高圧注入系の不作動と蓄圧注入系からのガス流入を想定したPWR炉容器底部破断LOCAにおける急減圧操作開始時期に関する研究,ROSA-V/LSTF実験SB-PV-06

Material type: 文書・図像類

Author: 鈴木光弘ほか

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Publication date: 2007-03

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Note (General)：: A small break LOCA experiment (SB-PV-06) was conducted at the LSTF of ROSA-V program to study effects of rapid secondary depressuriza-tion action on c...

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Summary, etc.：: A small break LOCA experiment (SB-PV-06) was conducted at the LSTF of ROSA-V program to study effects of rapid secondary depressuriza-tion action on c...

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Material Type: 文書・図像類
Title: 高圧注入系の不作動と蓄圧注入系からのガス流入を想定したPWR炉容器底部破断LOCAにおける急減圧操作開始時期に関する研究,ROSA-V/LSTF実験SB-PV-06
Author/Editor: 鈴木光弘
竹田武司
浅香英明
中村秀夫
Author Heading: 鈴木光弘
竹田武司
浅香英明
中村秀夫
Publication Date: 2007-03
Publication Date (W3CDTF): 2007-03
Alternative Title: A Study on timing of rapid depressurization action during PWR vessel bottom break LOCA with HPI failure and AIS-gas inflow, ROSA-V/LSTF test SB-PV-06
Periodical title: JAEA-Research 2007-037
Text Language Code: eng
Target Audience: 一般
Note (General): A small break LOCA experiment (SB-PV-06) was conducted at the LSTF of ROSA-V program to study effects of rapid secondary depressuriza-tion action on core cooling as one of accident management (AM) measures for a PWR in case of high pressure injection system failure and non-condensable gas inflow from the accumulator injection system. The break simulated 10 instrument tubes rupture equivalent to 0.2\% cold leg break. It was clarified through comparison with former experiments that (1) the depressurization initiated by detecting the vessel level below the primary loop (4545s) was degraded by the gas inflow resulting in whole core uncovery prior to the start of low pressure injection and (2) an alternative start of the depressurization by detecting level decrease at the SG outlet plenum (2330s), would limit the core uncovery suggesting more effective parameter for the AM measures. The report presents the experiment results with the effects of rapid depressurization initiation timing.
ROSA-V計画で、PWR小破断冷却材喪失事故を模擬したLSTF実験(SB-PV-06)を実施し、以前に行った実験との比較により、高圧注入系の不作動と蓄圧注入系からの非凝縮性ガス流入を想定した場合に、アクシデントマネジメント(AM)策の1つである2次系急減圧操作の実施時期が炉心冷却に及ぼす影響を調べた。破断口は原子炉容器底部の計装管10本破断を模擬したが、これはコールドレグ0.2\%破断に相当する。次の点が明らかになった。(1)急減圧操作は炉容器水位が1次系配管以下に低下した時点(4545s)で開始したが、流入ガスにより減圧が阻害され、低圧注入系作動以前に全炉心露出に至った。(2)急減圧開始の代替方策として、蒸気発生器出口プレナムの水位低下検出(2330s)によると、炉心露出は限定されるため、より有効なAM策の指標になると予測される。本報告書は、本実験結果とこれらの急減圧操作開始時期の効果をまとめたものである。
Source: /JAEA-Research-2007-037.pdf （fulltext）
https://jopss.jaea.go.jp/pdfdata/JAEA-Research-2007-037.pdf
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Original Data Provider (Database): 日本原子力研究開発機構 : JOPSS:JAEA Originated Papers Searching System