SCWR transient safety analysis code SCAC-CSR1000-Reference-Cited by-同舟云学术

SCWR transient safety analysis code SCAC-CSR1000

Published:2015-08 Issue: Volume:83 Page:318-325
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Liu Liang^ORCID,Zhou Tao,Li Yu,Chen Juan,Ali Muhammad Zeeshan,Xiao Zejun

Funder

Research Fund of the China Key Laboratory of Nuclear Reactor System Design Technology

Research Fund of the China Key Laboratory of nuclear thermal-hydraulic technology

Central Universities special funds basic research and business projects

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

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4. Influence analysis of coupled neutronics and thermal-hydraulics on characteristics of supercritical water-cooled reactor system;Chen;At. Energy Sci. Technol.,2013

5. Research status and prospect of super critical water-cooled reactor;Cheng;At. Energy Sci. Technol.,2008

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