Effect of dissolved oxygen on the corrosion behavior at the crevice surface in high temperature water under gamma-ray irradiation
- 1. Japan Atomic Energy Agency, Nuclear Science and Engineering Center, Tokai, Ibaraki (Japan)
- 2. Japan Atomic Energy Agency, Nuclear Safety Research Center, Tokai, Ibaraki (Japan)
Description
In order to evaluate the effects of dissolved oxygen concentration on the radiolytic water quality within the cracks of stress corrosion cracking (SCC) under irradiation and the spatial distribution of water quality along the depth axis during irradiation, we conducted immersion tests of stainless steel with a crevice gap and computational simulations of water radiolysis. It has been confirmed that Fe2O3 is formed throughout the entire crevice region, irrespective of the dissolved oxygen concentration. Furthermore, it has been estimated that oxidant species generated by radiolysis within the crack are consumed by the growth of oxides under irradiation, and that the reduction in pH at the crack tip occurs by hydrolysis of dissolved metallic elements and enrichment of anions. (author)
Availability note (English)
Available from https://www.jstage.jst.go.jp/browse/jcorr/73/4/_contents/-char/en
Abstract (Japanese)
放射線照射下でのSCCき裂内の放射線分解水質における溶存酸素濃度の寄与とき裂深さ方向の水質分布の評価のため,隙間付与ステンレス鋼のガンマ線照射下試験とラジオリシス解析を実施した.その結果,溶存酸素濃度によらず隙間内全域にFe2O3が形成されることを確認した.また,照射下では,き裂内でラジオリシスにより直接生成された酸化剤種は被膜成長で消費され,放射線環境下でもき裂先端部で溶出金属の加水分解とアニオン濃縮によるpH低下が発生することが推定された.(著者)Additional details
Additional titles
- Original title (Japanese)
- ガンマ線照射下にある高温水中でのステンレス鋼隙間内腐食挙動における溶存酸素の影響
- Augmented title (English)
- (free terms) Boiling Water Reactors; Stress Corrosion Cracking; Stainless steel; gamma-ray irradiation; Dissolved oxygen; Hydrogen peroxide; Crevice
Identifiers
Publishing Information
- Journal Title
- Zairyo To Kankyo (Online)
- Journal Volume
- 73
- Journal Issue
- 4
- Series
- 雑誌名:材料と環境
- Journal Page Range
- p. 102-109
- ISSN
- 1881-9664
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 55078328
- Subject category
- S36: MATERIALS SCIENCE; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BWR TYPE REACTORS; CRACKS; CREVICE CORROSION; DEPTH; DISSOLVED GASES; GAMMA RADIATION; HYDROGEN PEROXIDE; IRON OXIDES; IRRADIATION; OXYGEN; PH VALUE; RADIOLYSIS; STAINLESS STEELS; STRESS CORROSION; TEMPERATURE RANGE 0400-1000 K; WATER CHEMISTRY; WATER QUALITY
- Descriptors DEC
- ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL RADIATION EFFECTS; CHEMICAL REACTIONS; CHEMISTRY; CORROSION; DECOMPOSITION; DIMENSIONS; ELECTROMAGNETIC RADIATION; ELEMENTS; ENRICHED URANIUM REACTORS; ENVIRONMENTAL QUALITY; FLUIDS; GASES; HIGH ALLOY STEELS; HYDROGEN COMPOUNDS; IONIZING RADIATIONS; IRON ALLOYS; IRON BASE ALLOYS; IRON COMPOUNDS; NONMETALS; OXIDES; OXYGEN COMPOUNDS; PEROXIDES; POWER REACTORS; RADIATION EFFECTS; RADIATIONS; REACTORS; SOLUTES; STEELS; TEMPERATURE RANGE; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TRANSITION ELEMENT COMPOUNDS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 31 refs., 7 figs., 6 tabs.