Paper Review Records
All Paper Review Records
10 valid samples · Newest publication first
Review days = acceptance date − received date. PDF, DOI, and publisher-page sources are retained.
Numerical investigation of thermal-hydraulic behavior in LBE-Cooled fast reactor assembly under ocean conditions via UDF-Enhanced CFD model
AuthorsYu Zhu; Kefan Zhang; Wenshun Duan; Sifan Dong; Hongli Chen
AffiliationsSchool of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui 230026, China
An efficient method for fault tree analysis to support nuclear plant operation decision-making
AuthorsMohamed Y. Nassar; Joseph O’Leary; Yunfei Zhao
AffiliationsRisk and Decision Analysis Laboratory, Department of Mechanical Engineering, University of Maryland, Glenn L. Martin Hall, 4298 Campus Dr., College Park, MD, 20742, United States; Center for Risk and Reliability, University of Maryland, Glenn L. Martin Hall, 4298 Campus Dr., College Park, MD, 20742, United States
A coupled three-dimensional porous-media and drift-flux model for full-domain thermal-hydraulic analysis of steam generators
AuthorsBo Wang; Yan Zhang; Zhiwei Huang; Yang Yang; Zhengrong Guo; Yukang Liu; Mingyang Li
AffiliationsNuclear Equipment Design Institute, Dongfang Electric Corporation Limited, Chengdu 610097, China; Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education of PRC, Chongqing University, 174 Shazheng District, Chongqing 400030, China; School of Energy and Power Engineering, Chongqing University, Chongqing 400030, China
Experimental and numerical study on the protective performance of special doors in nuclear power plants subjected to windborne missile impact and long-duration blast loading
AuthorsPeng Xu; Xunjia Zhuo; He Zhu; De Chen
AffiliationsCollege of Civil Engineering, Tongji University, Shanghai 200092, China; Shenzhen China Nuclear Power Design Co., Ltd., Shenzhen 518172, China; State Key Laboratory of Nuclear Power Safety Technology and Equipment, China Nuclear Power Engineering Co., LV, Shenzhen 518116, China; School of Mechanics and Engineering Science, Shanghai University, Shanghai 200444, China
Studies of oxygen control in a lead–bismuth eutectic loop
AuthorsHui Li; Xiaoyang Lun; Wei Mao; Xingyan Zhou; Haicai Lyu; Huiping Zhu; Fang Liu; Ruixian Liang; Xiaobo Li; Fenglei Niu
AffiliationsInstitute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, China; School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China; Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
Comparison of control rod worth and doubling time in the high flux reactor: Static and dynamic Serpent 2 simulations with ENDF/B-VIII.0 and JEFF-3.3
AuthorsAlan Wichink Kruit; Benjaminas Marcinkevicius; Kornilios Routsonis
AffiliationsNRG PALLAS, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten, The Netherlands
Fuel-form effects on normal-operation and LOCA performance of U–ZrH and MOX fuel rods in the MARVEL microreactor
AuthorsYuze Tan; Rong Liu
AffiliationsSchool of Electric Power, South China University of Technology, Guangzhou 510640, Guangdong, China
Development of a neutronics–thermal–fluid–structure coupling methodology for performance analysis of U-50Zr helical cruciform fuel
AuthorsJianfeng Xu; Qufei Song; Tenglong Cong; Hui Guo; Hanyang Gu
AffiliationsSchool of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dongchuan Road, Shanghai, 200240, China
Performance mechanism and reliable operating regime of high-temperature sodium heat pipes with a large aspect ratio for MHPRs
AuthorsKun Li; Yan Yan; Xujia Wang; Quan Zhou; Kai Zhang; Qiming Men; Shengyao Jiang; Nan Gui
AffiliationsShanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai 200233, China; Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Tsinghua University, Beijing 100084, China
Research on system operation control method for SMRs based on main pump health assessment
AuthorsKai Wang; Zhi Chen; Pengcheng Yang; Yaowu Li; Yifan Jian; Xuecen Zhao
AffiliationsNational Key Laboratory of Nuclear Reactor Technology, Nuclear Power Institute of China, 610213 Chengdu, China
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