Development and validation of a coupled neutron diffusion-thermal hydraulic calculation procedure for fast reactor applications-Reference-Cited by-同舟云学术

Development and validation of a coupled neutron diffusion-thermal hydraulic calculation procedure for fast reactor applications

Published:2020-05 Issue: Volume:139 Page:107243
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Zhang Xuebei,Zeng Qin,Chen Hongli^ORCID

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

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3. Xie, Z.S., 2004. Physical Analysis of Nuclear Reactor. Xi’an: Xi'an Jiao Tong University press.

4. Neutronic analysis of HPLWR fuel assembly cluster;Tashakor;Ann. Nucl. Energy,2012

5. Thermal-hydraulic and neutron-physical characteristics of a new SCWR fuel assembly;Liu;Ann. Nucl. Energy,2009

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