Burn-up characteristics of ADS system utilizing the fuel composition from MOX PWRs spent fuel
Burn-up characteristics of accelerator-driven system, ADS has been evaluated utilizing the fuel composition from MOX PWRs spent fuel. The system consists of a high intensity proton beam accelerator, spallation target, and sub-critical reactor core. The liquid lead–bismuth, Pb–Bi, as spallation targe...
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Published in | Annals of nuclear energy Vol. 29; no. 18; pp. 2173 - 2186 |
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Main Authors | , , , , , , |
Format | Journal Article |
Language | English |
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Elsevier Ltd
01.12.2002
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Abstract | Burn-up characteristics of accelerator-driven system, ADS has been evaluated utilizing the fuel composition from MOX PWRs spent fuel. The system consists of a high intensity proton beam accelerator, spallation target, and sub-critical reactor core. The liquid lead–bismuth, Pb–Bi, as spallation target, was put in the center of the core region. The general approach was conducted throughout the nitride fuel that allows the utilities to choose the strategy for destroying or minimizing the most dangerous high level wastes in a fast neutron spectrum. The fuel introduced surrounding the target region was the same with the composition of MOX from 33 GWd/t PWRs spent-fuel with 5 year cooling and has been compared with the fuel composition from 45 and 60 GWd/t PWRs spent-fuel with the same cooling time. The basic characteristics of the system such as burn-up reactivity swing, power density, neutron fluxes distribution, and nuclides densities were obtained from the results of the neutronics and burn-up analyses using ATRAS computer code of the Japan Atomic Energy research Institute, JAERI. |
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AbstractList | Burn-up characteristics of accelerator-driven system, ADS has been evaluated utilizing the fuel composition from MOX PWRs spent fuel. The system consists of a high intensity proton beam accelerator, spallation target, and sub-critical reactor core. The liquid lead–bismuth, Pb–Bi, as spallation target, was put in the center of the core region. The general approach was conducted throughout the nitride fuel that allows the utilities to choose the strategy for destroying or minimizing the most dangerous high level wastes in a fast neutron spectrum. The fuel introduced surrounding the target region was the same with the composition of MOX from 33 GWd/t PWRs spent-fuel with 5 year cooling and has been compared with the fuel composition from 45 and 60 GWd/t PWRs spent-fuel with the same cooling time. The basic characteristics of the system such as burn-up reactivity swing, power density, neutron fluxes distribution, and nuclides densities were obtained from the results of the neutronics and burn-up analyses using ATRAS computer code of the Japan Atomic Energy research Institute, JAERI. Burn-up characteristics of accelerator-driven system, ADS has been evaluated utilizing the fuel composition from MOX PWRs spent fuel. The system consists of a high intensity proton beam accelerator, spallation target, and sub-critical reactor core. The liquid lead-bismuth, Pb-Bi, as spallation target, was put in the center of the core region. The general approach was conducted throughout the nitride fuel that allows the utilities to choose the strategy for destroying or minimizing the most dangerous high level wastes in a fast neutron spectrum. The fuel introduced surrounding the target region was the same with the composition of MOX from 33 GWd/t PWRs spent-fuel with 5 year cooling and has been compared with the fuel composition from 45 and 60 GWd/t PWRs spent-fuel with the same cooling time. The basic characteristics of the system such as burn-up reactivity swing, power density, neutron fluxes distribution, and nuclides densities were obtained from the results of the neutronics and burn-up analyses using ATRAS computer code of the Japan Atomic Energy research Institute, JAERI. copyright 2002 Elsevier Science Ltd. All rights reserved. |
Author | Lasman, A.S. Marsongkohadi Su'ud, Z. Tsujimoto, K. Osugi, T. Marsodi Nishihara, K. |
Author_xml | – sequence: 1 surname: Marsodi fullname: Marsodi email: marsodi@batan.go.id organization: P2TIK-BATAN, National Nuclear Energy Agency of Indonesia, Puspiptek-, Serpong, 15310, Indonesia – sequence: 2 givenname: A.S. surname: Lasman fullname: Lasman, A.S. organization: P2TIK-BATAN, National Nuclear Energy Agency of Indonesia, Puspiptek-, Serpong, 15310, Indonesia – sequence: 3 givenname: K. surname: Nishihara fullname: Nishihara, K. email: nishi@omega.tokai.jaeri.go.jp organization: Transmutation Group, Department of Nuclear Energy System, Japan Atomic Energy Research Institute, JAERI, Tokai-mura, 319-1159, Japan – sequence: 4 givenname: T. surname: Osugi fullname: Osugi, T. organization: Transmutation Group, Department of Nuclear Energy System, Japan Atomic Energy Research Institute, JAERI, Tokai-mura, 319-1159, Japan – sequence: 5 givenname: K. surname: Tsujimoto fullname: Tsujimoto, K. organization: Transmutation Group, Department of Nuclear Energy System, Japan Atomic Energy Research Institute, JAERI, Tokai-mura, 319-1159, Japan – sequence: 6 surname: Marsongkohadi fullname: Marsongkohadi organization: Nuclear Reactor Research Group, Physics Department, Bandung Institute of Technology, ITB, Bandung, 40132, Indonesia – sequence: 7 givenname: Z. surname: Su'ud fullname: Su'ud, Z. email: szaki@fi.itb.ac.id organization: Nuclear Reactor Research Group, Physics Department, Bandung Institute of Technology, ITB, Bandung, 40132, Indonesia |
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References | Salvatores, Slessarev, Tchistiakov (BIB4) 1998; 130 Sasa, T., Tsujimoto, K., Takizuka, T., Takano, H., 1999. For Accelerator-Driven Transmutation Reactor Analyses Code System, ATRAS, JAERI Report (JAERI - Data/Code 99–007), JAERI, Japan. Mukaiyama, T. et al., 1990. Characteristics of MA transmutation in ABR and power reactor. In: Proceeding of the OECD/NEA Information Exchange Meeting on Actinide and Fission Product Separation and Transmutation, Mito, Japan, 6–8 November 1990, pp. 326–346. Takizuka, T., Tsujimoto, K., Sasa, T., Nishihara, K., Takano H., 2000. Design study of lead–bismuth cooled ADS dedicated to nuclear waste transmutation. The Second Fujihara International Seminar on Advanced Nuclear Energy Systems Toward Zero Release of Radioactive Wastes, S6–3, Shizuoka, Japan, 6–9 November 2000. Tsujimoto, K., Sasa, T., Takano, H., Takizuka, T., Mukaiyama, T., Hayano, M., Yokobori, H., Kamishima, Y., 1998. Conceptual study of the lead–bismuth cooled accelerator-driven system. Second International Topical Meeting on Nuclear Applications of Accelerator Technology, AccApp'98, Galtiburg, Tennessee, USA, 20–23 September, pp. 137–143. 10.1016/S0306-4549(02)00033-6_BIB3 10.1016/S0306-4549(02)00033-6_BIB6 10.1016/S0306-4549(02)00033-6_BIB5 Salvatores (10.1016/S0306-4549(02)00033-6_BIB4) 1998; 130 10.1016/S0306-4549(02)00033-6_BIB9 |
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Title | Burn-up characteristics of ADS system utilizing the fuel composition from MOX PWRs spent fuel |
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