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- Material Type
- 規格・テクニカルリポート類
- Author/Editor
- シュラウド・再循環系配管サンプル調査チーム中島 甫柴田 勝之塚田 隆鈴木 雅秀木内 清加治 芳行菊地 正彦上野 文義中野 純一三輪 幸夫海老根 典也西山 裕孝本岡 隆文加藤 千明新谷 文将
- Publication Date
- 2004-03
- Publication Date (W3CDTF)
- 2004
- Alternative Title
- Report of Examination of the Sample from Core Shroud (2F2-H3) at Fukushima Dai-ni Power Station Unit-2 (Contract research)
- Periodical title
- JAERI-Tech 2004-015
- Target Audience
- 一般
- Note (General)
- 出版タイプ： NA東京電力(株)福島第二原子力発電所2号機においては、原子力安全・保安院の指示によりシュラウド溶接部の目視点検を実施し、炉心シュラウド中間胴/中間部リング溶接線H3外面にひび割れを発見した。本調査は、東京電力(株)が日本核燃料開発(株)にて実施するき裂を含む材料サンプルの調査・評価に関して、原研が第三者機関として調査計画の策定段階から加わり、調査中には随時試験データの評価や試験現場への立会を実施し、最終的に得られた調査データを入手し原研独自の調査報告書を作成することにより、調査の透明性を確保することを目的として実施した。本調査の結果と溶接により発生する引張残留応力及び炉水中の比較的高い溶存酸素濃度を考慮すると、このき裂は応力腐食割れ(SCC)であると考えられる。応力腐食割れの発生原因については、さらに施工法の調査などを行い検討する必要がある。The Tokyo Electric Power Company (TEPCO) visually inspected the weld joint of core shroud at Fukushima Dai-ni Nuclear Power Station Unit-2 by a direction of the Nuclear and Industrial Agency, cracks were observed at outer side of the ring weld joint (H3) between a core shroud middle trunk and a middle ring. TEPCO has conducted a material examination with Nippon Nuclear Fuel Development Co. Ltd. (NFD) on the specimen including cracks sampled from the core shroud. The present examination has been performed with the objective to independently investigate and evaluate the materials by jointly attending the examination with NFD from the planning stage. Based on results of the present examination, the probable presence of tensile residual stress by welding process and dissolved oxygen contents in the cooling water, it was shown that the cracks were considered to be stress corrosion cracking (SCC). However, the cause of the cracks needs more consideration on the way of shroud construction.
- Source
- /JAERI-Tech-2004-015.pdf （fulltext）