Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system
A feasibility of reusing option of spent nuclear fuel in a fusion-fission hybrid system without partitioning was checked as an alternative option of pyro-processing with critical reactor system. Neutronic study was performed with MCNP 6.1 for this option, direct reuse of spent PWR fuel (DRUP). Vario...
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doaj-442f7a2b884743dda11b3d800f8b5d172020-11-25T00:40:32ZengElsevierNuclear Engineering and Technology1738-57332018-10-0150710601067Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid systemSeong Hee Hong0Myung Hyun Kim1Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do, 17104, South KoreaCorresponding author.; Department of Nuclear Engineering, Kyung Hee University, 1732 Deogyeong-daero, Giheung-gu, Yongin-si, Gyeonggi-do, 17104, South KoreaA feasibility of reusing option of spent nuclear fuel in a fusion-fission hybrid system without partitioning was checked as an alternative option of pyro-processing with critical reactor system. Neutronic study was performed with MCNP 6.1 for this option, direct reuse of spent PWR fuel (DRUP). Various options with DRUP fuel were compared with the reference design concept; transmutation purpose blanket with (U-TRU)Zr fuel loading connected with pyro-processing.Performance parameters to be compared are transmutation performance of transuranic (TRU) nuclides, required fusion power and tritium breeding ratio (TBR). When blanket part is loaded only with DRUP, initial keff level becomes too low to maintain a practical subcritical system, increasing the required fusion power. In this case, production rate of TRU nuclides exceeds the incineration rate.Design optimization is done for combining DRUP fuel with (U-TRU)Zr fuel. Reactivity swing is reduced to about 2447 pcm through fissile breeding compared to (U-TRU)Zr fuel option. Therefore, a required fusion power is reduced and tritium breeding performance is improved. However, transmutation performance with TRU nuclides especially 241Am is degraded because of softening effect of spectrum. It is known that partitioning and transmutation should be accompanied with fusion-fission hybrid system for the effective transmutation of TRU. Keywords: Fusion–fission hybrid system, Partitioning and transmutation, Direct reuse of spent PWR fuel, TRU transmutation, Tritium breeding ratiohttp://www.sciencedirect.com/science/article/pii/S1738573318300251 |
collection |
DOAJ |
language |
English |
format |
Article |
sources |
DOAJ |
author |
Seong Hee Hong Myung Hyun Kim |
spellingShingle |
Seong Hee Hong Myung Hyun Kim Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system Nuclear Engineering and Technology |
author_facet |
Seong Hee Hong Myung Hyun Kim |
author_sort |
Seong Hee Hong |
title |
Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system |
title_short |
Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system |
title_full |
Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system |
title_fullStr |
Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system |
title_full_unstemmed |
Neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system |
title_sort |
neutronic investigation of waste transmutation option without partitioning and transmutation in a fusion-fission hybrid system |
publisher |
Elsevier |
series |
Nuclear Engineering and Technology |
issn |
1738-5733 |
publishDate |
2018-10-01 |
description |
A feasibility of reusing option of spent nuclear fuel in a fusion-fission hybrid system without partitioning was checked as an alternative option of pyro-processing with critical reactor system. Neutronic study was performed with MCNP 6.1 for this option, direct reuse of spent PWR fuel (DRUP). Various options with DRUP fuel were compared with the reference design concept; transmutation purpose blanket with (U-TRU)Zr fuel loading connected with pyro-processing.Performance parameters to be compared are transmutation performance of transuranic (TRU) nuclides, required fusion power and tritium breeding ratio (TBR). When blanket part is loaded only with DRUP, initial keff level becomes too low to maintain a practical subcritical system, increasing the required fusion power. In this case, production rate of TRU nuclides exceeds the incineration rate.Design optimization is done for combining DRUP fuel with (U-TRU)Zr fuel. Reactivity swing is reduced to about 2447 pcm through fissile breeding compared to (U-TRU)Zr fuel option. Therefore, a required fusion power is reduced and tritium breeding performance is improved. However, transmutation performance with TRU nuclides especially 241Am is degraded because of softening effect of spectrum. It is known that partitioning and transmutation should be accompanied with fusion-fission hybrid system for the effective transmutation of TRU. Keywords: Fusion–fission hybrid system, Partitioning and transmutation, Direct reuse of spent PWR fuel, TRU transmutation, Tritium breeding ratio |
url |
http://www.sciencedirect.com/science/article/pii/S1738573318300251 |
work_keys_str_mv |
AT seongheehong neutronicinvestigationofwastetransmutationoptionwithoutpartitioningandtransmutationinafusionfissionhybridsystem AT myunghyunkim neutronicinvestigationofwastetransmutationoptionwithoutpartitioningandtransmutationinafusionfissionhybridsystem |
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