Application of the GIF Safety Design Criteria and Safety Design Guidelines on Decay Heat Removal System to Next Generation Sodium-Cooled Fast Reactor in Japan

被引：0

作者：

Yamano, Hidemasa ^{[1
]}

Futagami, Satoshi ^{[1
]}

Higurashi, Koichi ^{[2
]}

机构：

[1] Japan Atomic Energy Agency (JAEA), 4002 Narita, O-arai, Ibaraki, 311-1393, Japan

[2] Mitsubishi FBR Systems, Inc (MFBR), 2-34-17, Jingumae, Shibuya, Tokyo,150-0001, Japan

来源：

Proceedings of Advanced Reactor Safety, ARS 2024 | 2024年

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D O I：

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学科分类号：

摘要：

Cooling systems - Dynamic response - Model structures - Nuclear reactor accidents - Railroad accidents - Reactor refueling - Structural dynamics - Thermoelectric equipment

引用

页码：121 / 130