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Tengfei Zhang
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Scientific Research
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Scientific Research
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Transient coupling analysis of loss-of-coolant accidents in HTR-PM based on CFD approaches.ANNALS OF NUCLEAR ENERGY.2022
Preliminary lightweight core design analysis of a micro-transportable gas-cooled thermal reactor.INTERNATIONAL JOURNAL OF ENERGY RESEARCH.2022
Preliminary conceptual design of a moderated micro nuclear reactor core cooled by heat pipe.ANNALS OF NUCLEAR ENERGY.2022
VITAS: A multi-purpose simulation code for the solution of neutron transport problems based on variational nodal methods.ANNALS OF NUCLEAR ENERGY.2022
Theory and application of the functional expansion fission matrix.Annals of Nuclear Energy.2022
Editorial: Reactor Physics: Methods and Applications.FRONTIERS IN ENERGY RESEARCH.2022
Variational nodal methods for neutron transport: 40 years in review.Nuclear Engineering and Technology.2022
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Published Books：
Nuclear power reactor designs from history to advances
Nuclear Physics Deterministic Code, Nuclear Power Plant Design and Analysis Codes Development, Validation, and Application for Science and Technology
Research Projects：
固体微型反应堆核-热-力多物理耦合关键技术研究
基于复杂构型中子输运算法的小型核反应堆核-热-力耦合研究
小型氦氙冷却移动式固体核反应堆多物理耦合技术研究
核反应堆三维模拟的高分辨率高效率非均匀中子输运计算方法研究
三维多群积分输运变分节块方法的研究与程序研制
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