Waste analysis generated by alternative reprocessing fuels from pressurised water reactions

Pereira, Cláubia; Leite, Euzimar M.; Faria, Eduardo Fernandes

doi:10.1016/s0306-4549(99)00102-4

Cited by 5 publications

(3 citation statements)

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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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“…Reactors such as VHTR, and its molten salt variant the LS-VHTR, HTTR and DB-MHR have been simulated. The reprocessed fuel used in all studies is based on the spent fuel type "C" coming from Angra-I nuclear plant, in Brazil, with 3.1% of initial enrichment, burnup to 33,000 MWd/THM simulated using the ORIGEN2.1 code (Croff, 1980), divided in three steps of 11,000 MWd/THM, with an average density power of 37.75 MW/THM and 5 years of cooling in pool (Cota and Pereira, 1997;Leite, 1998, 1999a,b;Pereira et al, 2000). The reprocessing technique used for each study is specified in each one.…”

Section: Introductionmentioning

confidence: 99%

Recent advances on the use of reprocessed fuels and combined thorium fuel cycles in HTR systems

Fortini

Monteiro

Scari

et al. 2015

Progress in Nuclear Energy

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“…Since nineties, the Departamento de Engenharia Nuclear (DEN) of Universidade Federal de Minas Gerais (UFMG) has been studying new fuels to PWR including the insertion of reprocessed fuels and thorium [5,6,7]. Some reprocessing techniques have been evaluated.…”

Section: Introductionmentioning

confidence: 99%

Assessment of the Insertion of Reprocessed Fuels and Combined Thorium Fuel Cycles in a PWR System

et al. 2015

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The insertion of reprocessed fuel spiked with thorium in a typical PWR fuel element considering (TRU-Th) cycle was simulated using different fissile materials that varied from 5.5% to 7.0%. The reprocessed fuels were obtained using the ORIGEN 2.1 code from a burned PWR standard fuel (33,000 MWd/tHM burned), with 3.1% of initial enrichment, which was remained in the cooling pool for five years and then reprocessed using UREX+ technique. The k inf , hardening spectrum and the fuel evolution during the burnup were evaluated. This study was performed using the SCALE 6.0

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Waste analysis generated by alternative reprocessing fuels from pressurised water reactions

Cited by 5 publications

References 0 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

Recent advances on the use of reprocessed fuels and combined thorium fuel cycles in HTR systems

Assessment of the Insertion of Reprocessed Fuels and Combined Thorium Fuel Cycles in a PWR System

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