Core Dynamics Analysis of Control Rod Withdrawal Test and Nuclear Characteristics in HTTR Reactor Power 30-60%-Reference-Cited by-同舟云学术

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Core Dynamics Analysis of Control Rod Withdrawal Test and Nuclear Characteristics in HTTR Reactor Power 30-60%

Published:2006 Issue:2 Volume:5 Page:81-95
ISSN:1347-2879
Container-title:Transactions of the Atomic Energy Society of Japan
language:en
Short-container-title:Transactions of the Atomic Energy Society of Japan

Author:

TAKAMATSU Kuniyoshi,NAKAGAWA Shigeaki,TAKEDA Tetsuaki

Publisher

Atomic Energy Society of Japan

Subject

Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Cited by 4 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Dynamic modeling and validation of the 5 MW small modular supercritical CO2 Brayton-Cycle reactor system;Energy Conversion and Management;2022-02

2. Experiments and validation analyses of HTTR on loss of forced cooling under 30% reactor power;Journal of Nuclear Science and Technology;2014-11-11

3. Spontaneous stabilization of HTGRs without reactor scram and core cooling—Safety demonstration tests using the HTTR: Loss of reactivity control and core cooling;Nuclear Engineering and Design;2014-05

4. Development of an Evaluation Model for the Thermal Annealing Effect on Thermal Conductivity of IG-110 Graphite for High-Temperature Gas-Cooled Reactors;Journal of Nuclear Science and Technology;2009-07

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