福岛第一核电站 2 号机组燃料包壳和燃料元件之间的相互作用对早期堆芯退化的解释

IF 1.5 4区工程技术 Q2 NUCLEAR SCIENCE & TECHNOLOGY

Journal of Nuclear Science and Technology Pub Date : 2024-05-04 DOI:10.1080/00223131.2024.2350534

Ayumi Itoh, Kosuke Inoue, Yoshinao Kobayashi, Kan Sakamoto, Yoichi Endo, Kenichiro Nozaki, Penghui Chai, Shoichi Suehiro, Takeshi Honda, Kenji Owada, Masato Mizokami, Mutsumi Hirai, Kenichi Ito, Shinya Mizokami

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引用次数: 0

摘要

福岛第一核电站 2 号机组堆芯退化的早期阶段是通过材料相互作用的燃料成分退化进行研究的。

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Early-phase core degradation interpretation by interaction between fuel cladding and fuel components in Fukushima Daiichi Nuclear Power Plant Unit 2

The early phase of the core degradation at the Fukushima Daiichi Nuclear Power Station Unit 2 was investigated in terms of a fuel-component degradation by materials interaction by carrying out the ...

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来源期刊

Journal of Nuclear Science and Technology 工程技术-核科学技术

CiteScore

2.40

自引率

16.70%

发文量

116

审稿时长

2.3 months

期刊介绍： The Journal of Nuclear Science and Technology (JNST) publishes internationally peer-reviewed papers that contribute to the exchange of research, ideas and developments in the field of nuclear science and technology, to contribute peaceful and sustainable development of the World. JNST ’s broad scope covers a wide range of topics within its subject category, including but are not limited to: General Issues related to Nuclear Power Utilization: Philosophy and Ethics, Justice and Policy, International Relation, Economical and Sociological Aspects, Environmental Aspects, Education, Documentation and Database, Nuclear Non-Proliferation, Safeguard Radiation, Accelerator and Beam Technologies: Nuclear Physics, Nuclear Reaction for Engineering, Nuclear Data Measurement and Evaluation, Integral Verification/Validation and Benchmark on Nuclear Data, Radiation Behaviors and Shielding, Radiation Physics, Radiation Detection and Measurement, Accelerator and Beam Technology, Synchrotron Radiation, Medical Reactor and Accelerator, Neutron Source, Neutron Technology Nuclear Reactor Physics: Reactor Physics Experiments, Reactor Neutronics Design and Evaluation, Reactor Analysis, Neutron Transport Calculation, Reactor Dynamics Experiment, Nuclear Criticality Safety, Fuel Burnup and Nuclear Transmutation, Reactor Instrumentation and Control, Human-Machine System: Reactor Instrumentation and Control System, Human Factor, Control Room and Operator Interface Design, Remote Control, Robotics, Image Processing Thermal Hydraulics: Thermal Hydraulic Experiment and Analysis, Thermal Hydraulic Design, Thermal Hydraulics of Single/Two/Multi Phase Flow, Interactive Phenomena with Fluid, Measurement Technology...etc.