Comparative study of transient thermal–hydraulic characteristics of SCWRs with different core design
Author:
Publisher
Elsevier BV
Subject
Nuclear Energy and Engineering
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1. Development of safety analysis code for SCWR and its LOCA analysis of CSR1000;Nuclear Engineering and Design;2018-02
2. Sensitivity and Uncertainty Analysis of a SCWR from Monte Carlo Simulations;Proceedings of The 20th Pacific Basin Nuclear Conference;2017
3. Preliminary study to improve the performance of SCWR-M during loss-of-flow accident;Nuclear Engineering and Design;2016-10
4. Passive safety system of a super fast reactor;Nuclear Engineering and Design;2015-08
5. Depressurization study of supercritical fluid blowdown from simple vessel;Annals of Nuclear Energy;2014-04
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