Ageing of structural materials for PWR and evaluation on safety and reliability of the reactor. (3) Possibility of increase for susceptibility of environmentally assisted cracking for ageing of austenitic stainless steel, carbon steel and low alloy steel

Published March 2022 | Version v1

Journal article Metadata-only

1. Former, Tohoku University, Graduate School of Engineering, Sendai, Miyagi (Japan)

no abstract available

Availability note (English)

Available from DOI: https://doi.org/10.3327/jaesjb.64.3_157

Original title (Japanese): 加圧水型軽水炉用構造材料の高経年化と炉の安全性・信頼性評価.(その3) ステンレス鋼,炭素鋼,低合金鋼の高経年化に伴う環境助長割れ感受性・き裂進展速度増大等の可能性について

Country of Publication: Japan
Country of Input or Organization: Japan
INIS RN: 53113820
Subject category: S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator: No Abstract
Descriptors DEI: AGING; CARBON STEELS; CRACK PROPAGATION; CRACKS; ELECTRIC POTENTIAL; ELECTROCHEMISTRY; IRRADIATION; LOW ALLOY STEELS; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS; REACTOR MATERIALS; SEGREGATION; STAINLESS STEELS; STRESS CORROSION; THERMAL STRESSES; WATER QUALITY
Descriptors DEC: ALLOYS; CARBON ADDITIONS; CHEMICAL REACTIONS; CHEMISTRY; COOLING SYSTEMS; CORROSION; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; ENVIRONMENTAL QUALITY; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; POWER REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; STEELS; STRESSES; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER COOLED REACTORS; WATER MODERATED REACTORS