of

MPR-GAS In Table 5 during period from Febru-

ary to April it was found the presence of Ru103 twotimes in the pool of IISSNF with the activity of 8142BqL and 3101 BqL (higher than LPHC = 4x10

2

BqL) and only one time detectacle in water of TC

with activity 459 BqL (higher than LPHC) but because Ru

103 is short life so this radionuclide decays

rapidly and its activities soon decreaseWhereas Nd

147 (T12 = 113 days) and Y

91 (T12 =

61 days) are only once presence in water of TC with

activity of 11884 BqL and 2398 BqL respectivelyThe both of activities of radionuclide in water of TC

higher than LPHC but in the pool of the IISSNF on

the same day the both of radionuclide have not beenfound (not detected) because their half life are very

7172019 06



short and have been diluted and also may be that the both radionuclide are generated from irradiatedtargets transferred to IRP or IRM

Based on Table 5 indicate that there arecontamination of Cs

137 Ru

103 Y

91 Nd

147 and Sb

124

in water cooling system of the TC and IISNF facility

but with existing the purification unit using the ion-exchange resin so that often their activities does not

appear This phenomena is caused by purificationunit is not operated continuously but periodically forsavings and optimization of its use

The analysis results of radionuclide contained inwaste of spent ion exchange resin utilizing in puri-

fication unit of primary cooling water in MPR-GASare shown in Table 7

Table 7 Analysis results of radionuclide contained in waste ofspent ion-exchange resin utilized

in purification unit of primary cooling

water in the MPR-GAS

Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10

In Table 7 shows that the waste of spention-exchange resin in all of tanks containing the

same radionuclide namely Cs137

Ce144

Zn65

Co60

and Mn

54 In this case there was only the fission

product of Cs137

and Ce144

but Sr 90

was not detected by Gamma Spectrometer because it is pure betaemitter Whereas the others fission product radio-nuclides such as Nd

147 Y

91 Sb

144 and Ru

103 were not

detected because they are have short life while theresin wastes have been stored long enough they arenot shown as at Table 5 mentioned above The presence of radionuclide from the activated corrosion products namely Zn

65 Co

60 and Mn

54 shows that the

corrosion process occur at the time of reactor opera-

tion and it only contaminate in the primary coolingwater then they are accumulated in the ion exchange

resin of the purification unit in the MPR-GASThe contamination of fission products in water

cooling system of the TC and ISSNF Facility can be

removed by the purification process The

contamination level of radionuclides are stillrelatively low the operation of the purification unit

can be carried-out regularly and it is not continuousfor saving or optimization of its use

(2) Analysis of the contamination of radio- nuc-

lides in ambient air

The analysis of contamination of radionuclidesin ambient air was carried out by direct measurementat the location of the VAC OFF GAS Sampling ofair in pool of the IISSNF and measurements (count-ing) of the activity of ambient air using I-CAM themeasurement of contamination at inlet of the air filteron the Air Channel System (ACS) by detector of NAI(Tl) and measurement of contamination at the outletair stack (OAS) sampling in OAS using a filter andits activity counting using alpha-beta counterThe analysis results of air contamination (in Bqm3)

are shown in Table 8

Table 8 The analysis results of air contamination in the

TC-ISSNF facility from February to April 2012

Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April

2012 Pool 00110 07800ACS none 58613OAS none 00058

none = no detected or lower than back-

ground activity

In Table 8 shows that in the period of Februaryto April 2012 the level of contamination can be seen

more real the estimated the I131 on inlet of air filter onACS that gives activity of gross βγ (betagamma) between 4689 to 5861 Bqcm3 which indicates the presence of accumulative contamination of I

131 (fis-

sion product with T12 = 81 days yield = 29 )from ambient air Whereas the others of fission product gases such as Kr

85(γ) and Xe

133(γ) are not

adsorbed by the air filter of ACSThe measurement of the air contamination level

by taking samples (sampling) in pool of IISSNF andin outlet air stack (OAS) were relatively low namelythe value of gross alpha (α) between 00106 to 00110

Bqcm3 and gross βγ between 0723 to 0780 Bq cm

3 whereas at the outlet air stack was obtained the

7172019 06



gross of alpha with value between none to 00052 Bqcm

3 and gross of betagamma between 00058 to

00898 Bq cm3The gross of βγ activity is estimated

from I131

(β γ) It showed the presence of contami-nation of I

131 Kr

85 and Xe

133 in ambient air in the

TC and IISSNF facility although it is still very low

Based on The LPHC in air are

[7]

Alpha (α) =074 Bqcm3 and Betagamma (βγ) = 74 Bqcm

3 so

the air contamination in the TC and IISSNF facilityis lower than the LPHC Then based on Decree ofChairman of BAPETEN No 02KA-BAPETENV1999 concerning The Standard of RadioactivityLevel in Environment the LPHC in air for I131 is

1x10-2

BqL or 10 Bqm3 15)

therefore the aircontamination from I

131 Kr

85 and Xe

133 in ambient

air of the TC and IISSNF facility is also lower thanthe LPHC so that the safety aspect of TC andIISSNF operation in good condition and conform to

the standard operationThe level of gases contamination of I131 Kr 85

and Xe133

in ambient air is still in very low level sothe ambient air will be flowed into the filter unit ofACS automatically when there are indications ofcontamination of these radionuclide which ismarked by the increasing of the air activity on the air

activity monitor in the ACS

(3) Analysis of the surface contamination in the

TC and IISSNF facility

The analysis of surface contamination activities

in the TC and IISSNF facility consist ofmeasurement of surface activities at several locations

(room or area) are as follows lobby the maincontrol room (MCR) dress exchange room (DER) pool area (Pool-I = Right side of Pool Area Pool-II= Left side of Pool Area Pool-III = Front side of PoolArea) TC Area (TC-I = TC of IISSNF Area TC-II

= TC of the MPR-GAS Area TC-III= TC of theIRPIRM Area) and purification unit room (PUR)The measurement of surface contamination werecarried-out using filter paper of wipe test and itscounting of the activity using alpha-beta counter The

analysis results of surface contaminations (in becquerelcm

2 or Bqcm

2) are shown in Table 9

Table 9 The analysis results of surfase contamination inthe TC and IISSNF facility from March to May 2012

Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ

March 2012 Lobby none 00074MCR none 00087

DER none 00105Pool-I 00006 none

Pool-I none none

IPool-I

II

none none

TC-I 00009 00210

TC-II none noneTC-III none nonePUR 00006 00734

April 2012 Lobby none 00175MCR none 00150

DER none nonePool-I none 00197Pool-I

I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228

May 2012 Lobby none 00370MCR none 00469

DER none nonePool-I none 00512

Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414

none = no detected or lower than back-ground activity

In Table 9 shows that in the period from Marchto May 2012 the measurement of the surface con-tamination level in the TC and IISSNF facility arerelatively low namely almost at all room or area forthe gross alpha and gross betagamma namely none(no detected) or relatively same with the background

activity (lt 1 Bqcm

2

) Beside that the surface con-tamination level in all arearoom of the TC andIISSNF facility still much lower than the LPHC (foralpha = 037 Bqcm

2 and for betagamma = 37

Bqcm2)[7]

This shows that the TC and IISSNF

facility maintained from surface contamination

(4) Monitoring for safety of working area and

worker againt contamination of radionuclides

Monitoring for safety of working area was

performed by measurement of radiation exposure inworking area of the facilityThe measurement results

of the average of radiation exposure on working areain this facility are as follows in zone I is not detected

7172019 06



whereas for zone II zone III and zone IV are76x10

-3 155x10

-3 and 82x10

-3 983221remhour respec-

tively These measurements much lower than the

Limit of Permited Higher of Radiation Exposure(LPHRE) The LPHRE for each zone of workingareas are as follows 16) Zone I le 075 983221remhour

Zone II le 25 983221remhour Zone III ge 25 983221rem hourand le10000 983221remhour Zone IV gt10000 983221rem

hourThe measurement results of the radiation expo-

sure for working area mentioned above is conform tothe radiation doses received by workers in this facil-ity The average of external radiation dose re-

ceived by workers is 052 to 059 mSvyear this ismuch lower than LPHD (Limit of Permitted Higher

Dose) namely 5 mSvyear whereas the average ofinternal radiation dose received by workers showsthat no internal doses received by wokers in this

facility17)

Based on the monitoring results for worker

safety on contamination of radionuclides during theTC and IISNF facility operation is in very goodcondition and safe in accordance with applicablesafety standards

(5) Technical action plan for optimization of the

IISSNF operation

Based on analysis and assessment releted to thecontamination of radionuclides mentioned aboveshows that the safety aspect of the TC and IISSNF

facility operation is in a good condition and conformto the standard operation and the existing regulation

Further the technical action plan for optimization ofthe IISSNF operation can be carried-out as follows a) The contamination of fission products in water

cooling system of the TC and ISSNF facility can be removed by the purification process In fact

that the contamination level of radionuclide fromfission products is still relatively low and eventhe contamination of radionuclides from the ac-tivated corrosion products were none (no de-tected or lower than background activity) so the

purification unit can be operated regularly and itis not continuous for savings or optimization of

its use b) The contamination level of radionuclide gases

(I131

Kr 85

and Xe133

) in ambient air is still in verylow level (much lower than the LPHC) so theambient air will be flowed into the filter unit in

the Air Channel System (ACS) automaticallywhen there are indications of contamination ofthese radionuclides The indication of contami-nation is marked by the increasing of the air ac-

tivity shown by the air activity monitor in theACSc) Monitoring of radionuclide contamination in

water cooling system and surface contaminationin the working area of the TC and IISSNF fa-cility can be carried-out also regularly based on

the contamination level shown by the activitymonitor for ambient air in the ACS

The technical action plan mentioned above is sub-

mitted for optimization of the TC and IISSNF facilityoperation and also to maintain its operation safety in

accordance with applicable safety standards

5CONCLUSION

The assessment based on the analysis results of

contamination level of radionuclides in the TC andIISSNF facility during the period from February toMay 2012 can be concluded that generally indicatesthe presence of contamination of the main fission product radionuclide (Cs

137 Nd

147 Sb

124 Y

91) in

water cooling system of the TC and IISSNF facilityThe contamination levels generally were still lowerthan the limit of permitted highest content (LPHC)although some times the contamination level for thefission products higher than LPHC Besides that inthe water cooling system of the TC and IISSNFfacility not indicates the presence of contamination

from the activated corrosion products such as Zn65

Co

60 and Mn

54 (not like that contained in the spent

ion-exchange resin at the purification unit of theMPR-GAS) Considering the contamination levelof radionuclide from fission products and activated

corosion products were still relatively very low andonly some times indicates the presence of contami-nation so the purification unit can be operated reg-ularly and it is not continuously for savings or opti-mization of its use Whereas for the contamination

level of gas radionuclides (I131

Kr 85

and Xe133

) inambient air is also still in very low level (much lower

than LPHC) so for optimization of operation theambient air will be flowed into the filter unit in theACS automatically when there are indications of

contamination The indication of the contamination

is marked by the increasing of the air activity shown by the air activity monitor in the ACS The surfacecontamination level in all arearoom of the TC andIISSNF facility still much lower than the LPHC thiscase shows that the TC and IISSNF facilitymaintained from surface contamination Based on the

assessment and analysis of the contamination levelcan be concluded also that the operation safety as-

pect of the TC and IISSNF facility is in very goodcondition and safe in accordance with applicablesafety standards

REFERENCES1) BATAN ndash IAEA ENGINEERING CONTRACT ldquoTransfer

Channel and ISSF for BATAN Preliminary Design

7172019 06



Packagerdquo November 1992

2) Zainus Salimin ldquoHeat Transfer Analysis on the Storage ofSpent Fuel of Indonesia Multi-Purpose Reactor-30 MW Proceeding of 6 th International Topical Meeting on

Nuclear Reactor Thermal Hydraulics Operations andSafety Nara Japan October 4-8 2004

3) Zainus Salimin ldquoHeats Transfer of Spent Nuclear Fuel at

Interim Storage of Wet type in PPTA Serpongrdquo

Proceedings of Seminar III on Technology and Safety NPPand Nuclear Facility PPTA SERPONG 5 ndash 6 September1995

4) Dyah S Rahayu Report of Repatriation for Spent NuclearFuel arising from MPR-GAS BATAN Serpong 2010

5) Zdenek Dlouhy Handling of Irradiated Fuel from Research

Reactorrdquo Czechoslovakia Nuclear Research InstituteCzechoslovakia 1976

6) IAEA ldquoGuidebook on Spent Fuel Storagerdquo IAEA

Technical Report Series No 240 Vienna 19947) IAEA ldquoFuel Handling Storage Systems in Nuclear Power

Plantrdquo IAEA Safety Series No 50-SGD 10 Vienna 1984

8) Zainus Salimin Dyah S Rahayu Performance of The

Interim Storage for Spent Nuclear Fuel related its Storage

Technology The 16 th National Seminar on Technologyand Safety of NPP and The others Facility Surabaya 28July 2010

9) MPeehs W Jung and J Banck ldquoSpent Fuel Storage

Performance in Relation to Storage Technologiesrsquorsquo Proceeding of The 1987 International Waste ManagementConference Hongkong November 29 ndash December 5 1987

10) Donald Q Kern ldquoProcess Heat Transferrdquo 4th edition GrawHill Book Co Singapure 1965

11) Manson Benedict et al ldquoNuclear Chemical Engineeringrdquorsquo

Second edition Mc Graw Hill Books Company New York

198112) Gunandjar Analysis of Radionuclide in Decommissioning

of Research Reactor Training Course on Decommissioningof Research Reactor September 2011

13) IAEA ldquoRadiological Characterization of Shut Down Nuclear Reactors for Decommissioning Purposes IAEA

Technical Report Series No 389 IAEA Vienna 1998

14) BATAN Radiochemical amp Radiopharmaceuticals Leaflet

of Radioisotope Production Centre National NuclearEnergy Agency of Indonesia 2001

15) BAPETEN Decree of Chairman of BAPETEN

No02Ka-BAPETENV-99 5 May 1999 concerning theLimit of Permitted Highest Content for environment 1999

16) Technicatome Options De Surete Principes De Base

BATAN-Technicatome WSPG NTA 0001 1983

17) BKL-PTLR BATAN Report of the Radiation Safety in Nuclear Energy Research Center of Serpong 2011

7172019 06



(SNF) The SNF contains radionuclides (radioactiveelements) ie remaining uranium (U) transuranium(TRU) and radionuclides of fission products as well

as the others activated products The SNF generatesheat and radiation decays of its radionuclides whichis stored in temporary reactor pond for cooling of 100

days or more On that cooling the SNF heat wasdecreased from 47590 ndash 3772 W per element of

SNF12)

The SNF was then transferred to the In-stallation of Interim Storage of Spent Nuclear Fuel(IISSNF) passing by transfer channel (TC) contain-ing water for its keeping on the rack on floor positionof pool The TC is also utilized for transferring of

irradiation targets from MPR-GAS to the Installationof Radioisotope Production (IRP) and transfer-

ring of SNF from MPR-GAS to the IIS-SNF andfrom Installation of Radiometallurgy (IRM) to theIISSNF The IISSNF has the pool construction con-

taining water for cooling radiation protection andradionuclides containment of the SNF for avoiding

its release to the working area The pool water qualityis demineralized water For maintaining of the waterquality from contamination of radionuclides thecontinuous water purification is performed byion-exchange process using resin

Based on design of the MPR-GAS normaloperation there are 8 replacement of SNF per cycles

and 7 cycles per years Therefore The storagecapacity of IISSNF is 1448 elements including con-trol rod the IISSNF can be utilized for storage of

SNF generated from 25 years MPR-GAS operationand one last core unloading The heats generated at

that capacity is 35 kW and heats from lightingsystem and that others is 5 kW Water cooling sys-tem of the IISSNF was designed for that heat re-moving by circulation of 6 m

3hour water pool to the

cooling system for maintaining of constant water

temperature of 35oC The IISSNF has the ventilation

and air conditioning system (VAC OFF GAS) formaintaining of constant air temperature of 20-25

oC

and relative humidity of 40-60 room negative pressure of 100 + 25 Pa radiation exposure of 2-5

mrem hour by air renewal of 5 times per hour 123)Since start MPR-GAS operation on the year

of 1987 until last year of 2011 the quantity of SNFhas been obtained 443 elements According to the policy that all of SNF containing uranium fromUnited State of America (USA) has to be sent back tothe origin country therefore up to 30 July 2009 it

was sent back (has been reexported) of 198 SNFelements to USA

4)

At the present the IISSNF contains 245 elementsconsists of 208 SNF elements and 37 control rod

elements and the TC was utilized for transferring243 elements of SNF from MPR-GAS to theIISSNF 231 irradiation targets from MPR-GAS to

the IPR and 2 elements of SNF from IRM to theIISSNF

4) The heats contamination of radionuclides

and radiation on the IISSNF are coming from the

SNF and the transportation of irradiation targetsAt the present on the normal operation of

MPR-GAS there are only 6 replacement of SNF per

cycles and 4 cycles per year In the condition of 1448SNF elements capacity of IISSNF the IISSNF can

be utilized for 60 years MPR-GAS operation Con-sidering the long period operation of IISSNF inwhich the population in the location will be increasedso the operation of IISSNF must be not on the con-dition of any problems excited The safety aspects of

IISSNS operation must be assessed to assure the long period of its safe operation On the analysis of op-

eration safety aspects of the IISSNF the qualitativeand quantitative assessments of heats contaminationof radionuclides and radiation will be performed

In this paper will be presented the assessment ofoperation safety aspect on contamination of radio-

nuclides in the water cooling system of the IISSNFincluding its working area surroundings and worker The assessment will be performed by analysis ofradionuclide contained in the samples ie watersamples from water cooling syatem of the TC and

IISSNF facility ambient air samples (containing thegases of radionuclides such as I

131 Kr

85 and Xe

133)

the spent ion-exchange resin samples (from water purification plant) and samples from surfase areacontaminated of radionuclides Monitoring on safety

of workers was performed regularly The analysisresults releted to the contamination of radionuclides

in the facility can be utilized for the evaluation of theoperation performance of the IISSNF according tothe existing regulation and for technical action planfor optimization of the IISSNF operation

2THEORY

(1) The TC and IISSNF facility

The SNF generates heat and radiation decays of

its radionuclide which is stored in temporary reactor pond for cooling of 100 days or more The SNF wasthen transferred to the Installation of Interim Storageof Spent Nuclear Fuel (IISSNF) passing by transferchannel (TC) containing water for its keeping on therack on floor position of pool The main objective ofSNF management is that the SNF can be storedsafely economics and conforming to the safetystandard regulation to ensure the public safety andthe environment until the SNF are transferred to re- pository for final storage or to reprocessing facility torecovery of uranium and plutonium (Pu)

567)

There are two systems in the interim storage ofSNF namely wet and dry storage systems The wetstorage system is storage in water pond that it can

7172019 06






SNF)


















temperature 193

o


o








5)




3 The






nuclear fuels

7172019 06















IISSNF facility











11)

92U235

+ 0n1

Z1LA1

+ Z2HA2





235



12)

92U235

+ 0n1 38Sr

90 + 54Xe

143 + 3 0n

1 (2)

92U235

+ 0n1

37Rb96

+ 55Cs137

+ 3 0n1

(3)


and Cs137


given in Table 1


Fission product

Half life Yield ()

Tc137

Cs90

Sr 90

Y85

Kr147

Pm144

Ce95

Zr 95 Nb

91Y

89Sr

103 Ru

141

Ce143Pr

140Ba

147 Nd

131I

133Xe

21x10 years



6535 days61 days

530 days

398 days


113 days

81 days53 days

60

6258

152761

6454

48

30

606263

26

2965

In Table 1 90

Sr 90

Y and95



137 Sr

90 I

131 Kr

85 and


7172019 06








fuel

( weight)

Spent nuclear

fuel

( weight)

U238

955 93

U 45 1 TRU - 1

Fission Prod-ucts

- 5



235 (and

8025 U

238


238 8 U







13Al27

+ 0n1

11 Na24

+ 2α4 hellip (4)

13Al27

+ 0n1

12Mg27

+ 1 p1 hellip (5)

12Mg26

+ 0n1

12Mg27

+ γ hellip (6)

12Mg24

+ 0n1

11 Na24

+ 1 p1 (7)

14Si30+ 0n1




27 and Si




54 Co

60











239 but has







Pu239 241x10years

α γ

Pu240 656x10years

α γ


Pu242 375x10years

α γ


Np 21x10 years α


Cm 1628 days α

Cm 181 years α



Tc99m

I131

) industry(Ir

191 Co

60 Sr

90) agriculture (S

35 P

32 N

15) and Hy-


7172019 06









235) its fission


92U235 + 0n

142Mo99 + 50Sn136 +2 0n

1 +200 MeV


Whereas Tc99m




activation is I131


52Te130 + 0n1

52Te131 + γ (11)

52Te131

53I131

+ -1β0 (12)






in MPR-GAS 14)

TargetsProduct of

radioisotopes


U (

9315 )

U235

(9315 )

U235

( 9315 )

Ir 191

( wa-ferdisc)

Ir 191

( wa-ferdisc)


203)

MoO3TeO2

Xenon (Xe124

)

MoI131

Xe133

Ir 192

Ir 192

bulk

Ga67

Tl201

Mo99

I131

I

125

P32

S35

Na2MoO4

NaI

Xenon gasIrIr

GaCl3

TlCl

Na2MoO4

NaI

NaIH3PO4

H2SO4

SulfurKCl

Cr metal (Cr 50

)Fe2O3 (Fe

58)

SrCO3 (Sr 84

)

HgOSn metal

(Sn112)

Yb2O3 (Yb168

)CaCO3 (Ca

44)

Fe2O3 (Fe54

)

Sn metal(Sn

118)

Cr

Fe59

Sr 85

Hg203

Sn113

Yb169

Ca45

Mn54

Sn119m

Na2CrO4 ampCrCl3

FeCl3

Sr(NO3)2

Hg(NO3)2

SnCl2 amp SnCl4

YbCl3

CaCl2MnCl2

SnCl2




eration

3METHODS




109 Fe

59 Co

60 and Am












(2) Work procedures




7172019 06




85 Xe

133) contained in







Kr

85 and Xe




















Sampling

times and

watersamples


(BqL)

Cs137

Sb12

4

Ru103

Nd147

Y91

Feb 2012


4

none


March



April





137 Sb

124 Ru

103




131 Kr

85 and




59 Co

60 Mn




Ba137




7172019 06









Sr 90












137 as radionuclide

standard




90 was





Radio nuc-lide

(half life)


LPHC(BqL

)TC Pool OPU

Cs

(3017y)

148 370 3256 7x102

Sb (603d) 444 903 533 7x102

Ru (3935d

)

459 3101 none 4x102

Nd (113d) 1188

4

none none 1x104

Y (61 d) 2398 none none 1x103

Sr (288y) 141 353 3108 7x102



137



147 and Sb





and Sr 90









Sb124

and Y91



of Ru103


137 and Sr

90 Ru






2





147 (T12 = 113 days) and Y

91 (T12 =





7172019 06





137 Ru

103 Y

91 Nd

147 and Sb

124









Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10



Ce144

Zn65

Co60

and Mn


product of Cs137

and Ce144

but Sr 90


147 Y

91 Sb

144 and Ru

103 were not


65 Co

60 and Mn

54 shows that the














Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April



ground activity



131 (fis-


85(γ) and Xe

133(γ) are not





7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06






SNF)


















temperature 193

o


o








5)




3 The






nuclear fuels

7172019 06















IISSNF facility











11)

92U235

+ 0n1

Z1LA1

+ Z2HA2





235



12)

92U235

+ 0n1 38Sr

90 + 54Xe

143 + 3 0n

1 (2)

92U235

+ 0n1

37Rb96

+ 55Cs137

+ 3 0n1

(3)


and Cs137


given in Table 1


Fission product

Half life Yield ()

Tc137

Cs90

Sr 90

Y85

Kr147

Pm144

Ce95

Zr 95 Nb

91Y

89Sr

103 Ru

141

Ce143Pr

140Ba

147 Nd

131I

133Xe

21x10 years



6535 days61 days

530 days

398 days


113 days

81 days53 days

60

6258

152761

6454

48

30

606263

26

2965

In Table 1 90

Sr 90

Y and95



137 Sr

90 I

131 Kr

85 and


7172019 06








fuel

( weight)

Spent nuclear

fuel

( weight)

U238

955 93

U 45 1 TRU - 1

Fission Prod-ucts

- 5



235 (and

8025 U

238


238 8 U







13Al27

+ 0n1

11 Na24

+ 2α4 hellip (4)

13Al27

+ 0n1

12Mg27

+ 1 p1 hellip (5)

12Mg26

+ 0n1

12Mg27

+ γ hellip (6)

12Mg24

+ 0n1

11 Na24

+ 1 p1 (7)

14Si30+ 0n1




27 and Si




54 Co

60











239 but has







Pu239 241x10years

α γ

Pu240 656x10years

α γ


Pu242 375x10years

α γ


Np 21x10 years α


Cm 1628 days α

Cm 181 years α



Tc99m

I131

) industry(Ir

191 Co

60 Sr

90) agriculture (S

35 P

32 N

15) and Hy-


7172019 06









235) its fission


92U235 + 0n

142Mo99 + 50Sn136 +2 0n

1 +200 MeV


Whereas Tc99m




activation is I131


52Te130 + 0n1

52Te131 + γ (11)

52Te131

53I131

+ -1β0 (12)






in MPR-GAS 14)

TargetsProduct of

radioisotopes


U (

9315 )

U235

(9315 )

U235

( 9315 )

Ir 191

( wa-ferdisc)

Ir 191

( wa-ferdisc)


203)

MoO3TeO2

Xenon (Xe124

)

MoI131

Xe133

Ir 192

Ir 192

bulk

Ga67

Tl201

Mo99

I131

I

125

P32

S35

Na2MoO4

NaI

Xenon gasIrIr

GaCl3

TlCl

Na2MoO4

NaI

NaIH3PO4

H2SO4

SulfurKCl

Cr metal (Cr 50

)Fe2O3 (Fe

58)

SrCO3 (Sr 84

)

HgOSn metal

(Sn112)

Yb2O3 (Yb168

)CaCO3 (Ca

44)

Fe2O3 (Fe54

)

Sn metal(Sn

118)

Cr

Fe59

Sr 85

Hg203

Sn113

Yb169

Ca45

Mn54

Sn119m

Na2CrO4 ampCrCl3

FeCl3

Sr(NO3)2

Hg(NO3)2

SnCl2 amp SnCl4

YbCl3

CaCl2MnCl2

SnCl2




eration

3METHODS




109 Fe

59 Co

60 and Am












(2) Work procedures




7172019 06




85 Xe

133) contained in







Kr

85 and Xe




















Sampling

times and

watersamples


(BqL)

Cs137

Sb12

4

Ru103

Nd147

Y91

Feb 2012


4

none


March



April





137 Sb

124 Ru

103




131 Kr

85 and




59 Co

60 Mn




Ba137




7172019 06









Sr 90












137 as radionuclide

standard




90 was





Radio nuc-lide

(half life)


LPHC(BqL

)TC Pool OPU

Cs

(3017y)

148 370 3256 7x102

Sb (603d) 444 903 533 7x102

Ru (3935d

)

459 3101 none 4x102

Nd (113d) 1188

4

none none 1x104

Y (61 d) 2398 none none 1x103

Sr (288y) 141 353 3108 7x102



137



147 and Sb





and Sr 90









Sb124

and Y91



of Ru103


137 and Sr

90 Ru






2





147 (T12 = 113 days) and Y

91 (T12 =





7172019 06





137 Ru

103 Y

91 Nd

147 and Sb

124









Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10



Ce144

Zn65

Co60

and Mn


product of Cs137

and Ce144

but Sr 90


147 Y

91 Sb

144 and Ru

103 were not


65 Co

60 and Mn

54 shows that the














Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April



ground activity



131 (fis-


85(γ) and Xe

133(γ) are not





7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06















IISSNF facility











11)

92U235

+ 0n1

Z1LA1

+ Z2HA2





235



12)

92U235

+ 0n1 38Sr

90 + 54Xe

143 + 3 0n

1 (2)

92U235

+ 0n1

37Rb96

+ 55Cs137

+ 3 0n1

(3)


and Cs137


given in Table 1


Fission product

Half life Yield ()

Tc137

Cs90

Sr 90

Y85

Kr147

Pm144

Ce95

Zr 95 Nb

91Y

89Sr

103 Ru

141

Ce143Pr

140Ba

147 Nd

131I

133Xe

21x10 years



6535 days61 days

530 days

398 days


113 days

81 days53 days

60

6258

152761

6454

48

30

606263

26

2965

In Table 1 90

Sr 90

Y and95



137 Sr

90 I

131 Kr

85 and


7172019 06








fuel

( weight)

Spent nuclear

fuel

( weight)

U238

955 93

U 45 1 TRU - 1

Fission Prod-ucts

- 5



235 (and

8025 U

238


238 8 U







13Al27

+ 0n1

11 Na24

+ 2α4 hellip (4)

13Al27

+ 0n1

12Mg27

+ 1 p1 hellip (5)

12Mg26

+ 0n1

12Mg27

+ γ hellip (6)

12Mg24

+ 0n1

11 Na24

+ 1 p1 (7)

14Si30+ 0n1




27 and Si




54 Co

60











239 but has







Pu239 241x10years

α γ

Pu240 656x10years

α γ


Pu242 375x10years

α γ


Np 21x10 years α


Cm 1628 days α

Cm 181 years α



Tc99m

I131

) industry(Ir

191 Co

60 Sr

90) agriculture (S

35 P

32 N

15) and Hy-


7172019 06









235) its fission


92U235 + 0n

142Mo99 + 50Sn136 +2 0n

1 +200 MeV


Whereas Tc99m




activation is I131


52Te130 + 0n1

52Te131 + γ (11)

52Te131

53I131

+ -1β0 (12)






in MPR-GAS 14)

TargetsProduct of

radioisotopes


U (

9315 )

U235

(9315 )

U235

( 9315 )

Ir 191

( wa-ferdisc)

Ir 191

( wa-ferdisc)


203)

MoO3TeO2

Xenon (Xe124

)

MoI131

Xe133

Ir 192

Ir 192

bulk

Ga67

Tl201

Mo99

I131

I

125

P32

S35

Na2MoO4

NaI

Xenon gasIrIr

GaCl3

TlCl

Na2MoO4

NaI

NaIH3PO4

H2SO4

SulfurKCl

Cr metal (Cr 50

)Fe2O3 (Fe

58)

SrCO3 (Sr 84

)

HgOSn metal

(Sn112)

Yb2O3 (Yb168

)CaCO3 (Ca

44)

Fe2O3 (Fe54

)

Sn metal(Sn

118)

Cr

Fe59

Sr 85

Hg203

Sn113

Yb169

Ca45

Mn54

Sn119m

Na2CrO4 ampCrCl3

FeCl3

Sr(NO3)2

Hg(NO3)2

SnCl2 amp SnCl4

YbCl3

CaCl2MnCl2

SnCl2




eration

3METHODS




109 Fe

59 Co

60 and Am












(2) Work procedures




7172019 06




85 Xe

133) contained in







Kr

85 and Xe




















Sampling

times and

watersamples


(BqL)

Cs137

Sb12

4

Ru103

Nd147

Y91

Feb 2012


4

none


March



April





137 Sb

124 Ru

103




131 Kr

85 and




59 Co

60 Mn




Ba137




7172019 06









Sr 90












137 as radionuclide

standard




90 was





Radio nuc-lide

(half life)


LPHC(BqL

)TC Pool OPU

Cs

(3017y)

148 370 3256 7x102

Sb (603d) 444 903 533 7x102

Ru (3935d

)

459 3101 none 4x102

Nd (113d) 1188

4

none none 1x104

Y (61 d) 2398 none none 1x103

Sr (288y) 141 353 3108 7x102



137



147 and Sb





and Sr 90









Sb124

and Y91



of Ru103


137 and Sr

90 Ru






2





147 (T12 = 113 days) and Y

91 (T12 =





7172019 06





137 Ru

103 Y

91 Nd

147 and Sb

124









Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10



Ce144

Zn65

Co60

and Mn


product of Cs137

and Ce144

but Sr 90


147 Y

91 Sb

144 and Ru

103 were not


65 Co

60 and Mn

54 shows that the














Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April



ground activity



131 (fis-


85(γ) and Xe

133(γ) are not





7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06








fuel

( weight)

Spent nuclear

fuel

( weight)

U238

955 93

U 45 1 TRU - 1

Fission Prod-ucts

- 5



235 (and

8025 U

238


238 8 U







13Al27

+ 0n1

11 Na24

+ 2α4 hellip (4)

13Al27

+ 0n1

12Mg27

+ 1 p1 hellip (5)

12Mg26

+ 0n1

12Mg27

+ γ hellip (6)

12Mg24

+ 0n1

11 Na24

+ 1 p1 (7)

14Si30+ 0n1




27 and Si




54 Co

60











239 but has







Pu239 241x10years

α γ

Pu240 656x10years

α γ


Pu242 375x10years

α γ


Np 21x10 years α


Cm 1628 days α

Cm 181 years α



Tc99m

I131

) industry(Ir

191 Co

60 Sr

90) agriculture (S

35 P

32 N

15) and Hy-


7172019 06









235) its fission


92U235 + 0n

142Mo99 + 50Sn136 +2 0n

1 +200 MeV


Whereas Tc99m




activation is I131


52Te130 + 0n1

52Te131 + γ (11)

52Te131

53I131

+ -1β0 (12)






in MPR-GAS 14)

TargetsProduct of

radioisotopes


U (

9315 )

U235

(9315 )

U235

( 9315 )

Ir 191

( wa-ferdisc)

Ir 191

( wa-ferdisc)


203)

MoO3TeO2

Xenon (Xe124

)

MoI131

Xe133

Ir 192

Ir 192

bulk

Ga67

Tl201

Mo99

I131

I

125

P32

S35

Na2MoO4

NaI

Xenon gasIrIr

GaCl3

TlCl

Na2MoO4

NaI

NaIH3PO4

H2SO4

SulfurKCl

Cr metal (Cr 50

)Fe2O3 (Fe

58)

SrCO3 (Sr 84

)

HgOSn metal

(Sn112)

Yb2O3 (Yb168

)CaCO3 (Ca

44)

Fe2O3 (Fe54

)

Sn metal(Sn

118)

Cr

Fe59

Sr 85

Hg203

Sn113

Yb169

Ca45

Mn54

Sn119m

Na2CrO4 ampCrCl3

FeCl3

Sr(NO3)2

Hg(NO3)2

SnCl2 amp SnCl4

YbCl3

CaCl2MnCl2

SnCl2




eration

3METHODS




109 Fe

59 Co

60 and Am












(2) Work procedures




7172019 06




85 Xe

133) contained in







Kr

85 and Xe




















Sampling

times and

watersamples


(BqL)

Cs137

Sb12

4

Ru103

Nd147

Y91

Feb 2012


4

none


March



April





137 Sb

124 Ru

103




131 Kr

85 and




59 Co

60 Mn




Ba137




7172019 06









Sr 90












137 as radionuclide

standard




90 was





Radio nuc-lide

(half life)


LPHC(BqL

)TC Pool OPU

Cs

(3017y)

148 370 3256 7x102

Sb (603d) 444 903 533 7x102

Ru (3935d

)

459 3101 none 4x102

Nd (113d) 1188

4

none none 1x104

Y (61 d) 2398 none none 1x103

Sr (288y) 141 353 3108 7x102



137



147 and Sb





and Sr 90









Sb124

and Y91



of Ru103


137 and Sr

90 Ru






2





147 (T12 = 113 days) and Y

91 (T12 =





7172019 06





137 Ru

103 Y

91 Nd

147 and Sb

124









Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10



Ce144

Zn65

Co60

and Mn


product of Cs137

and Ce144

but Sr 90


147 Y

91 Sb

144 and Ru

103 were not


65 Co

60 and Mn

54 shows that the














Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April



ground activity



131 (fis-


85(γ) and Xe

133(γ) are not





7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06









235) its fission


92U235 + 0n

142Mo99 + 50Sn136 +2 0n

1 +200 MeV


Whereas Tc99m




activation is I131


52Te130 + 0n1

52Te131 + γ (11)

52Te131

53I131

+ -1β0 (12)






in MPR-GAS 14)

TargetsProduct of

radioisotopes


U (

9315 )

U235

(9315 )

U235

( 9315 )

Ir 191

( wa-ferdisc)

Ir 191

( wa-ferdisc)


203)

MoO3TeO2

Xenon (Xe124

)

MoI131

Xe133

Ir 192

Ir 192

bulk

Ga67

Tl201

Mo99

I131

I

125

P32

S35

Na2MoO4

NaI

Xenon gasIrIr

GaCl3

TlCl

Na2MoO4

NaI

NaIH3PO4

H2SO4

SulfurKCl

Cr metal (Cr 50

)Fe2O3 (Fe

58)

SrCO3 (Sr 84

)

HgOSn metal

(Sn112)

Yb2O3 (Yb168

)CaCO3 (Ca

44)

Fe2O3 (Fe54

)

Sn metal(Sn

118)

Cr

Fe59

Sr 85

Hg203

Sn113

Yb169

Ca45

Mn54

Sn119m

Na2CrO4 ampCrCl3

FeCl3

Sr(NO3)2

Hg(NO3)2

SnCl2 amp SnCl4

YbCl3

CaCl2MnCl2

SnCl2




eration

3METHODS




109 Fe

59 Co

60 and Am












(2) Work procedures




7172019 06




85 Xe

133) contained in







Kr

85 and Xe




















Sampling

times and

watersamples


(BqL)

Cs137

Sb12

4

Ru103

Nd147

Y91

Feb 2012


4

none


March



April





137 Sb

124 Ru

103




131 Kr

85 and




59 Co

60 Mn




Ba137




7172019 06









Sr 90












137 as radionuclide

standard




90 was





Radio nuc-lide

(half life)


LPHC(BqL

)TC Pool OPU

Cs

(3017y)

148 370 3256 7x102

Sb (603d) 444 903 533 7x102

Ru (3935d

)

459 3101 none 4x102

Nd (113d) 1188

4

none none 1x104

Y (61 d) 2398 none none 1x103

Sr (288y) 141 353 3108 7x102



137



147 and Sb





and Sr 90









Sb124

and Y91



of Ru103


137 and Sr

90 Ru






2





147 (T12 = 113 days) and Y

91 (T12 =





7172019 06





137 Ru

103 Y

91 Nd

147 and Sb

124









Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10



Ce144

Zn65

Co60

and Mn


product of Cs137

and Ce144

but Sr 90


147 Y

91 Sb

144 and Ru

103 were not


65 Co

60 and Mn

54 shows that the














Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April



ground activity



131 (fis-


85(γ) and Xe

133(γ) are not





7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06




85 Xe

133) contained in







Kr

85 and Xe




















Sampling

times and

watersamples


(BqL)

Cs137

Sb12

4

Ru103

Nd147

Y91

Feb 2012


4

none


March



April





137 Sb

124 Ru

103




131 Kr

85 and




59 Co

60 Mn




Ba137




7172019 06









Sr 90












137 as radionuclide

standard




90 was





Radio nuc-lide

(half life)


LPHC(BqL

)TC Pool OPU

Cs

(3017y)

148 370 3256 7x102

Sb (603d) 444 903 533 7x102

Ru (3935d

)

459 3101 none 4x102

Nd (113d) 1188

4

none none 1x104

Y (61 d) 2398 none none 1x103

Sr (288y) 141 353 3108 7x102



137



147 and Sb





and Sr 90









Sb124

and Y91



of Ru103


137 and Sr

90 Ru






2





147 (T12 = 113 days) and Y

91 (T12 =





7172019 06





137 Ru

103 Y

91 Nd

147 and Sb

124









Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10



Ce144

Zn65

Co60

and Mn


product of Cs137

and Ce144

but Sr 90


147 Y

91 Sb

144 and Ru

103 were not


65 Co

60 and Mn

54 shows that the














Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April



ground activity



131 (fis-


85(γ) and Xe

133(γ) are not





7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06









Sr 90












137 as radionuclide

standard




90 was





Radio nuc-lide

(half life)


LPHC(BqL

)TC Pool OPU

Cs

(3017y)

148 370 3256 7x102

Sb (603d) 444 903 533 7x102

Ru (3935d

)

459 3101 none 4x102

Nd (113d) 1188

4

none none 1x104

Y (61 d) 2398 none none 1x103

Sr (288y) 141 353 3108 7x102



137



147 and Sb





and Sr 90









Sb124

and Y91



of Ru103


137 and Sr

90 Ru






2





147 (T12 = 113 days) and Y

91 (T12 =





7172019 06





137 Ru

103 Y

91 Nd

147 and Sb

124









Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10



Ce144

Zn65

Co60

and Mn


product of Cs137

and Ce144

but Sr 90


147 Y

91 Sb

144 and Ru

103 were not


65 Co

60 and Mn

54 shows that the














Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April



ground activity



131 (fis-


85(γ) and Xe

133(γ) are not





7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06





137 Ru

103 Y

91 Nd

147 and Sb

124









Waste of

spent resin

The content of

radionuclides

Total activity

(BqL)

Tank-I Cs Ce Zn

65 Co

60 Mn

54

807x10

Tank-II Cs Ce Zn

65

Co60

Mn54

699x10

Tank-III Cs Ce

Zn65

Co

60 Mn

54

599x10

Tank-IV Cs Ce Zn65

Co

60 Mn

54

973x10



Ce144

Zn65

Co60

and Mn


product of Cs137

and Ce144

but Sr 90


147 Y

91 Sb

144 and Ru

103 were not


65 Co

60 and Mn

54 shows that the














Period ofsampling

Areaor

room

Air contamina-tion

(Bqm3)

α βγ

Feb2012 Pool 00109 0723

ACS none 5158

OAS none none

March 2012 Pool 00106 0761

ACS none 46891

OAS 00052 00898

April



ground activity



131 (fis-


85(γ) and Xe

133(γ) are not





7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06






from I131


131 Kr

85 and Xe




[7]


3 so


1x10-2

BqL or 10 Bqm3 15)


131 Kr

85 and Xe

133 in ambient



and Xe133










2 or Bqcm



Period of

sampling

Room or

area

Surface conta-

mination level(Bqcm

2)

α βγ



Pool-I none none

IPool-I

II

none none

TC-I 00009 00210




I

none 00336

Pool-I

II

00017 00271

TC-I none 00405

TC-II none 00274

TC-III none none

PUR 00015 00228



Pool-II

00009 00216

Pool-I

II

00003 00494

TC-I 00009 00370

TC-II none 01389

TC-III none 07321PUR 00472 06414



activity (lt 1 Bqcm

2



Bqcm2)[7]








7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06




-3 155x10

-3 and 82x10









facility17)




IISSNF operation








(I131

Kr 85

and Xe133









5CONCLUSION



137 Nd

147 Sb

124 Y

91) in



Co

60 and Mn





Kr 85

and Xe133









7172019 06


































7172019 06


































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