検索対象:     
報告書番号:
※ 半角英数字
 年 ~ 
 年

Empirical equations for tensile properties and stress-strain curves of neutron irradiated stainless steels in LWR conditions

軽水炉条件で中性子照射されたステンレス鋼の引張特性及び応力-ひずみ曲線に関する経験式の検討

福谷 耕司*; 藤井 克彦*; 知見 康弘; 端 邦樹

Fukuya, Koji*; Fujii, Katsuhiko*; Chimi, Yasuhiro; Hata, Kuniki

軽水炉の炉内構造物の構造健全性評価に資するため、中性子照射したオーステナイト系ステンレス鋼の最新の引張特性データベースを用いたデータフィッティングにより、引張特性の中性子照射量依存性を示す経験式と、応力-ひずみ関係を示す傾向曲線を提案した。データベースに収められた引張特性データは、日本の国家プロジェクトの報告書と公開文献から得られたもので、データシートの形でまとめた。引張特性の中性子照射量依存性を示す経験式は、冷間加工316と溶体化304/316ステンレス鋼に対し、照射量の増加に伴って飽和する式に基づき、温度範囲280-350$$^{circ}$$C、損傷量範囲で最大80dpaを対象として検討した。また、応力-ひずみ関係を示す曲線はSwiftモデルに基づいて検討した。こうして得られた経験式と応力-ひずみ関係の計算結果は、実験値によく一致した。本論文では、組成と冷間加工等、材料の相違の影響について議論した。

For structural integrity assessment on reactor internals of light water reactors, empirical equations of tensile properties as a function of neutron dose, and trend curves of stress-strain relations of neutron-irradiated austenitic stainless steels was proposed by fitting to recently developed database. The data in the database were obtained from reports of national projects in Japan and open literature, which was summarized in the form of data sheets. The empirical equations for tensile properties were formulated by using a saturation-type formulae. The equations were for CW 316 and SA 304/316 stainless steels in the temperature range of 280-350$$^{circ}$$C and the dose range up to 80 dpa. Stress-strain relation curves were reproduced based on the Swift model. Obtained calculated results by the empirical equations and stress-strain relations were reasonably well fitted to experimental data. The effects of composition and cold-working, etc. on tensile properties were discussed.

Access

:

- Accesses

InCites™

:

Altmetrics

:

[CLARIVATE ANALYTICS], [WEB OF SCIENCE], [HIGHLY CITED PAPER & CUP LOGO] and [HOT PAPER & FIRE LOGO] are trademarks of Clarivate Analytics, and/or its affiliated company or companies, and used herein by permission and/or license.