research reactor lr-0 2010 vver meeting · 2011. 3. 2. · vver-440/lr-0 enrichment 3.6% cluster lr...
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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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