Grain boundary phosphorous segregation and its influence on the ductile brittle transition temperature in reactor pressure vessel steels

A. Kimura, M. Shibata, R. Kasada, H. Nakata, K. Fujii, K. Fukuya

研究成果: Conference article査読

6 被引用数 (Scopus)

抄録

The materials used for this work were two sorts of reactor pressure vessel (RPV) steels, which contain different amounts of phosphorous (P), namely 0.011 and 0.002 wt%. The specimens for Charpy V-notch (CVN) impact test, Auger electron spectroscopy (AES), and tensile test were thermally aged at 400, 450, and 500°C for 1000, 3000, and 5000 h. After the thermal aging, the AES specimens were broken in the AES chamber to measure the P concentration at grain boundaries. The AES measurements for as-received specimens were carried out following hydrogen charging so that grain boundary facets were available even without P segregation. The AES measurements revealed that the peak height ratio (PHR) of P/Fe at the grain boundaries of the high-P steel were 0.066, 0.141, and 0.120 in the specimens aged at 400°C for 3000 h, 450°C for 3000 h, and 500°C for 1000 h, respectively. The ductile-brittle transition temperature (DBTT) was measured for the aged specimens, and the ΔDBTT of 15K was observed only for the specimen aged at 450°C for 3000 h, although no changes in the hardness and tensile properties were observed. The grain boundary fracture ratio (GBFR) increased with increasing the PHR of P/Fe. Grain boundary fracture mode was located at the area close to the V-notch root. There was a good relationship among PHR, GBFR, and DBTT, indicating directly that the shift in the DBTT was due to grain boundary embrittlement caused by P segregation.

本文言語English
ページ(範囲)565-578
ページ数14
ジャーナルASTM Special Technical Publication
1447
DOI
出版ステータスPublished - 2004
外部発表はい
イベントEffects of Radiation on Materials: 21st International Symposium - Tucson, AZ, United States
継続期間: 2002 6 182002 6 20

ASJC Scopus subject areas

  • Engineering(all)

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