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Neutronic Calculation Analysis for CN HCCB TBM-Set 被引量:3

Neutronic Calculation Analysis for CN HCCB TBM-Set
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摘要 Using the Monte Carlo transport code MCNP, neutronic calculation analysis for China helium cooled ceramic breeder test blanket module (CN HCCB TBM) and the associated shield block (together called TBM-set) has been carried out based on the latest design of HCCB TBM-set and C-lite model. Key nuclear responses of HCCB TBM-set, such as the neutron flux, tritium production rate, nuclear heating and radiation damage, have been obtained and discussed. These nuclear performance data can be used as the basic input data for other analyses of HCCB TBM-set, such as thermal-hydraulics~ thermal-mechanics and safety analysis. Using the Monte Carlo transport code MCNP, neutronic calculation analysis for China helium cooled ceramic breeder test blanket module (CN HCCB TBM) and the associated shield block (together called TBM-set) has been carried out based on the latest design of HCCB TBM-set and C-lite model. Key nuclear responses of HCCB TBM-set, such as the neutron flux, tritium production rate, nuclear heating and radiation damage, have been obtained and discussed. These nuclear performance data can be used as the basic input data for other analyses of HCCB TBM-set, such as thermal-hydraulics~ thermal-mechanics and safety analysis.
出处 《Plasma Science and Technology》 SCIE EI CAS CSCD 2015年第7期607-611,共5页 等离子体科学和技术(英文版)
基金 supported by the Major State Basic Research Development Program of China(973 Program)(No.2013GB108000)
关键词 MCNP HCCB TBM-set neutronic calculation nuclear performance MCNP, HCCB TBM-set, neutronic calculation, nuclear performance
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  • 1Giancarli L M, Abdou M, Campbell D J, et al. 2012, Fusion Engineering and Design, 87: 395.
  • 2Feng K M, Pan C H, Zhang G S, et al. 2012, Fusion Engineering and Design, 87: 1138.
  • 3Feng K M, Zhang G S, Hu G, et al. 2014, Fusion En?gineering and Design, 89: 1119.
  • 4X-5 Monte Carlo Team. 2003, MCNP-A General Monte Carlo N-Particle Transport Code, Version 5, Vol. II: Users Guide. La-CP-03-0245, Los Alamos Na?tional Laboratory.
  • 5Lopez Al-Dama D, Trkov A. 2004, FENDL-2.1: up?date of an evaluated nuclear data library for fusion applications, Report INDC(NDS)-46, IAEA, Vienna.
  • 6Marin A, Kim B Y, Bertolini C, et al. 2013, Fusion Engineering and Design, 88: 2791.
  • 7Kim B Y, Sabourin F, Merola M, et al. 2014, Fusion Engineering and Design, 89: 1969.
  • 8Chaudhuri P, Ranjithkumar S, Sharma D, et al. 2014, Fusion Engineering and Design, 89: 1362.
  • 9Commin L, Madeleine S, Dechelle C, et al. 2011, Fu?sion Engineering and Design, 86: 2143.
  • 10Pascal R, Beloglazov S, Bonagiri S, et al. 2012, Fusion Engineering and Design, 87: 1347.

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