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ナトリウム冷却高速炉の炉心損傷事故時の制御棒材の共晶溶融挙動に関する研究,27; 15mass% B$$_{4}$$C-SS共晶溶融物の垂直分光放射率,熱容量および熱伝導率測定

Study on eutectic melting behavior of control rod materials in core disruptive accidents of sodium-cooled fast reactors, 27; Normal spectral Emissivity, heat capacity and thermal conductivity of 15mass% B$$_{4}$$C-SS eutectic molten material

東 英生*; 福山 博之*; 山野 秀将   

Higashi, Hideo*; Fukuyama, Hiroyuki*; Yamano, Hidemasa

ナトリウム冷却高速炉の炉心損傷事故における制御棒材(炭化ホウ素: B$$_{4}$$C)と原子炉構造材(ステンレス鋼: SS)の共晶反応挙動を模擬するのに必要な熱物性モデル構築のため、超高温熱物性計測システム(PROSPECT)を用いた非接触レーザー周期加熱カロリメトリ法により、15mass% B$$_{4}$$C-SS系融体の放射率,熱容量および熱伝導率の測定を行った結果について報告する。

The purpose of this study is to develop the thermophysical property model needed to simulate the behavior of the eutectic compound of the control rod material (boron carbide (B$$_{4}$$C)) and the structural material of a reactor vessel (stainless steel: SS) during a core disruptive accident in a sodium-cooled fast reactor. This paper describes the emissivity, thermal capacity, and thermal conductivity of the molten material of 15mass% B$$_{4}$$C-SS measured with High-Temperature Thermophysical Property Measurement System (PROSPECT) employing noncontact laser modulation calorimetry.

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