Rong-Rui Yang; Yuan Yuan; Chen Hao; Ji Ma; Guang-Hao Liu

doi:10.1007/s41365-021-00969-w

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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

NUCLEAR ENERGY SCIENCE AND ENGINEERING | Updated：2021-12-06

- 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 Cover Article Enhanced Publication
- Nuclear Science and Techniques Vol.32, Issue 11, (2021)
- Affiliations：
  
  Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, College of Nuclear Science and Technology, Harbin Engineering University,Harbin,China.,150001;Department of Reactor Technology, Beijing Institute of Nuclear Engineering, China Nuclear Power Engineering Co., Ltd,Beijing,China,100089
- Author bio：
- Funds：
- DOI：10.1007/s41365-021-00969-w CLC：
- Published：01 November 2021，
  
  Published Online：18 November 2021，
  
  Received：19 July 2021，
  
  Revised：13 September 2021，
  
  Accepted：15 September 2021
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Cite this article
Rong-Rui Yang, Yuan Yuan, Chen Hao, et al. 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. [J]. Nuclear Science and Techniques 32(11):127(2021)
DOI：

Rong-Rui Yang, Yuan Yuan, Chen Hao, et al. 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. [J]. Nuclear Science and Techniques 32(11):127(2021) DOI： 10.1007/s41365-021-00969-w.

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

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 Cover Article Enhanced Publication