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Neutronic calculations for CANDU thorium systems using Monte Carlo techniques

Neutronic calculations for CANDU thorium systems using Monte Carlo techniques
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摘要 In this paper, we have investigated the prospects of exploiting the rich world thorium reserves using Canada Deuterium Uranium (CANDU) reactors. The analysis is performed using the Monte Carlo MCNP code in order to understand how much time the reactor is in criticality conduction. Four different fuel compositions have been selected for analysis. We have obtained the infinite multiplication factor, k∞, under full power operation of the reactor over 8 years. The neutronic flux distribution in the full core reactor has already been investigated. In this paper, we have investigated the prospects of exploiting the rich world thorium reserves using Canada Deuterium Uranium (CANDU) reactors. The analysis is performed using the Monte Carlo MCNP code in order to understand how much time the reactor is in criticality conduction. Four different fuel compositions have been selected for analysis. We have obtained the infinite multiplication factor, k∞, under full power operation of the reactor over 8 years. The neutronic flux distribution in the full core reactor has already been investigated.
机构地区 Department of Physics
出处 《Chinese Physics C》 SCIE CAS CSCD 2014年第8期111-115,共5页 中国物理C(英文版)
关键词 CANDU reactors thorium oxide plutonium oxide MCNP code CANDU reactors, thorium oxide, plutonium oxide, MCNP code
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参考文献15

  • 1:ahin S, :ahin H M, Acir A. Nuclear Engineering and Design, 2010, 240:2066 2074. 被引量:1
  • 2Sahin S, Acir A. Energy Conversion and Management, 2006, 47:1661 1675. 被引量:1
  • 3Sahin S, Yildiz K, Sahin H M, Sahin N, Acir A. Nuclear En:,i- neering and Design, 2006, 236(17): 178 -179. 被引量:1
  • 4Busse M. Optimization Of Thorium-Based Seed-Blanket l:ml Cycles For Nuclear Power Plants. M.S., Nuclear Engineering Instituto Balseiro, University of Cuyo, Argentina, 1995. 被引量:1
  • 5Canerl M, Dugan E T. Annals of Nuclear Energy, 2000, 2T: 759-770. 被引量:1
  • 6Chanyun L. Design and Neutronic Evaluation of Thorium Fuel in Pressurized Water Reactors. Master of Science Thesis Reac- tor Physics Department Royal Institute of Technology, Stock- holm, Sweden, 2008. 被引量:1
  • 7LONGY. Modeling the Performance of High Burn-up Thoria and Urania PWR Fuel. Department of Nuclear Engineering, B.S., Tsinghua University, Beijing, China, 1995. 被引量:1
  • 8IAEA. Thorium Based Fuel Options for the Generation of Elec- tricity: Development in the 1990s, IAEA-TECDOC-1155, 2000. 被引量:1
  • 9Margeanuand C A, Rizoiu A C. Thorium-Based :els Prelim- inary Lattice Cell Studies For CANDU Reactors. Proceedings of tile 7TM Conference on Nuclear and Particle Physics. Sharm El-Sheikh, Egypt, 2009. 被引量:1
  • 10Moosakhani A, Nasrabadi M N, Timuri B. Nuclear Engineering and Design, 2011, 241:1459-1462. 被引量:1

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