書誌事項
- タイトル別名
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- Thermal Load Control Methods for the HTTR-IS Nuclear Hydrogen Production System
- HTTR-IS水素製造装置における熱負荷変動緩和システムの運転制御法
- HTTR IS スイソ セイゾウ ソウチ ニ オケル ネツ フカ ヘンドウ カンワ システム ノ ウンテン セイギョホウ
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説明
One of the key technology requirements to achieve the non-nuclear-grade hydrogen plants coupled to the HTTR is the development of control methods mitigating the effect of IS process-abnormal thermal load transients on the reactor operation. This study focused on developing the control methods for the thermal mitigation system in the HTTR-IS system. The control methods are developed to stabilize the steam generator helium gas outlet temperature increase against the high-temperature helium gas inflow. The key parameters and equipment are determined and the control operations are simulated. The simulation results show that the steam generator water temperature can be effectively decreased by interfacing the actuation of the air cooler inlet shut-off valve with the actuation of the diverter valve. Furthermore, the air cooler outlet shut-off valve is activated as the pressure difference approaches zero between the steam generator bottom and the down comer from the air cooler to the steam generator. It is demonstrated that the control methods developed enable the continuation of the nuclear reactor normal operation under IS process abnormal conditions and without operator intervention.<br>
収録刊行物
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- 日本原子力学会和文論文誌
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日本原子力学会和文論文誌 7 (4), 328-337, 2008
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390001205186194688
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- NII論文ID
- 10024631947
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- NII書誌ID
- AA11643165
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- ISSN
- 21862931
- 13472879
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- NDL書誌ID
- 9732415
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- 本文言語コード
- ja
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- データソース種別
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- JaLC
- NDL
- Crossref
- CiNii Articles
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- 抄録ライセンスフラグ
- 使用不可