Evaluation of Hot Spot Factors for Thermal and Hydraulic Design of HTTR.
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概要
- 論文の詳細を見る
High Temperature Engineering Test Reactor (HTTR) is a graphite-moderated and helium gas-cooled reactor with 30 MW in thermal power and 950°C in reactor outlet coolant temperature. One of the major items in thermal and hydraulic design of the HTTR is to evaluate the maximum fuel temperature with a sufficient margin from a viewpoint of integrity of coated fuel particles. Hot spot factors are considered in the thermal and hydraulic design to evaluate the fuel temperature not only under the normal operation condition but also under any transient condition conservatively. This report summarizes the items of hot spot factors selected in the thermal and hydraulic design and their estimated values, and also presents evaluation results of the thermal and hydraulic characteristics of the HTTR briefly.
- 一般社団法人 日本原子力学会の論文
著者
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Murata Isao
Department Of Earth And Planetary Physics Graduate School Of Science University Of Tokyo
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Fujimoto Nozomu
Department Of Httr Project Japan Atomic Energy Research Institute
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MARUYAMA So
Department of HTTR Project, Japan Atomic Energy Research Institute
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YAMASHITA Kiyonobu
Department of HTTR Project, Japan Atomic Energy Research Institute
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SUDO Yukio
Department of HTTR Project, Japan Atomic Energy Research Institute
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MURAKAMI Tomoyuki
HTR Project Office, Fuji Electric Co., Ltd.
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FUJII Sadao
Engineering Department, Kawasaki Heavy Industries, Ltd.,
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MURATA Isao
Department of HTTR Project, Japan Atomic Energy Research Institute
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