nuclear fuel for vver reactors. actual state and...
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NUCLEAR FUEL FORNUCLEAR FUEL FORVVER REACTORS.VVER REACTORS.ACTUAL STATE AND ACTUAL STATE AND TRENDSTRENDS
Presented byPresented by VV. . MolchanovMolchanovdeputy executive directordeputy executive director
8th International Conference on VVER Fuel Performance, Modeling and Experimental Support 27.09–02.10.2009, Helena Resort, Bulgaria
P. LavrenyukV. MolchanovV. Ionov
8th International Conference on VVER Fuel Performance, Modeling and Experimental Support 27.09–02.10.2009, Helena Resort, Bulgaria 2
Development, fabrication and implementation of new Development, fabrication and implementation of new generation of fuel assemblies for VVERgeneration of fuel assemblies for VVER--type reactorstype reactors
Satisfaction of Customer needs Satisfaction of Customer needs regarding nuclear fuel performance regarding nuclear fuel performance
and value improvementand value improvement
Competitive advantages and marketing developmentCompetitive advantages and marketing development
Providing enhanced safety of fabrication and use of nuclear fuelProviding enhanced safety of fabrication and use of nuclear fuel
TVEL Corporation Prime ObjectivesTVEL Corporation Prime Objectives
8th International Conference on VVER Fuel Performance, Modeling and Experimental Support 27.09–02.10.2009, Helena Resort, Bulgaria 3
Tasks to be solved and Methods of SolutionTasks to be solved and Methods of Solution
Increasing of FA service Increasing of FA service lifetimelifetime
Improving reliabilityImproving reliability((demountable FA, debris demountable FA, debris
filtersfilters, , chatterchatter--resistant FAresistant FA))
Increasing of fuel Increasing of fuel burnburn--upup
UprateUprate
Implementation of Implementation of 55--66––years fuel cyclesyears fuel cycles
Decreasing of irradiation impact Decreasing of irradiation impact on the rector vesselon the rector vessel
Implementation of safe and costImplementation of safe and cost--effective fuel effective fuel cyclescycles
8th International Conference on VVER Fuel Performance, Modeling and Experimental Support 27.09–02.10.2009, Helena Resort, Bulgaria 4
Эксплуатируемыеэнергоблоки 24
Novovoronezh NPPNovovoronezh NPP
Armenian NPPArmenian NPP
BoguniceBogunice NPPNPP MohovceMohovce NPPNPP Rivne NPPRivne NPP
DukovanyDukovany NPPNPP LoviisaLoviisa NPPNPP Kola NPPKola NPP
Number of Number of operating unitsoperating units 2323
VVERVVER‐‐440 Nuclear Fuel440 Nuclear Fuel: : sales geographysales geography
PaksPaks NPPNPP
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RKRK--22 typetype
20% decrease of number of 20% decrease of number of FA in reload batchFA in reload batch
Cost cutting for Cost cutting for spent fuel handlingspent fuel handling
Enhanced Enhanced parameters of parameters of
nuclear safety for nuclear safety for fresh Ufresh U--Gd fuel Gd fuel
handling handling
possibility of possibility of withdrawing of failed withdrawing of failed pin (with necessary pin (with necessary
equipment)equipment)
10% decrease of 10% decrease of natural uranium rate natural uranium rate
consumptionconsumption
Advantages of 2Advantages of 2ndnd generation of VVERgeneration of VVER‐‐440 FA440 FA
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Substantiation and ImplementationSubstantiation and Implementation of VVERof VVER‐‐440440 FAFA
UnitUnit 1: 1: Implementation of Implementation of FAFA with with chatterchatter--resistant design resistant design ((since since 20020099))
UnitUnit 2: 2: Commercial operation of FA with Commercial operation of FA with chatterchatter--resistant design (since 2008)resistant design (since 2008)
UnitUnit 3: 3: Commercial operation of FA and Commercial operation of FA and followers of 2followers of 2ndnd generation generation ((since since 2008)2008)
Kola NPPKola NPP
UnitUnit 44: : Commercial operation of FA and Commercial operation of FA and followers of 2followers of 2ndnd generation generation ((since since 2008)2008)
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Power upratePower uprate
Implementation oImplementation of f VVERVVER‐‐440 Nuclear Fuel440 Nuclear Fuel
DukovanyDukovany105%105% Implementation of Implementation of 2nd 2nd generation ofgeneration of FAFA
BoguniceBogunice107%107%
MohovceMohovce107%107%
PaksPaks108%108% Substantiation of nuclear fuel operation Substantiation of nuclear fuel operation
in in ““load followload follow”” modesmodesRivneRivne
108% (108% (plannedplanned))
LoviisaLoviisa110%110%
Development of demountable follower Development of demountable follower designdesign
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Next step forward: 3Next step forward: 3rdrd generation of VVERgeneration of VVER‐‐440 FA440 FADevelopment of the 3Development of the 3rdrd generation of FA is based on operation generation of FA is based on operation experience of 2experience of 2ndnd generation of FA and results derived from generation of FA and results derived from development of FA for VVERdevelopment of FA for VVER--440, TVSA type and TVS440, TVSA type and TVS--2 type for 2 type for VVERVVER--10001000. . The waterThe water--uranium ratio was significantly improved due to use of uranium ratio was significantly improved due to use of angle bars in combination with water tubes and increasing of fueangle bars in combination with water tubes and increasing of fuel l rod lattice pitch up to 1rod lattice pitch up to 122..6 6 mmmm. . Fuel cycle:Fuel cycle: 66--yearsyears..Expected result of 3Expected result of 3rdrd generation implementation generation implementation –– more effective more effective fuel utilization (up to 10%)fuel utilization (up to 10%)..Project designProject design was issued in was issued in 2007.2007.Supply of pilot batch of 3Supply of pilot batch of 3rdrd generation FA for test operation generation FA for test operation –– 2010.2010.
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up to 4.87up to 4.874.254.25 // 4.384.383.823.823.603.60Average reload Average reload batch enrichment, batch enrichment,
w/o Uw/o U235235
FA of the 2nd / FA of the 2nd / 3rd generation, 3rd generation, with wrapperwith wrapper
FA of the 2nd FA of the 2nd generation, generation, with wrapperwith wrapper
Conventional Conventional FA with FA with wrapperwrapper
Conventional Conventional FA with FA with wrapperwrapper
FA TypeFA Type
Shaped, UShaped, U‐‐GdGdShaped, UShaped, U‐‐GdGdShapedShapedNonNon‐‐shapedshapedType of fuel rod Type of fuel rod bundlebundle
before 1997before 1997 19981998––20022002 20032003––20102010 20102010……
Number of FA in Number of FA in reload batchreload batch 105105 8484 6666 6060
BurnBurn‐‐upup, , GWGW××dd/tHM/tHM 3636 4545 5757 6565
Fuel cycleFuel cycle 33‐‐yearyear 44‐‐yearyear 55‐‐yearyear 66‐‐yearyear
Natural Uranium Natural Uranium consumption,consumption,tHM/GWtHM/GW××dd
0.2560.256 0.2090.209 0.1840.184 0.1800.180
Development of VVERDevelopment of VVER‐‐440 Nuclear Fuel440 Nuclear Fuel
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d
Zaporozhzhya NPP
Khmelnytska NPP
Rivne NPP
South‐Ukraine NPP
Kudankulam NPP
Busher NPP
Tyanvan NPP
Kozloduy NPP
Rostov NPP, unit 2
Balakovo NPP
Kalinin NPP
Novovoronezh NPP
Rostov NPP, unit 1
Temelin NPP
VVERVVER‐‐1000 Nuclear Fuel1000 Nuclear Fuel: : sales geographysales geography
Number of units Number of units ((operatingoperating / / under under construction)construction)
2288 / / 44
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1.1. Casing constructionCasing construction2.2. UU--Gd fuel, average assembly enrichment Gd fuel, average assembly enrichment –– 4,34,3 w/ow/o 235235UU3.3. Fuel cycleFuel cycle 44××300 300 EFPDEFPD
VVERVVER‐‐10010000 Nuclear Fuel for NovovoronezhNuclear Fuel for Novovoronezh‐‐55
Fabrication of FA using Fabrication of FA using unified parts since unified parts since 20102010
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3. 3. Provided featuresProvided featuresenhanced burnenhanced burn‐‐upupenhanced FA lifeenhanced FA life‐‐time up to time up to 6 6 yearsyearsimproved reliabilityimproved reliabilitynew generation of fuel rodnew generation of fuel rodload follow modeload follow modesafe performance under power uprate conditions safe performance under power uprate conditions
(Nnom=107%)(Nnom=107%)
1.1. Stable geometric Stable geometric behaviourbehaviour2.2. FailFail--safe operation of RCCAsafe operation of RCCA
TVSATVSA TVSTVS‐‐22
VVERVVER‐‐1001000 Nuclear Fuel for0 Nuclear Fuel for ВВ‐‐320, В320, В‐‐338338,, ВВ‐‐302302New generation of FANew generation of FA
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TVSTVS‐‐22
Kalinin NPPKalinin NPP::TVSATVSA sincesince 19981998 Balakovo NPPBalakovo NPP::
TVSTVS‐‐2 2 sincesince 20032003Ukrainian NPPUkrainian NPP::TVSATVSA sincesince 20032003
Kozloduy NPPKozloduy NPP::TVSA since TVSA since 20042004
TVSATVSA
Fuel cycle 4Fuel cycle 4××12, average assembly burn12, average assembly burn‐‐up up 55 55 GWGW××dd//tHMtHMStable geometry during operation Stable geometry during operation ((bowing less than bowing less than 77mmmm))No frettingNo fretting‐‐wear during operationwear during operationOnOn‐‐site repairable dsite repairable demountableemountable ddesignesign
Rostov NPPRostov NPP::TVSTVS‐‐2 2 sincesince 20082008
VVERVVER‐‐1001000 Nuclear Fuel Today0 Nuclear Fuel Today
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Main featuresMain featuresfuel stack is increased onfuel stack is increased on 150150 mmmmUOUO22 mass mass –– 552424..11 kgkg1212 spacer gridsspacer gridsantivibration gridantivibration grid3 3 mixing gridsmixing grids –– sincesince 20102010antianti--debris filter debris filter ((restrain particles more than 2 mm restrain particles more than 2 mm
sizesize) ) –– since since 2010 2010
TendenciesTendenciesincreasedincreased uraniumuranium capacitycapacityimproved heat reliabilityimproved heat reliabilityenhanced operational safetyenhanced operational safety
In operation at BalakovoIn operation at Balakovo--11 sincesince 20062006
VVERVVER‐‐1001000 Nuclear Fuel Development:0 Nuclear Fuel Development: TVSTVS‐‐22ММ
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Operation at KalininOperation at Kalinin--2, Kalinin2, Kalinin--3 is planned since3 is planned since 20102010
TendenciesTendenciesincreasedincreased uraniumuranium capacitycapacityimproved heat reliabilityimproved heat reliabilityenhanced operational safetyenhanced operational safety
Main featuresMain featuresfuel stack is increased onfuel stack is increased on 150150 mmmmUOUO22 mass mass –– 552424..11 kgkg115 spacer grids5 spacer gridsantivibration gridantivibration gridantianti--debris filter debris filter ((restrain particles more than 2 mm restrain particles more than 2 mm
sizesize))
VVERVVER‐‐1001000 Nuclear Fuel Development:0 Nuclear Fuel Development: TVSATVSA‐‐PLUSPLUS
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Antivibration gridAntivibration grid
AntiAnti--debris debris filterfilter
In operation at KalininIn operation at Kalinin--1 since 20061 since 2006
TendenciesTendenciesincreasedincreased uraniumuranium capacitycapacityimproved heat reliabilityimproved heat reliabilityenhanced operational safetyenhanced operational safety
Main featuresMain featuressolid pellet 7.8/solid pellet 7.8/00mmmmUOUO22 mass mass –– 55446 kg6 kg8 spacer grids8 spacer gridsantivibration gridantivibration grid3 3 mixing gridsmixing grids –– sincesince 20102010antianti--debris filter debris filter ((restrain particles more restrain particles more
than 2 mm sizethan 2 mm size) ) –– since since 2010 2010
VVERVVER‐‐1001000 Nuclear Fuel Development:0 Nuclear Fuel Development: TVSATVSA‐‐ALFAALFA
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Current Current valuevalue
Advanced Advanced valuevalue
Cladding thicknessCladding thickness, , mmmm 00..6565 00..5757
Pellet diameterPellet diameter, , mmmm 77..57/757/7..6060 77..8080
Central holeCentral hole, , mmmm 11..4 / 14 / 1..22 00
Average grain sizeAverage grain size, , μμmm 1010 2525
Design features providing VVER fuel rod service life timeDesign features providing VVER fuel rod service life time: : ZrZr spongesponge sincesince 20092009Advanced fuel pellets Advanced fuel pellets Optimized E110Optimized E110
L=L=3530 +150 3530 +150 mmmm
L=L=3530 +200 3530 +200 mmmm
VVERVVER‐‐1001000 Nuclear Fuel0 Nuclear Fuel: : Advanced Fuel RodsAdvanced Fuel Rods
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sincesince 20032003 AdvancedAdvancedCycle length, Cycle length, EFPDEFPD 44××331010 33××515100 55××310310Reload batchReload batch, , pcspcs 4242 6666 3636Assembly burnAssembly burn--up, GWup, GW··dd//tHMtHM 5555 6060 up to 6up to 688
KalininKalinin‐‐11
Balakovo NPPBalakovo NPPRostov NPPRostov NPP
TVSTVS--22ММsince since 20082008
TVSATVSA--ALFAALFAsincesince 20020088
Fuel cycle Fuel cycle 33××1818
Fuel cycle Fuel cycle 55××12 12
KalininKalinin‐‐2, Kalinin2, Kalinin‐‐33
TVSATVSA--PLUSPLUSsince since 20201010 Fuel cycleFuel cycle 33××1818
Fuel Cycles: UprateFuel Cycles: Upratedd PowerPower ((104% 104% NNnomnom))
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ParameterParameter ValueValueOuter/ inner pellet diameterOuter/ inner pellet diameter, , mmmm 77..66 // 11..22Outer / inner cladding diameterOuter / inner cladding diameter, , mmmm 99..11 // 77..7373Increased fuel stack heightIncreased fuel stack height, , mmmm 36803680Spacer gridsSpacer grids, , pcspcs 88Mixing gridsMixing grids, , pcspcs 66Reference fuel cycleReference fuel cycle, , EFPDEFPD 55××320320Lead rod burnLead rod burn--upup, , GWGW··dd//tHMtHM up toup to 7272AntiAnti--debris filterdebris filter yesyes
Design of TVSADesign of TVSA--T is based on TVSAT is based on TVSA--ALFA designALFA designFirst full core loading at Temelin NPP First full core loading at Temelin NPP –– in in 20102010
VVERVVER‐‐1001000 Nuclear Fuel0 Nuclear Fuel: : TVSATVSA‐‐TT for Temelin NPPfor Temelin NPP
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before before 19971997
19981998––20102010
sincesince19981998
sincesince20032003
sincesince20062006
sincesince20062006
sincesince20102010
FA typeFA type TVSTVS,,TVSTVS--MM
UTVSUTVS TVSATVSA TVSTVS--22 TVSATVSA--ALFAALFA
TVSTVS--2M2M TVSATVSA--PLUSPLUS
Type of BAType of BA –– UU--GdGd UU--GdGd UU--GdGd UU--GdGd UU--GdGd UU--GdGd
Average Average enrichment of enrichment of reload batchreload batch, , w/ow/o
44..3131 33..7777 up toup to 44..44 44..2626 44..8383 44..8888 4.884.88
Reload batchReload batch, , pcspcs 5454 4848 4242 5454 3636 60 60 –– 6666 60 60 –– 6666
Outer fuel rod Outer fuel rod diameterdiameter, , mmmm 77..57 / 2,357 / 2,3 77..57 / 157 / 1..55 77..57 / 1,457 / 1,4 77..57 / 157 / 1..44 77..8 / 08 / 0..00 77..6 / 16 / 1..22 77..6 / 16 / 1..22
Assembly burnAssembly burn--upup, , GWGW××dd//tHMtHM 4949 4949 5555 5555 додо 6868 додо 6868 додо 6868
Fuel cycleFuel cycle 33××11 33××11 44××(310(310––320)320)
3 3 ××(350(350––370)370)
5 5 ××(310(310––320)320)
3 3 ××(480(480––510)510)
3 3 ××(480(480––510)510)
Uranium Uranium consumptionconsumption, , tHM/GWtHM/GW××dd
00..240240 00..205205 00..199199 00..210210 00..187187 00..230230 00..230230
Development of VVERDevelopment of VVER‐‐1001000 Nuclear Fuel0 Nuclear Fuel
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VVERVVER--1000 1000 nuclear fuel provides load follow modesnuclear fuel provides load follow modes
Primary load follow Primary load follow within the range of within the range of ±± 2 % 2 % NNnomnom
Power maneuvering Power maneuvering 100100––7575––100 % 100 % NNelel
raterate up to up to 1% 1% NNnomnom//minmin200 200 cycles through operating periodcycles through operating period
60
70
80
90
100
110
4 0 6 12 18 24
VVERVVER‐‐1001000 Nuclear Fuel0 Nuclear Fuel: : Load FollowLoad Follow
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R&D, FA based on TVS-2M design:
Enhanced uranium capacity due to increased fuel stack height and advanced fuel rod design (cladding 9.1 / 7.93 mm, pellet 7.8 / 0.0 mm)
Improved heat reliability at uprated power
Modified Zr alloys
AES-2006 Technical Assignment Requirements
Thermal power – 3200 MW(Тinlet=298.8 °С, mass steam quality up to 13 %)
Fuel cycles 5×12 and 3×18, maximum assembly burn-up up to 70 GW·d/tHM
Load Follow Operation – during 90% of operation time within the range 100-20-100 % Nnom and rate of change 5% Nnom/min
AESAES‐‐2006 Nuclear Fuel2006 Nuclear FuelDevelopment StepDevelopment Step‐‐byby‐‐Step Step (1)(1)
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Phase #1 (2007 – 2009)
Base FA design development:
- Thermal PowerThermal Power: : 3200 3200 MWMW-- Increased fuel stack heightIncreased fuel stack height ((pelletpellet 7.67.6 /1.2 /1.2 mmmm, , grain grain
sizesize 25 25 µµmm))-- Average assembly burnAverage assembly burn--up up :: 64 64 GWGW··dd//tHMtHM-- Load Follow Load Follow 100100--7575--100 % 100 % NNnomnom
-- Mixing gridsMixing grids
AESAES‐‐2006 Nuclear Fuel2006 Nuclear FuelDevelopment StepDevelopment Step‐‐byby‐‐Step Step ((22))
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Phase #1 Results2. Fuel Cycles
Fuel Cycle, EFPD 5×310 3×510Reload batch, pcs 36 72
Average enrichment of reload batch, w/o 235 U 4.83 4.69
Discharge burn-up, GW·d/tHMAverage assembly burn-upLead rod burn-up
58.464.2
48.357.0
AESAES‐‐2006 Nuclear Fuel2006 Nuclear FuelDevelopment StepDevelopment Step‐‐byby‐‐Step Step ((33))
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CONCLUSIONSCONCLUSIONS
VVERVVER--440 Nuclear Fuel440 Nuclear Fuel
Implementation of 2Implementation of 2ndnd generation of FA with the generation of FA with the following performance characteristicsfollowing performance characteristics::-- Average FP failure factor during operation is less than Average FP failure factor during operation is less than 11··1010--66; ;
-- Fuel burnFuel burn--upup: : up to up to 60 60 GW×dGW×d//tHMtHM;;
-- 55--year fuel cycleyear fuel cycle;;
-- Unit thermal power uprate up to Unit thermal power uprate up to 110% 110% NNnomnom;;
-- Load Follow ModeLoad Follow Mode (97,5(97,5±±2,5%2,5% andand 100100--7575--100% 100% NNnomnom))
33rdrd generation of FA is developed (RKgeneration of FA is developed (RK--3 Type)3 Type)
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VVERVVER--10001000 Nuclear FuelNuclear Fuel
1)1) New generation of FA (TVSA and TVSNew generation of FA (TVSA and TVS--2) is developed, 2) is developed, implemented and successfully operated at Russian, Ukrainian and implemented and successfully operated at Russian, Ukrainian and Bulgarian NPPs providingBulgarian NPPs providingSafe and reliable operation cycle of Safe and reliable operation cycle of 66 yearsyearsAssembly burnAssembly burn--up up – up to up to 60 60 GWGW××dd//tHMtHMLoad Follow ModeLoad Follow Mode
2)2) For satisfaction of customer needs regarding nuclear fuel For satisfaction of customer needs regarding nuclear fuel performance the following development of FA design is under performance the following development of FA design is under wayway::Power uprate up to Power uprate up to 104%104% NNnomnom;;Fuel cycles length up toFuel cycles length up to 18 18 monthsmonths
CONCLUSIONSCONCLUSIONS
8th International Conference on VVER Fuel Performance, Modeling and Experimental Support 27.09–02.10.2009, Helena Resort, Bulgaria 27
Thank you for your attentionThank you for your attention