Micro Heteregeneous Approaches for the Insertion of Reprocessed and Combined Thorium Fuel Cycles in a PWR System

Monteiro, Fabiana B. A.; Castro, Victor; Faria, Rochkhudson B. de; Fortini, Ângela; Silva, Clarysson A. M. da; Pereira, Cláubia

doi:10.1557/opl.2016.34

Cited by 3 publications

(3 citation statements)

References 3 publications

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“…Such a policy was also adopted by other European countries and by Japan [2]. Another kinds of mixed fuels have been investigating e.g., oxides of thorium/uranium, thorium/plutonium, thorium/transuranic, and transuranic/uranium [1,[3][4][5][6]. Recently, researchers have been turning their attention to Th fuel cycle in PWRs aiming at reducing the generation of minor actinides, at improving the nuclear power sustainability, and at better fuel utilization and breeding [7][8][9].…”

Section: Introductionmentioning

confidence: 99%

Heat transfer in a simulated spent fuel pool for different types of spent fuels

Faria¹,

Godino²,

Corzo³

et al. 2023

Braz. J. Develop.

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Historically, the Spent Fuel Pool (SFP) of Angra II, from Brazil, has received standard spent fuel (SF) assemblies of uranium dioxide (UO2) discharged from Pressurized Water Reactors (PWR) of the Nuclear Power Plants (NPP) of Angra. However, in case of using Mixed Oxide (MOX) or thorium-based fuels at a proportion of 1/3 or 1/4 of the total of fuel assemblies in their PWRs as it has been occurring worldwide, it would require further thermal studies of wet storage of the new mixed SF generated. It includes the determination of the water boiling time (Tb) of the SFP in case of breakdown of its external cooling system (ECS). This work presents studies of Tb of a simulated SFP storing mixed SF discharged from PWRs. The types of mixed SF studied include MOX plus UO2, oxide of thorium/uranium (U-Th)O2 plus UO2, and oxide of thorium/transuranic (TRU-Th)O2 plus UO2. All the mixed SF was considered to contain 1/3 or 1/4 of either thorium-based fuels or reprocessed fuel. The simulations were implemented in CFX Ansys and OpenFOAM© codes. Tb from simulations with Ansys ranged from 4.05 h to 5.97 h, and from 3.45 h to 5.77 h from simulations with OpenFOAM©. Results show that, independent of the mixed loading pattern of the SFP, the water would reach the saturation temperature more rapidly when (TRU-Th)O2 was present. By contrast, when MOX was present, Tb was greater.

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Section: Introductionmentioning

confidence: 99%

Heat transfer in a simulated spent fuel pool for different types of spent fuels

Faria¹,

Godino²,

Corzo³

et al. 2023

Braz. J. Develop.

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“…Based on the idea of using reprocessed nuclear fuels in conjunction with UO2 in a PWR [2][3][4], this work evaluates the water boiling time in the ECS collapse scenario. UO2, (TRU-Th)O2, (U-Th)O2, and MOX spent fuels were assumed discharged from PWR.…”

Section: Introductionmentioning

confidence: 99%

Water boiling time in a spent fuel pool with adiabatic and non-adiabatic boundary conditions

Faria¹,

Godino²,

Corzo³

et al. 2022

BJDV

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The Spent Fuel Pool (SFP) of Angra II, from Brazil, has received standard spent fuel (SF) assemblies of Uranium dioxide (UO2) discharged from Pressurized Water Reactors (PWR) of the Nuclear Power Plants (NPP) of Angra since the beginning of its operation. However, in case of using Mixed Oxide (MOX) or Thorium-based fuels, it would require further thermal studies of wet storage. It includes the determination of the water boiling time (Tb) of the SFP in case of breakdown of its external cooling system (ECS). This work presents studies of Tb of a simulated SFP storing mixed SF discharged from PWRs. The types of mixed SF studied include MOX plus UO2, oxide of thorium/uranium (U-Th)O2 plus UO2, and oxide of Thorium/transuranic (TRU-Th)O2 plus UO2. The simulations were implemented in CFX Ansys considering the top of the SFP as either adiabatic or non-adiabatic wall. Tb is considerably higher when the non-adiabatic boundary condition is used.

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“…In addition to MOX recycle, other non-proliferating reprocessing fuels such as Th-Pu, Th-U e Th-TRU(transuranic) has also been studied [7].…”

Section: Introductionmentioning

confidence: 99%

Criticality safety analysis of spent fuel pool for a PWR using UO2, MOX, (Th-U)O2 and (TRU-Th)O2 fuels

et al. 2019

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A spent fuel pool of a typical Pressurized Water Reactor (PWR) was evaluated for criticality studies when it uses reprocessed fuels. PWR nuclear fuel assemblies with four types of fuels were considered: standard PWR fuel, MOX fuel, thorium-uranium fuel and reprocessed transuranic fuel spiked with thorium. The MOX and UO2 benchmark model was evaluated using SCALE 6.0 code with KENO-V transport code and then, adopted as a reference for other fuels compositions. The four fuel assemblies were submitted to irradiation at normal operation conditions. The burnup calculations were obtained using the TRITON sequence in the SCALE 6.0 code package. The fuel assemblies modeled use a benchmark 17x17 PWR fuel assembly dimensions. After irradiation, the fuels were inserted in the pool. The criticality safety limits were performed using the KENO-V transport code in the CSAS5 sequence. It was shown that mixing a quarter of reprocessed fuel withUO2 fuel in the pool, it would not need to be resized

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Micro Heteregeneous Approaches for the Insertion of Reprocessed and Combined Thorium Fuel Cycles in a PWR System

Cited by 3 publications

References 3 publications

Heat transfer in a simulated spent fuel pool for different types of spent fuels

Heat transfer in a simulated spent fuel pool for different types of spent fuels

Water boiling time in a spent fuel pool with adiabatic and non-adiabatic boundary conditions

Criticality safety analysis of spent fuel pool for a PWR using UO2, MOX, (Th-U)O2 and (TRU-Th)O2 fuels

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