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Neutronic study of utilization of discrete thorium-uranium fuel pins in CANDU-6 reactor

  • Published:2019-04 Issue:2 Volume:51 Page:377-383
  • ISSN:1738-5733
  • Container-title:Nuclear Engineering and Technology
  • language:en
  • Short-container-title:Nuclear Engineering and Technology

Author:

Deng Nianbiao,Yu Tao,Xie Jinsen,Chen Zhenping,Xie Qin,Zhao Pengcheng,Liu Zijing,Zeng Wenjie

Funder

National Natural Science Foundation of China

2018 Graduate Research and Innovation Project of Hunan Province, PR China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference24 articles.

1. Power Reactor Information System;IAEA,2017

2. Validation of thorium fuel benchmark by DRAGON code using WLUP library;Zhang;Atomic Energy Sci. Technol.,2016

3. Thorium Fuel Cycle: Potential Benefits and Challenges, IAEA-tecdoc-1450;International Atomic Energy Agency,2005

4. Technical advantage of HWR and the tentative plan for its development;Zhang;China Nuclear Power,2010

5. Characteristics and development of CANDU NPP unit;Qian;Chinese J. Nucl. Sci. Eng.,2003

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