Transition cycle analysis of light water-cooled SMR core loaded with MOX (TRU) and FCM (TRU) fueled PWR assemblies

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초록

In this study, a light water-cooled small modular reactor (SMR) core loaded with special fuel assemblies composed of mixed oxide (MOX) fuel rods using UO2-TRUO2 and fully ceramic micro-encapsulated (FCM) fuel rods using TRUO2 was suggested and analyzed for transuranic (TRU) transmutation as an alternative option before the commercialization of sodium-cooled fast reactor (SFR). Especially, the FCM rods were loaded with only TRUO2 for deep burning of TRU. This study performed neutronic analysis of the transition cycle cores with the new fuel assemblies. In addition to the neutronic analysis, detailed analyses on two important issues for the light water-cooled reactor (LWR) core loaded with TRU were performed in fuel assembly level calculation. First, an effective burnable absorber design was searched to mitigate the degradation in effectiveness of the burnable absorber caused by the hardened neutron spectrum. Secondly, a reactivity decomposition analysis was performed for understanding quantitative nuclide-wise and reaction-wise contributions to the void reactivity which is a key safety parameter of TRU-bearing fuel assemblies. The analysis on the TRU mass flow through the transition cycles showed that a high net TRU consumption rate of 14.7% can be achieved at the equilibrium cycle.

키워드

Light water-cooled SMRMOX-FCM fuel assemblyNet TRU consumption rateReactivity decompositionTRU transmutationCooling waterFuelsOxide mineralsPressurized water reactorsSmall nuclear reactorsSodium-cooled fast reactorsUranium dioxideBurnable absorberConsumption ratesDecomposition analysisEquilibrium cycleNeutronic analysisSafety parametersSmall modular reactorsSodium cooled fast reactors (SFR)Light water reactors
제목
Transition cycle analysis of light water-cooled SMR core loaded with MOX (TRU) and FCM (TRU) fueled PWR assemblies
저자
Hwang,Dae HeeHong, Ser Gi
DOI
10.1016/j.nucengdes.2021.111103
발행일
2021-04
유형
Article
저널명
Nuclear Engineering and Design
375
페이지
1 ~ 13