Premium
Preliminary safety analysis for the SCWR‐FQT facility
Author(s) -
Liu Xiaojing,
Yang Ting,
Chai Xiang,
Xiong Jinbiao,
Zhang Tengfei,
Cheng Xu
Publication year - 2020
Publication title -
international journal of energy research
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.808
H-Index - 95
eISSN - 1099-114X
pISSN - 0363-907X
DOI - 10.1002/er.5032
Subject(s) - supercritical fluid , neutron transport , nuclear engineering , research reactor , thermal hydraulics , engineering , electricity generation , mechanical engineering , environmental science , power (physics) , heat transfer , nuclear physics , neutron , physics , quantum mechanics , thermodynamics
Summary In recent years, a substantial number of theoretical, numerical and experimental R&D activities are carried out on the supercritical water‐cooled reactor (SCWR), which proposed as one of the Generation IV nuclear power plants by the Generation IV International Forum (GIF). A research plan has been proposed by GIF on the designing and licensing of a SCWR prototype, which is planned to be constructed and operated in the near future. In the preliminary stage of this research plan a fuel assembly, with its experimental loop, will be constructed and tested in SCWR operating conditions. This article reviews the research activities carried out in the Supercritical Water Reactor Fuel Qualification Test (SCWR‐FQT) project in Europe and Super Critical Reactor In‐Pipe Test Preparation (SCRIPT) project in China. These research activities studied both neutronic and thermal–hydraulic behavior of the test fuel assembly and auxiliary systems of SCWR fuel test facility. CFD simulations, subchannel analysis and system simulations coupled with neutronics code are performed to study the performance of the tested fuel assembly, especially safety related aspects.