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Loss of core cooling test without one cooling line in Vessel Cooling System (VCS) of High Temperature engineering Test Reactor (HTTR)

HTTRにおけるVCS1系統停止時の炉心冷却喪失試験

藤原 佑輔; 根本 隆弘; 栃尾 大輔; 篠原 正憲; 小野 正人; 濱本 真平; 飯垣 和彦; 高田 昌二

Fujiwara, Yusuke; Nemoto, Takahiro; Tochio, Daisuke; Shinohara, Masanori; Ono, Masato; Hamamoto, Shimpei; Iigaki, Kazuhiko; Takada, Shoji

HTTRにおいて、原子炉出力が9MWの状態かつ炉心流量の喪失を模擬した状態において炉心冷却喪失状態を模擬するためにVCS1系統を停止させた。試験の結果、炉内構造物の温度変化は緩慢であった。また、RPV温度は数度下降し、遮蔽体コンクリートの温度上昇は1度以下であった。VCS冷却管を詳細にモデル化した解析ではVCS冷却管の温度上昇はおよそ15度であり、遮蔽体コンクリートの影響が小さいことを明らかにした。これらの結果から、VCS1系統停止状態であっても冷却能力は保たれることを明らかにした。

In HTTR, the test was carried out at the reactor thermal power of 9 MW under the condition that one cooling line of VCS was stopped to simulate the partial loss of cooling function from the surface of RPV in addition to the loss of forced cooling flow in the core simulation. The test results showed that temperature change of the core internal structures and the biological shielding concrete was slow during the test. Temperature of RPV decreased several degrees during the test. The temperature decrease of biological shielding made of concrete was within 1 degree C. The numerical result simulating the detail configuration of the cooling tubes of VCS showed that the temperature rise of cooling tubes of VCS was about 15 degree C, which is sufficiently small, which did not significantly affect the temperature of biological shielding concrete. As the results, it was confirmed that the cooling ability of VCS can be kept in case that one cooling line of VCS is lost.

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