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- Material Type
- 規格・テクニカルリポート類
- Author/Editor
- 広井 博佐藤 稔田辺 裕美綿見 正和吉岡 直樹堀 雅夫
- Publication Date
- 1979-06
- Publication Date (W3CDTF)
- 1979
- Alternative Title
- Test results of Run-4 in steam generator safety test facility (SWAT-3); Report No.9; Large leak sodium-water reaction test
- Periodical title
- PNC TN941 79-118
- Target Audience
- 一般
- Note (General)
- 出版タイプ： NA高速増殖原型炉「もんじゅ」蒸気発生器の大リーク・ナトリウムー水反応事故に対する安全設計データを得るため,動燃大洗工学センターにおいて,SWAT―1試験装置,SWAT―3試験装置を用いて試験が行なわれている。本報告書はSWAT―3で実施された第4回大リーク・ナトリウム‥水反応試験(Run―4)にて得られたデータをとりまとめたものである。Run―4で使用された内部構造物は,東芝/石川島播磨重工業(株)で設計製作されたものである。三試験の主目的は伝熱管コイル上部(液面下640mm)でのナトリウム-水反応現象の解明にある。Run―4の注水率は,9.0kg/secであり,これはiso―velocitymodelによれば,「もんじゅ」蒸気発生器伝熱管5本破断に相当する試験規模であった。試験においては,圧力,歪,温度,液面,ボイド,配管反力,加速度,変位,流量等が計測された。初期スパイク圧力は注水点近傍で14.7kg/cm$\times$2aであり,蒸発器内での準定常圧力の最大値は54kg/cm$\times$2aであった。蒸発器放出系ラプチャ板は注水開始後0.536secに破裂し,放出系の作動は良好であった。伝熱管二次破断はなかった。Large leak sodium-water reaction tests have been carried out using the SWAT-3 facility in PNC O-arai Engineering Center to obtain data on the safe design of the prototype LMFBR Monju's steam generator with reference to preventing large leak accident. This report gives the results of SWAT-3 run-4 test. The heat transfer tube bundle of the evaporator used in Run-4 test was designed and manufaetured by TOSHIBA/IHI. Main purpose of this test is to clarify sodium-water reaction phenomena occured in the upper coil region, that is, the place near by sodium surface. Water was injected into the evaporator at the rate of 9.0 kg/sec, which corresponds to a test scale of 5 tube failure in an actural size system according to iso-velocity modeling. Measurements were taken of pressure, strain, temperature, sodium level, void, thrust load, acceleration, displacement, flow rate, and so on. Initial spike pressure was 14.7 kg/cm$^{2}$a closest to the injection point, and the maximum quasi-steady pressure in the evaporator was 5.4 kg/cm$^{2}$a. The rupture disc of the evaporator burst 0.536 sec. after water was injected, and the pressure relief system functioned well. No secondary tube failure was observed.
- Source
- /PNC-TN941-79-118.pdf （fulltext）