Guo-Min Sun; Mao-Song Cheng

doi:10.1007/s41365-016-0070-1

Your Location：

Home >

Browse articles >

Development of a MCNP and ORIGEN2 based burnup code for molten salt reactor

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2021-02-23

- Development of a MCNP and ORIGEN2 based burnup code for molten salt reactor Cover Article Enhanced Publication
- Nuclear Science and Techniques Vol.27, Issue 3, (2016)
- Affiliations：
  
  Shanghai Institute of Applied Physics, Chinese Academy of Sciences,Shanghai,China,201800;University of Chinese Academy of Sciences,Beijing,China,100190
- Author bio：
- Funds：
- DOI：10.1007/s41365-016-0070-1 CLC：
- Published：20 June 2016，
  
  Published Online：11 May 2016，
  
  Received：29 April 2014，
  
  Revised：14 June 2015，
  
  Accepted：14 June 2015
Scan the full text
Cite this article
Guo-Min Sun, Mao-Song Cheng. Development of a MCNP and ORIGEN2 based burnup code for molten salt reactor. [J]. Nuclear Science and Techniques 27(3):65(2016)
DOI：

Guo-Min Sun, Mao-Song Cheng. Development of a MCNP and ORIGEN2 based burnup code for molten salt reactor. [J]. Nuclear Science and Techniques 27(3):65(2016) DOI： 10.1007/s41365-016-0070-1.

Views

Downloads

Cited

Alert me when the article has been cited

Submit

Tools

Publicity Resources

Flow field effect of delayed neutron precursors in liquid-fueled molten salt reactors

Conceptual design and neutronic analysis of a megawatt-level vehicular micro reactor based on TRISO fuel particles and S-CO₂ direct power generation

Burnup optimization of once-through molten salt reactors using enriched uranium and thorium

Absorption effect of pure nickel on the corrosion behaviors of the GH3535 alloy in tellurium vapor

k_eff uncertainty quantification and analysis due to nuclear data during the full lifetime burnup calculation for a small-sized prismatic high temperature gas-cooled reactor

Related Author

Xian-Di Zuo

Yu-Qing Dai

Kai-Cheng Yu

Zhi-Min Dai

Fang-Yuan Zhang

Gui-Feng Zhu

Yang Zou

Rui Yan

Related Institution

Shanghai Jiao Tong University

School of Materials of Science and Engineering, University of Shanghai for Science and Technology

Department of Reactor Technology, Beijing Institute of Nuclear Engineering, China Nuclear Power Engineering Co., Ltd

Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University

CAS Innovative Academies in TMSR Energy System, Chinese Academy of Sciences

⁰

Development of a MCNP and ORIGEN2 based burnup code for molten salt reactor Cover Article Enhanced Publication