The Review of the Reactor Physical Experiments Carried out on the LR-0 Research Reactor NRI Řež plc for Reactors of the VVER Type František Hudec†, Bohumil Jánský, Vlastimil Juříček , Ján Mikuš, Evžen Novák, Bohumil Ošmera†, Severin Pošta, Vojtěch Rypar, Marie Švadlenková
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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
�� 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
�� 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)..
�� 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.
�� 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..
�� 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..
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).
�� 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..
�� 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.
�� 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
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
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
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.
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
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
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%
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
-- 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
�� 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
n/γ separation (AmBe neutron – gamma source)Digital Spectrometer Development
CONTACTSCONTACTSAddressAddress::Nuclear Research InstituteNuclear Research Institute ŘŘeežž plcplc..ResearchResearch Center Center ŘŘeežž Ltd.Ltd.250 68 Husinec 250 68 Husinec –– ŘŘeežž 130130CzechCzech RepublicRepublic