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Session 4b: Designs under development (non-water-cooled Gen IV and SMRs)
Sodium Cooled Fast Reactor
HidekiKAMIDE,SodiumFastReactor“Interna;onalWorkshoponAdvancedReactorSystemsandFutureEnergyMarketNeeds”(Apr.12,2017OECDConferenceCentre,Paris,France) 1
HidekiKamide
Japan Atomic Energy Agency
Features of SFR System • FastNeutron:ü Neutronenergyishighü Neutronyieldperabsorp;on(fission)isgreaterthan2.0
ü U-238+n→Pu-239ü Effec;veUseofU/Pu
• SodiumCoolant:ü Lessneutronmodera;onü HighTemp.(around550℃)highthermalefficiencyStructuralDesignguidelineü NoPressuriza;onü Compa;blewithStructural
Materialsü Sodium-WaterReac;on
HidekiKAMIDE,SodiumFastReactor“Interna;onalWorkshoponAdvancedReactorSystemsandFutureEnergyMarketNeeds”(Apr.12,2017OECDConferenceCentre,Paris,France) 2
10-310-210-1100101102103104 105106 107
Neu
tron
flux
Neutronenergy(eV)
LWR FBRFissionarea(235U)
Fissionarea(239Pu)
Fig.1
HidekiKAMIDE,SodiumFastReactor“Interna;onalWorkshoponAdvancedReactorSystemsandFutureEnergyMarketNeeds”(Apr.12,2017OECDConferenceCentre,Paris,France) 3
SFR Development in the world
HidekiKAMIDE,SodiumFastReactor“Interna;onalWorkshoponAdvancedReactorSystemsandFutureEnergyMarketNeeds”(Apr.12,2017OECDConferenceCentre,Paris,France) 4
0
0.2
0.4
0.6
0.8
1
LWRSF
volumedecreases
toone-seventh
VolumeofHLW
perunitp
ower
gene
ra;o
n(rela;
vevalue
)
LWRReprocessing
(Vitrifiedwaste)
FRReprocessing
(Vitrifiedwaste)
Fuel Cycle (Pu/Minor Actinide recycling) p Effec;veUseofU(Puu;liza;on)p Reduc;onofEnvironmentalBurden
• ReprocessingrecoveringUandPufromspentfuelreducesthevolumeofHLW(Fig.1)
• MinorAc;niderecyclingreducestheradiotoxicityofHLW(Fig.2)
Fig.1 Fig.2
Safety Design Requirement considering FR features
HidekiKAMIDE,SodiumFastReactor“Interna;onalWorkshoponAdvancedReactorSystemsandFutureEnergyMarketNeeds”(Apr.12,2017OECDConferenceCentre,Paris,France) 5
SDC
SDG
SafetyFundamentals
SafetyRequirements Targetsof
globalstandards
Domes;cCodesandStandards
DesignguidesoftheReactorCoolantSystemandAssociatedSystemsinNuclearPowerPlants
<HierarchyofSafetyStandards>
Aimingfor“Eliminateoftheneedofoff-siteemergency”
Preven;onofCoreDamage
Mi;ga;onofCoreDamage
ResidualRisk
DesignBasisAccidents
Preven;onSitua;ons
Mi;ga;onSitua;ons
Situa;onscoveredbyPrac;calElimina;onDemonstra;on
DesignExtensionCondi;ons
JAEA’s FR cycle R&D facilities
HidekiKAMIDE,SodiumFastReactor“Interna;onalWorkshoponAdvancedReactorSystemsandFutureEnergyMarketNeeds”(Apr.12,2017OECDConferenceCentre,Paris,France) 6
Reprocessing
Fuel Fabrication
FR
Monju
Joyo
AGF
Pu-3
CPF
FMF
（MA：Minor Actinide）
AtheNa facility
Fuel Fabrication: l Remote MA-bearing MOX fuel
fabrication technology l Determination of fuel composition range
applicable
Fuel Development & Irradiation Test: l Systematic irradiation tests
of MA-bearing MOX fuel, High Pu-contents MOX fuel
Reactor Characteristics & Reactor system: l Feasibility confirmation of FR plant
technologies l Acquisition of characteristics of MA-
containing core
Reprocessing: l Development of MA
partitioning process and performance evaluation
l Establishment of feasible process concepts
Spent MOX fuel
U, Pu, MA
MA-bearing new MOX fuel
(AdvancedTechnologyExperimentSodium(Na)Facility)
Sodium Test : l Demonstration of Large
Sodium Component
Market Issue
HidekiKAMIDE,SodiumFastReactor“Interna;onalWorkshoponAdvancedReactorSystemsandFutureEnergyMarketNeeds”(Apr.12,2017OECDConferenceCentre,Paris,France) 7
ü DefineGenIVSystemR&Dac?vi?es:ACrac?vedesignsfordeploymentinaenergymarketenvironment(2040-50)
• Sustainability(Wasteburden,effec?vefueluse,GlobalWarming)
• Economics(CostsofConstruc?on/Opera?on&Maintenance/FuelCycle,FinancialRisk)
• PublicAcceptance(SafetyandEnvironment)ü Increasetheopportunity;Load-Following,Harmonizingwith
fluctua?ngpowerofrenewableenergyandasmart-grid,SmallModularReactor,Non-electricapplica?on,
ü Crosscu^ngIssues:Materials,SafetyStandard&Guideline,Educa?on&Training
