×
近期发现有不法分子冒充我刊与作者联系,借此进行欺诈等不法行为,请广大作者加以鉴别,如遇诈骗行为,请第一时间与我刊编辑部联系确认(《中国物理C》(英文)编辑部电话:010-88235947,010-88236950),并作报警处理。
本刊再次郑重声明:
(1)本刊官方网址为cpc.ihep.ac.cn和https://iopscience.iop.org/journal/1674-1137
(2)本刊采编系统作者中心是投稿的唯一路径,该系统为ScholarOne远程稿件采编系统,仅在本刊投稿网网址(https://mc03.manuscriptcentral.com/cpc)设有登录入口。本刊不接受其他方式的投稿,如打印稿投稿、E-mail信箱投稿等,若以此种方式接收投稿均为假冒。
(3)所有投稿均需经过严格的同行评议、编辑加工后方可发表,本刊不存在所谓的“编辑部内部征稿”。如果有人以“编辑部内部人员”名义帮助作者发稿,并收取发表费用,均为假冒。
                  
《中国物理C》(英文)编辑部
2024年10月30日

Neutronic calculations for CANDU thorium systems usingMonte Carlo techniques

  • 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.
      PCAS:
  • 加载中
  • [1] Şahin S, Şahin H M, Acir A. Nuclear Engineering and Design, 2010, 240: 2066-2074[2] Şahin S, Acir A. Energy Conversion and Management, 2006, 47: 1661-1675[3] Şahin S, Yildiz K, Şahin H M, Şahin N, Acir A. Nuclear Engineering and Design, 2006, 236(17): 178-179[4] Busse M. Optimization Of Thorium-Based Seed-Blanket Fuel Cycles For Nuclear Power Plants. M.S., Nuclear Engineering Instituto Balseiro, University of Cuyo, Argentina, 1995[5] Canerl M, Dugan E T. Annals of Nuclear Energy, 2000, 27: 759-770[6] Chanyun L. Design and Neutronic Evaluation of Thorium Fuel in Pressurized Water Reactors. Master of Science Thesis Reactor Physics Department Royal Institute of Technology, Stockholm, Sweden, 2008[7] LONG Y. Modeling the Performance of High Burn-up Thoria and Urania PWR Fuel. Department of Nuclear Engineering, B.S., Tsinghua University, Beijing, China, 1995[8] IAEA. Thorium Based Fuel Options for the Generation of Electricity: Development in the 1990s, IAEA-TECDOC-1155, 2000[9] Margeanuand C A, Rizoiu A C. Thorium-Based Fuels Preliminary Lattice Cell Studies For CANDU Reactors. Proceedings of the 7th Conference on Nuclear and Particle Physics. Sharm El-Sheikh, Egypt, 2009[10] Moosakhani A, Nasrabadi M N, Timuri B. Nuclear Engineering and Design, 2011, 241: 1459-1462[11] Oak Ridge National Laboratory, Monte Carlo N-Particle Transport Code System. Los Alamos National Laboratory, Los Alamos, New-Mexico, 2000."MCNP4C manual"[12] Snoj L, Ravnik M. Calculation of Power Density with MCNP in TRIGA Reactor. Nuclear Energy for New Europe, International Conference, Portorož, Slovenia, 2006[13] Eshghi Yaraziz M, Shayesteh M. Golobal J. P A Sci. and Tech., 2011, v01: 65-72[14] Eshghi M, Shayesteh M. Archives Des Sciences, 2012, 65(4): 1[15] Lamarsh J R. Introduction to Nuclear Engineering. Second ed. Addison-Wesley Publishing Co., USA, 1983
  • 加载中

Get Citation
M. Saldideh, M. Shayesteh and M. Eshghi. Neutronic calculations for CANDU thorium systems usingMonte Carlo techniques[J]. Chinese Physics C, 2014, 38(8): 088201. doi: 10.1088/1674-1137/38/8/088201
M. Saldideh, M. Shayesteh and M. Eshghi. Neutronic calculations for CANDU thorium systems usingMonte Carlo techniques[J]. Chinese Physics C, 2014, 38(8): 088201.  doi: 10.1088/1674-1137/38/8/088201 shu
Milestone
Received: 2013-09-11
Revised: 1900-01-01
Article Metric

Article Views(1874)
PDF Downloads(124)
Cited by(0)
Policy on re-use
To reuse of subscription content published by CPC, the users need to request permission from CPC, unless the content was published under an Open Access license which automatically permits that type of reuse.
通讯作者: 陈斌, bchen63@163.com
  • 1. 

    沈阳化工大学材料科学与工程学院 沈阳 110142

  1. 本站搜索
  2. 百度学术搜索
  3. 万方数据库搜索
  4. CNKI搜索

Email This Article

Title:
Email:

Neutronic calculations for CANDU thorium systems usingMonte Carlo techniques

    Corresponding author: M. Saldideh,
    Corresponding author: M. Eshghi,

Abstract: 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.

    HTML

Reference (1)

目录

/

DownLoad:  Full-Size Img  PowerPoint
Return
Return