The Review of the Reactor Physical Experiments Carried out on the LR-0 Research Reactor NRI Řež plcfor Reactors of the VVER TypeFrantišek Hudec†, Bohumil Jánský, Vlastimil Juříček, Ján Mikuš, Evžen Novák, Bohumil Ošmera†, Severin Pošta,Vojtěch Rypar, Marie Švadlenková

GeneralGeneral informationinformation

GeneralGeneral informationinformation

LRLR--0 0 ReactorReactor

�� EExperimentalxperimental zerozero ppowerower rreactoreactor

�� MAIN USE: DMAIN USE: Determinationetermination of theof the nneutroneutron-- physical physical ccharacteristicsharacteristics oof f WWERWWERand and PWRPWR ttypeype rreactoreactor llatticesatticesand and sshieldinghielding with with UOUO22 oror MOXMOX ffueluel

GeneralGeneralDescriptionDescription

TechnicalTechnicalParametersParameters 11

MaximalMaximal

powerpower:: …………………….. .. 1 kW1 kW

MaximalMaximal

ThermalThermal

FFluxlux::…………10101313 n.mn.m--22.s.s--11

ReactorReactor

vessel: vessel: diamdiam..... ... 3.5 m3.5 m

heightheight 6.5 m6.5 m

AtmosphericAtmospheric

PressurePressure

Room temperatureRoom temperature

or heating or heating up toup to 7070ooCC

TechnicalTechnicalParametersParameters 22

Fuel :Fuel :-- shortened shortened VVERVVER--10001000

and and VVERVVER--440440 fuel assembliesfuel assemblies

-- enrichment enrichment 1.6 1.6 -- 4.4 % in U4.4 % in U235235

-- 6565 dismountable VVERdismountable VVER--10001000

fuel assemblies fuel assemblies

FuelFuel

element :element :-- UOUO22 pellets o.d.pellets o.d. 7.53 mm7.53 mm

active length active length 11 250 mm250 mm

-- total length total length 11 357 mm357 mm

-- claddingcladding

(Zr+1%Nb) o.d.(Zr+1%Nb) o.d. 9.15x 0.72 mm9.15x 0.72 mm

TechnicalTechnicalParametersParameters 33

Control :Control :

-- moderator levelmoderator level

boron acid boron acid -- up to 12 g/kgup to 12 g/kg

-- control clusterscontrol clusters --BB44CC pelletspellets

StartStart--up:up: 19831983

LRLR--0 0 ExperimentalExperimentalAdvantagesAdvantages 1/1/44

�� WWWWER and PWR related ER and PWR related radiallyradially to to full scale full scale experimentsexperiments..

�� FFlexiblelexible rearrangementsrearrangementsof the coreof the core..

�� FFlexiblelexible operationoperation..

�� MModelingodeling neutron field neutron field parameters of power parameters of power reactorsreactors..

�� CCapabilityapability to design and to design and operate operate multizonemultizone corescores,,i.e. substituted cores, i.e. substituted cores, with an inner inserted part with an inner inserted part in in hexagonalhexagonal or or squaresquaregeometrygeometry (driven by LR(driven by LR--0 0 standard assemblies)standard assemblies)..

LRLR--0 0 ExperimentalExperimentalAdvantagesAdvantages 2/2/44

�� Standard Standard andand specialspecialsupporting platesupporting plates for s for MOCKMOCK--UPUPss experimentsexperiments..

�� SSpecialpecial supporting platesupporting plates, s, which enables the which enables the triangulartriangular symmetrical symmetrical assemblyassembly arrangementarrangementwith an arbitrary pitch.with an arbitrary pitch.

LRLR--0 0 ExperimentalExperimentalAdvantagesAdvantages 33//44

�� MModelingodeling neutron field neutron field parameters of power parameters of power reactorsreactors..

�� WWideide range benchmarking range benchmarking possibilities, with high possibilities, with high reproducibility of the reproducibility of the benchmark design benchmark design parametersparameters..

�� WWideide range of measurement range of measurement techniques including techniques including equipment and experienced equipment and experienced personalpersonal..

LRLR--0 0 ExperimentalExperimentalAdvantagesAdvantages 44//44

Reactor Hall

Laboratory of n,g Spectrometry

TheThe ShortShort ReviewReview ofof ExperimentalExperimental ProjectsProjects

1.1. PiPin Wise Flux n Wise Flux DDistributionistribution MeasurementsMeasurements2.2. WWWERWER--440440 AndAnd WWERWWER--10001000 MockMock--uuppss3.3. Compact Spent Fuel StorageCompact Spent Fuel Storage4.4. SpaceSpace KineticsKinetics ExperimentExperiment5.5. Core ParametersCore Parameters ExperimentalExperimental DeterminationDetermination6.6. Experiment With New Design Fuel AssemblyExperiment With New Design Fuel Assembly7.7. WWERWWER--440 440 ControlControl AssemblyAssembly InfluenceInfluence8.8. Burnable Absorber StudyBurnable Absorber Study

ReviewReview ofof experimentalexperimentalprojectsprojects 1/1/55

�� PIPIN WISE FLUX N WISE FLUX DISTRIBUTION DISTRIBUTION MEASUREMENTS:MEASUREMENTS:

RRadialadial and axial fission density and axial fission density distributionsdistributions in the fuel in the fuel assemblies, e.g. the model of assemblies, e.g. the model of WWERWWER--440 control assembly 440 control assembly type with and without partially type with and without partially inserted absorption part, WWER inserted absorption part, WWER -- 440 and WWER 440 and WWER -- 1000 1000 MOCKMOCK--UPsUPs, compact spent fuel , compact spent fuel storage lattices, burnable storage lattices, burnable absorber study (absorber study (GdGd22OO33 and and ZZrBrB22), experiments with WWER), experiments with WWER--440 profiled fuel assembly440 profiled fuel assembly..

ReviewReview ofof experimentalexperimentalprojectsprojects 2/2/55

�� WWERWWER--440440

andand

WWERWWER--10001000

MOCKMOCK--UPsUPs::MMeasurementseasurements of the of the spacespace--energy distributionenergy distributionof the neutron flux for RPV of the neutron flux for RPV dosimetrydosimetry purposes purposes -- in the in the vicinity of the pressure vicinity of the pressure vessel model (from the core vessel model (from the core boundary to the biological boundary to the biological shielding).shielding).

ReviewReview ofof experimentalexperimentalprojectsprojects 33//55

�� COMPACT SPENT FUEL COMPACT SPENT FUEL STORAGE:STORAGE: experimental experimental VVerificationerification of the criticality safety of the criticality safety with relation to design parameters with relation to design parameters and different absorbing materialand different absorbing material..

ReviewReview ofof experimentalexperimentalprojectsprojects 44//55

�� SPACE KINETICS EXPERIMENT:SPACE KINETICS EXPERIMENT:BBenchmarkenchmark data for spacedata for space--time kinetics time kinetics code qualification.code qualification.

�� CORE PARAMETERS:CORE PARAMETERS: IIntegralntegral and and safety parameters, such as control and safety parameters, such as control and shutshut--down rods integral and differential down rods integral and differential efficiency, critical water level, efficiency, critical water level, waterwater level level reactivity coefficient.reactivity coefficient.

�� EXPERIMENT WITH NEW DESIGN EXPERIMENT WITH NEW DESIGN FUEL ASSEMBLY:FUEL ASSEMBLY: IInfluencenfluence of new of new profiled fuel assembly and spacerprofiled fuel assembly and spacer--grid grid material on the pin wise spatial flux density material on the pin wise spatial flux density distribution.distribution.

ReviewReview ofof experimentalexperimentalprojectsprojects 55//55

�� WWERWWER--440 CONTROL 440 CONTROL ASSEMBLY INFLUENCE:ASSEMBLY INFLUENCE:MMeasurementeasurement of pin wise flux of pin wise flux distributions.distributions.

�� BURNABLE ABSORBER BURNABLE ABSORBER STUDY:STUDY: PPowerower distribution distribution measurements with measurements with GdGd22OO33 and and ZZrBrB22 absorbers.absorbers.

Model Model ofof WWERWWER--440 440 ControlControlAssemblyAssembly usedused on LRon LR--0 0

WWERWWER--440 440 CONTROL CONTROL ASSEMBLYASSEMBLY

Principal

scheme with

details of

important

parts.

Details of grids

and outer coat.

ExamplesExamples ofof thethe ExperimentalExperimental ProjectsProjectsin more in more detailsdetails

1.1. Experimental verification of proposed solutions for theExperimental verification of proposed solutions for the VVERVVER--440440 control assembly coupler inducedcontrol assembly coupler induced power peakingpower peaking

2.2. BUC BUC –– BurnBurn--UpUp CreditCredit measurementmeasurement

3.3. The complex benchmarking of the radiation field in the vicinity The complex benchmarking of the radiation field in the vicinity of the RPV of the RPV -- included in the included in the programmeprogramme of the REDOS (of the REDOS (REactorREactorDOSimetryDOSimetry) project) project

4.4. WWER WWER PhysicsPhysics ExperimentsExperiments: : HexagonalHexagonal LatticesLattices(1.22(1.22--cm cm PitchPitch) ) o o LowLow--enrichedenriched U(3.6, 4.4 U(3.6, 4.4 WtWt.% U235) O2 .% U235) O2 FuelFuel AssembliesAssemblies in in LightLight WaterWater withwith VariableVariable FuelFuel--assemblyassembly PitchPitch

5.5. SpentSpent FuelFuel TransmutationTransmutation ExperimentsExperiments

6.6. Boric acid Boric acid ((1010B) B) concentration measurementconcentration measurement systemsystem forfor nuclearnuclearpowerpower plantsplants

CoreCore LoadingLoading for for ControlControl AssemblyAssembly ExperimentExperiment

Full Fuel AssemblyFull Fuel AssemblyEnrichment 1Enrichment 1

Half Fuel AssemblyHalf Fuel AssemblyEnrichment 2Enrichment 2

Full Fuel AssemblyFull Fuel AssemblyEnrichment 2Enrichment 2

Control AssemblyControl Assembly

1. 1. Experimental verification of proposed Experimental verification of proposed solutions for thesolutions for the VVERVVER--440440 control assembly control assembly coupler inducedcoupler induced power peakingpower peaking

FISSION DENSITY AXIAL DISTRIBUTIOFISSION DENSITY AXIAL DISTRIBUTIO NNmeasurementmeasurement

K ( j ) = M ( j ) / M ( 4 ) …. j = 1,2,3,5

RELATIVERELATIVE FISSION DENSITY FISSION DENSITY AXIAL DISTRIBUTIOAXIAL DISTRIBUTIO NN(for (for allall variantsvariants ))

Bottom Partof the ControlAssembly withHafnium Plates

1. Comparison of different variants - with and without hafnium

plates - is possible due to similar critical water levels

(corresponding to the same boron acid concentration in the

moderator).

2. Numerical comparison of Hf plating: power peaking factors

for different axial heights – total maximum of distribution or local

maximum corresponding coupler region.

Using axial fission distributions we could compare: a) variant No. 1 & 2 Hcr = 72.164 cm & 77.167 cmb) variant No. 3 & 4 Hcr = 112.816 cm & 111.374 cm

COMPARISON COMPARISON POSSIBILITY POSSIBILITY OF OF LRLR--0 0 AXIAL AXIAL FISSION PRODUCTS DISTRIBUTIONFISSION PRODUCTS DISTRIBUTIONSS

ComparisonComparison ofof totaltotal axialaxial fissionfission productsproductsdistributiondistribution vvariantariant No.1No.1 andand vvariantariant No.4No.4

0

10000

20000

30000

40000

50000

60000

0 20 40 60 80 100 120

H

M1 Var4

M2 Var4

M3 Var4

M4 Var4

M5 Var4

M1 Var1

M2 Var1

M3 Var1

M4 Var1

M5 Var1

FISSION DENSITY AXIAL DISTRIBUTIOFISSION DENSITY AXIAL DISTRIBUTIO NNvariant No.2variant No.2

z[cm]

M1

M2

M3

M4

M5

0

10000

15000

20000

25000

30000

35000

40000

45000

50000

0 10 20 30 40 50 60 70 80

5000

77.167 cm

FISSION DENSITY AXIAL DISTRIBUTIOFISSION DENSITY AXIAL DISTRIBUTIO NNvariant No.3variant No.3

0 10 20 30 40 50 60 70 80 90 100 110z[cm]

0

5000

10000

15000

20000

25000

30000

35000

40000

coun

t M1

M5

M2M3

M4

112.95cm

Experiment description:Verification of the 2nd generation profiled fuel peaking under high boron conditions for CRF and with Hf platingof the production type.

ResultsResults : : Extension of the experimental Extension of the experimental database 2006 database 2006 -- 20072007

Technical needs:We need either 1 shortened fuel assembly of 2nd generation fuel or to approximately model it with fuel elementsof other enrichments.

Present status:This case has been left open - so far funding and fuel assembly is not ensured.

2. BUC 2. BUC –– BurnBurn --UpUp CreditCreditmeasurementmeasurement

II

M1

I control system linear chambers

M experimental neutron chambers

M4 inverse kinetics neutron chambers

water level unit

M2

M4

M

III

I control sytem logaritm. chambers

19 fuel assemblies VVER-440/LR-0 enrichment 3.6%

cluster LR -0/VVER-1000

116

120

105 112

114

119 110

108

103 109

111

106

102

118

107

115

104

101

117

HK

15 I

IV

VI

EXP2 32

HK

V EXP1

27

HK3

HKXcluster LR -0/VVER-440

HK shut down cluster

EXP experimental xxx

HK

HK

13

HK

XX

HK3

36

6

3

21

42

15

30

28

32

10

24

39

7

18

R [cm] δρ/δH

[pcm/cm] σ

[pcm] Hkrit

[cm] σ

[cm] Ô

[cm] Var.

98.1685 2.2511 76.5226 0.0167 0.0530 19 x 3,6 ATABOR1

221.933 3.5436 54.0364 0.0021 0.0503 19 x 3,6, Fe

18.5

263.144 7.9935 51.5795 0.0095 0.0511 18 x 3,6, 1 x 4,4 Fe

80.5775 7.0756 77.6734 0.1382 0.1471 19 x 3,6, Fe 19.0

123.5275 8.3205 71.4046 0.1312 0.1405 18 x 3,6, 1 x 4,4 Fe

40.8595 0.2028 104.5015 0.0757 0.0909 19 x 3,6, Fe 19.25

54.4619 0.716803 92.1729 0.0199 0.0540 18 x 3,6, 1 x 4,4 Fe

54.4484 0.1576 93.9544 0.0086 0.0510 18 x 3,6, 1 x 4,4 19.5

31.2259 0.632723 111.524 0.1433 0.1519 19 x 3,6

367.622 2.2690 38.8028 0.0185 0.0535 19 x 3,6

493.398 8.1720 37.6118 0.0034 0.0504 18 x 3,6, 1x 4,4

353.599 19.6349 41.7399 0.0114 0.0504 18 x 3,6, 1x 4,4 Fe

363.552 13.9265 43.3637 0.0073 0.0508 19 x 3,6 Fe

195.367 4.3100 57.0873 0.0967 0.1090 19 x 3,6 ATABOR2

186.393 5.8553 56.0344 0.01320 0.0520 19 x 3,6 ATABOR1

199.792 0.8020 55.6770 0.0028 0.0503 18 x 3,6, 1x 4,4 ATABOR2

18.0

210.147 5.2353 54.7852 0.0103 0.0513 18 x 3,6, 1x 4,4 ATABOR1

CriticalityCriticality measurementmeasurement

Extension of the validation tasks for availability and accuracy of calculation codes used forcriticality safety analysis verification of the storage lattice or VVER-440 reactor corerespectively.

3. 3. The complex benchmarking of the radiation field in The complex benchmarking of the radiation field in the vicinity of the RPV the vicinity of the RPV -- included in theincluded in the pprogrammerogramme of of the REDOS the REDOS ((REactorREactor DOSimetryDOSimetry ) ) project.project.

Scheme ofmeasurement in RPV (step 5 cm)

RPV0-RPV20 Photon spectra over RPVRPV surface = RPV-0

RPV outer = RPV – 20 [cm]

RPV model withazimuthal mappingdevice

RPV simmulator

4. 4. WWER WWER PhysicsPhysics ExperimentsExperiments::

LEULEU--8xx8xx

MCNP model for criticality calculation WWER-1000

Hexagonal Lattices(1.22-cm Pitch) ofLow-enriched U(3.6, 4.4 Wt.% U235) O2 Fuel Assemblies in Light Waterwith Variable Fuel-assembly Pitch

a) LEU-86 – WWER-1000b) LEU-87 – WWER-440c) LEU-HRK – Control Assembly

LEU-86

PublishedPublished ::NEA/NSC/DOC/(95)03/IV NEA/NSC/DOC/(95)03/IV Volume IVVolume IVLEULEU--COMPCOMP--THERMTHERM--086086

LEULEU--86 WWER86 WWER--10001000

MCNP model for criticality calculation WWER-440

VVER-440/LR-0control-custerassembly

VVER-440/LR-0control-clusterassembly

Central fuelassembly

3.6% fuelassembly

Control clusterassemblystructural

tubes

Control clustergrid

FA spacing grid

VVER-440SC nest

VVER-440nest

Central tube

Detail of FA bottom part

Fuel element

FA assembly base plate

Al base forhexagonal Al tube

VVER-440 nest

H O2

Standard plate

Benchmark plate

Special plate

Control clusterassembly cut

Central FA fuel cut

Central FA bottom grid cut

Central FA nest cut

Fuel element

FA Al tube

ATABOR

08-GA50017-85-1

39.0

158.6

LEU-87

LEULEU--87 WWER87 WWER--440440

WWER WWER PhysicsPhysics ExperimentsExperiments::

LEULEU--8xx8xx

PublishedPublished ::NEA/NSC/DOC/(95)03/NEA/NSC/DOC/(95)03/IVVolumeIVVolumeIVLEUIVLEU--COMPCOMP--THERMTHERM--087087

LEU-HRK

LEULEU--HRK HRK WWERWWER--440 440 ControlControl AssemblyAssembly

WWER WWER PhysicsPhysics ExperimentsExperiments::

LEULEU--8xx8xx

PublishedPublished : : UnderUnder RevisionRevision

WWERWWER--440 440 CONTROL CONTROL ASSEMBLYASSEMBLY

Principal

scheme with

details of

important

parts.

Details of grids

and outer coat.

5. 5. SpentSpent FuelFuel TransmutationTransmutation ExperimentsExperiments

Driver Driver CoreCore

Insert Insert CoreCore withwithFluoride Fluoride SaltsSalts MixtureMixture

RadialRadial DistributionDistribution ofof FissionFission ProductsProductsin LRin LR--0 FA0 FA

The radial distributionof fission products(represented by gammaenergy in keV) in LR-0 fuelassemblies

6.6. Boric acid concentration measurementBoric acid concentration measurement

onon NNuclearuclear PowerPower PlantsPlants

Boron isotope 10B

TheThe SelectionSelection ofof PublishedPublished ExperimentsExperiments on LRon LR--0 0 ResearchResearch ReactorReactor -- 11

Report, PublicationExperiment (Benchmark, Mock-Up) performed on LR-0

ÚJV 10190-R,T 4/1994WWER-440 Control Assembly Influence Measurement (Contract between NRI Řež and NPP Paks Nr. PA-4-0704-3-HJ)

ÚJV 8879-R,T 1990Meeting IAEA Vienna, 11-14 December 1989,

Safety Aspects of Using Gd Poisoned Fuel in the WWER Reactors(Proceedings of the I.symposium AER, NRI Řež, 1991, Progress Report IAEA Contract Nr. 5328/RB )

ÚJV Z 5/1993Criticality Benchmark Experiment of Spent Fuel WWER-440 ContainerCASTOR 440/84 Type

ÚJV Z 215-R,T 5/1997ÚJV Z 188-F 1996

Power Space Distribution in the LR-0 Reactor Core – 32 FA of WWER-1000

ÚJV 9511-R,T 11/1991 LR-0 Reactor Benchmark Core Symmetry Verification

ÚJV 9818-R,T 12/199212/1992ÚJV 9866-R,T 2/1993

WWER-1000 Benchmark Reactor Core Power And Neutron Flux Distribution Measurement (IAEA Research Contract No. 5964/RB, 1992)

ÚJV 10308-R,F,T (OCT1994)Spent Fuel VVER-440 Compact Container ALSTOR (SKODA JS) CriticalityVerification

IAEA Research Contract No. 7660/EN, June 1996

Comparison of the Power Distribution in the WWER-1000 Type 2% 235U Fuel Assembly Calculated Using Either Diffusion or Transport Code and EitherAsymptotic or Non-asymptotic Constants for Elementary Cells

ÚJV 8968-R,T (1988)Power Space Distribution in the LR-0 Reactor Core – 13 FA of WWER-440, Enrichment 3.6%

TheThe SelectionSelection ofof PublishedPublished ExperimentsExperiments on LRon LR--0 0 ResearchResearch ReactorReactor -- 22

NEA/NSC/DOC/(95)03/IV Volume IV LEU-COMP-THERM-087

WWER Physics Experiments: Hexagonal Lattices(1.22-cm Pitch) o Low-enriched U(3.6, 4.4 Wt.% U235)O2 Fuel Assemblies in Light Water withVariable Fuel-assembly Pitch

Report, PublicationExperiment (Benchmark, Mock-Up) performed on LR-0

September 14-19, 2008 New WWER Benchmark on the LR-0 Reseasrch Reactor (InternationalConference on the Physics of Reactors Nuclear Power, Switzerland)

Science and Techn. of Nuclear Install., Vol. 2008, Art.ID 753091, 5

Power Distribution and Possible Influence onFuel Failure in WWER-1000

UJV Z 2526 8/2009WWER-440 Local Power Peaking ExperimentEXPERIMENT-TO-CODE BENCHMARK SOLUTIONWITH MCNP5

ÚJV č. – 11576 R 12/2000LR-0 Reactor Core Criticallity Measurement for Calculation Method Validation

ÚJV 12345 R,F 12/2006Fission Density Distribution Measurement in Vicinity of WWER-440 Control Assembly Model in LR-0 Reactor (IAEA RER/9/076 PROJECT)

ÚJV 9506-R 1991 WWER-440 Spent Fuel Compact Storage Neutron-Physical CharacteristicMeasurement (Russian Contract N 54-02/88147-108, 1983 - 1989)

ÚJV Z 339-R,T 1/1999 Database for VVER-1000 Reactor Pressure Vessel , May 1997 Dosimetry,ASTM STP PA1.04, PA2000

ÚJV č. Z 274 12/1997Nucleon No. 2, 1998NUKLEONIKA´98 Conference

Influence of Improved Fuel on Neutron Flux Distribution in WWER-440 FuelAssembly of JEDU NPP

TheThe SelectionSelection ofof thethe RealizedRealized ProjectsProjects

IAEA Wienna1995SRR 2/95

TACIS Development of Advanced Methods for theEvaluation Of Irradiation Embrittlement of WWER-1000/320 Type RPVS -Dosimetry BenchmarkExperiment

No. 1H-PK2/20

No. 1H-PK2/05

FT-TA/055

FIR1-CT-2002-40157

FIKS-CT-2001-00120

RER/9/076 89432J

RER/4/017

Acronym

Ministry of Industry and Tradeof the Czech Republic

Ministry of Industry and Tradeof the Czech Republic

Ministry of Industry and Tradeof the Czech Republic

IAEA Wienna

IAEA Wienna

IAEA Wienna

IAEA Wienna

Suported by

2005Reactor Physics Experiments for Advanced and NewReactor Types

StartName

2004Neutron an Photon Progressive Detection MethodsUtilisation in Applied Research for Nuclear Facilities

2004SPHINX Nuclear Transmutation System

2003RENION Reactor Neutronic Investigations on LR-0 Research Reactor

2001REDOS Reactor Dosimetry – Accurate Determinationand Benchmarking of Radiation Field ParameterRelevant for Pressure Vessel Monitoring

2000Strengthening safety and reliability of nuclear fuel andmaterials in nuclear power plants – WG3 “WWER 440 Local Power Peaking Induced by Control Rods

1995Database For Qualification of the WWER-1000 Reactor Pressure Vessel Exposure Evaluation

LVR-15 – Sodium Cooled Fast Reactorsmeasurements on full scale model ofstraight and bent sodium pipe withdiam of 40cm

InternationalInternational CoCo--OperationOperationRussian Russian RResearchesearch CCentresentres

Shielding – neutron transport through sodium pipeline

Sodium blocks for pipeline modelling

Institute Institute ofof PhysicsPhysics andand PowerPower

EngineeringEngineering, , ObninskObninsk

InternationalInternational CoCo--OperationOperationRussian Russian RResearchesearch CCentresentres

ДоговорДоговор ««РеперныеРеперные экспериментальныеэкспериментальные исследованияисследованияполяполя быстрыхбыстрых нейтроновнейтронов вв макетемакете реакторареактора ВВЭРВВЭР нанастендестенде LRLR--0 0 вв обоснованиеобоснование методикиметодики уточнённогоуточнённогорасчётарасчёта радиационнойрадиационной нагрузкинагрузки корпусакорпуса ии образцовобразцов--свидетелейсвидетелей ии методикиметодики мониторингамониторинга радиационнойрадиационнойнагрузкинагрузки корпусакорпуса»»

CommonCommon experimentalexperimental projectsprojects on LRon LR--0 0 reactorreactor

WWWWER ER RReactorseactors DDosimetryosimetry

�� RussianRussian ResearchResearch Centre Centre KurtchatovKurtchatov Institute, Institute, NuclNucleearar ReactorReactor InstituteInstitute

�� FSUE OKB "GIDROPRESS", Podolsk FSUE OKB "GIDROPRESS", Podolsk

�� FSUE "SSC RIARFSUE "SSC RIAR„„ DimitrovgradDimitrovgrad, , UlyanovskUlyanovsk regionregion

-- ThermalThermal neutronsneutrons measurementmeasurement

Russian Russian RResearchesearch CCentresentres

CommonCommon experimentalexperimental projectsprojects on LRon LR--0 0 reactorreactor

Neutron Neutron andand GGammaamma FFieldsields SSpectrapectra

MMeasurementeasurement andand EEvaluationvaluation

�� SSC RFSSC RF--Institute Institute ofof PhysicsPhysics andand PowerPower EngineeringEngineering, , ObninskObninsk

-- Nuclear data base in transmutation, activation and radiationNuclear data base in transmutation, activation and radiationdamage behavior of materials in different neutron spectradamage behavior of materials in different neutron spectra

�� SRC RF TRINITI, SRC RF TRINITI, TroitskTroitsk, , MoscowMoscow

-- Si Si gammagamma spectrometersspectrometers

�� SECNRS, SECNRS, MoscowMoscow -- ««НаучноНаучно--техническийтехнический центрцентр попо ядернойядернойии радиационнойрадиационной безопасностибезопасности»» НТЦНТЦ ЯРБЯРБ

SupportingSupporting LaboratoryLaboratory atat thethe LRLR--0 0 reactorreactor -- 11LSNMLSNM -- LaboratoryLaboratory ofof SpectrometrySpectrometry andand Neutron Neutron MeasurementMeasurement

�� BenchmarkBenchmark experimentsexperimentson on sphericalspherical oror cylindricalcylindricalassembliesassemblies

�� WWideide range range ofof reactorreactor materialsmaterials : : FeFe, H20, D20, Na , H20, D20, Na andand NiNi

�� CfCf--252 252 drivendriven experimentalexperimentalassembliesassemblies –– measurementmeasurement in in wellwell describeddescribed ((measuredmeasured andandcalculatedcalculated ) ) mixedmixed neutron neutron andandgammagamma fieldsfields

�� HighHigh reproducibilityreproducibility ofof physicalphysicalparametersparameters

�� NuclearNuclear data data librarieslibraries testingtesting(JEFF, BROND, JENDL, ENDF) (JEFF, BROND, JENDL, ENDF) basedbased on on integralintegral measurementmeasurement

Laboratory for n, g SpectrometryExperimental Assemblies of

LSNMLSNM -- LaboratoryLaboratory ofof SpectrometrySpectrometry andand Neutron Neutron MeasurementMeasurement

Measurement Method

effect

E

100

air background

AB

floor background

FB

labbackground

LB

Detector

FlexoRabbit

Shadow Cone

Cf-252 neutron sourceplacedin the centre

Iron Sphere

200

Feø100cm

Fe PE+B20 30

Spectrometer

NOTE: All dimesions are in cm

Principalmeasurementscheme ofleakageneutronspectrumfrom ironsphere ofdiam. 100cm.Shadow Cone:Fe – iron,PE+B –polyethylenewith boron

EFFECT E EVALUATIONEFFECT E EVALUATIONA = E + AB + FB + LBA = E + AB + FB + LB -- measmeas .. without without

shadow coneshadow cone

B =B = AB + FB + LBAB + FB + LB -- measmeas .. with with shadow coneshadow cone

E = A E = A -- BB

Boron Neutron Capture Therapy – reactor beam

n,g characteristics measurementDevelopment of measurement methods and equipmnets for thebeam parameter (stability, reproducibility) fast testing

LSNMLSNM –– AuxiliaryAuxiliary ActivitiesActivities ExampleExample

BNCT BNCT FacilityFacility MeasurementMeasurement

BNCT neutron beam

on LVR-15 reactor

beam output

SupportingSupporting LaboratoryLaboratory atat thethe LRLR--0 0 reactorreactor -- 22

LaboratoryLaboratory forfor GammaGamma ScanningScanning

Gamma Scanning of irradiated

fuel elements for determination

of Neutron Flux Distribution

in Reactor Core

LaboratoryLaboratory forfor GammaGamma SpectrometrySpectrometry

Digital Spectrometry Project

# ch 40.0 0.00 0.00

Qf (a.u.)

Counts

Qs (a.u.)

100.0

0.1

1.0

10.0

150

0

10

20

30

40

50

60

70

80

90

100

110

120

130

140

Qs (a.u.) 190 0 20 40 60 80 100 120 140 160 180

n/γ separation (AmBe neutron – gamma source)Digital Spectrometer Development

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