Development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life

316FR stainless steel and Mod.9Cr-1Mo steel are candidate structural materials for the present design of sodium-cooled fast reactor (SFR) in Japan. A number of research works have been performed in Japan to develop the SFR for practical use. Aiming at enhancing its economic competitiveness and reduc...

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Autores principales: Takashi ONIZAWA, Ryuta HASHIDATE
Formato: article
Lenguaje:EN
Publicado: The Japan Society of Mechanical Engineers 2019
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Acceso en línea:https://doaj.org/article/8cf4fdd04a204b76a12c68405f5a11ab
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spelling oai:doaj.org-article:8cf4fdd04a204b76a12c68405f5a11ab2021-11-29T05:34:41ZDevelopment of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life2187-974510.1299/mej.18-00477https://doaj.org/article/8cf4fdd04a204b76a12c68405f5a11ab2019-01-01T00:00:00Zhttps://www.jstage.jst.go.jp/article/mej/6/1/6_18-00477/_pdf/-char/enhttps://doaj.org/toc/2187-9745316FR stainless steel and Mod.9Cr-1Mo steel are candidate structural materials for the present design of sodium-cooled fast reactor (SFR) in Japan. A number of research works have been performed in Japan to develop the SFR for practical use. Aiming at enhancing its economic competitiveness and reducing radioactive waste, Japan Atomic Energy Agency has proposed an attractive plant concept and made great efforts to demonstrate the applicability of some innovative technologies to the plant. One of the most practical means is to extend the design life to 60 years. Accordingly, the material strength standards set by the Japan Society of Mechanical Engineers (JSME) have to be extended from 300,000 to 500,000 hours but this extension requires more precise estimation of creep rupture strength and creep strain of the materials in the long term. This paper describes the development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel considering changes in creep mechanisms at high temperatures in the long term based on evaluations of long-term creep properties of the materials. The creep property equations developed in this study will provide more precise estimation of the creep properties in the long term than the present creep property equations of JSME.Takashi ONIZAWARyuta HASHIDATEThe Japan Society of Mechanical Engineersarticle316fr stainless steelmod.9cr-1mo steelcreepcreep rupture equationcreep strain equationregion splitting methodMechanical engineering and machineryTJ1-1570ENMechanical Engineering Journal, Vol 6, Iss 1, Pp 18-00477-18-00477 (2019)
institution DOAJ
collection DOAJ
language EN
topic 316fr stainless steel
mod.9cr-1mo steel
creep
creep rupture equation
creep strain equation
region splitting method
Mechanical engineering and machinery
TJ1-1570
spellingShingle 316fr stainless steel
mod.9cr-1mo steel
creep
creep rupture equation
creep strain equation
region splitting method
Mechanical engineering and machinery
TJ1-1570
Takashi ONIZAWA
Ryuta HASHIDATE
Development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life
description 316FR stainless steel and Mod.9Cr-1Mo steel are candidate structural materials for the present design of sodium-cooled fast reactor (SFR) in Japan. A number of research works have been performed in Japan to develop the SFR for practical use. Aiming at enhancing its economic competitiveness and reducing radioactive waste, Japan Atomic Energy Agency has proposed an attractive plant concept and made great efforts to demonstrate the applicability of some innovative technologies to the plant. One of the most practical means is to extend the design life to 60 years. Accordingly, the material strength standards set by the Japan Society of Mechanical Engineers (JSME) have to be extended from 300,000 to 500,000 hours but this extension requires more precise estimation of creep rupture strength and creep strain of the materials in the long term. This paper describes the development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel considering changes in creep mechanisms at high temperatures in the long term based on evaluations of long-term creep properties of the materials. The creep property equations developed in this study will provide more precise estimation of the creep properties in the long term than the present creep property equations of JSME.
format article
author Takashi ONIZAWA
Ryuta HASHIDATE
author_facet Takashi ONIZAWA
Ryuta HASHIDATE
author_sort Takashi ONIZAWA
title Development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life
title_short Development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life
title_full Development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life
title_fullStr Development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life
title_full_unstemmed Development of creep property equations of 316FR stainless steel and Mod.9Cr-1Mo steel for sodium-cooled fast reactor to achieve 60-year design life
title_sort development of creep property equations of 316fr stainless steel and mod.9cr-1mo steel for sodium-cooled fast reactor to achieve 60-year design life
publisher The Japan Society of Mechanical Engineers
publishDate 2019
url https://doaj.org/article/8cf4fdd04a204b76a12c68405f5a11ab
work_keys_str_mv AT takashionizawa developmentofcreeppropertyequationsof316frstainlesssteelandmod9cr1mosteelforsodiumcooledfastreactortoachieve60yeardesignlife
AT ryutahashidate developmentofcreeppropertyequationsof316frstainlesssteelandmod9cr1mosteelforsodiumcooledfastreactortoachieve60yeardesignlife
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