Loading…
Time–temperature-sensitization diagrams and critical cooling rates of different nitrogen containing austenitic stainless steels
Nitrogen-alloyed 316L stainless steel is being used as structural material for high temperature fast breeder reactor components with a design life of 40 years. With a view to increase the design life to 60 years and beyond, high nitrogen stainless steels are being considered for certain critical com...
Saved in:
Published in: | Journal of nuclear materials 2010-04, Vol.399 (1), p.62-67 |
---|---|
Main Authors: | , |
Format: | Article |
Language: | English |
Subjects: | |
Citations: | Items that this one cites Items that cite this one |
Online Access: | Get full text |
Tags: |
Add Tag
No Tags, Be the first to tag this record!
|
cited_by | cdi_FETCH-LOGICAL-c438t-25e92216a81cfa0b52d7a908e91ab829f2ae7559ca09b31b0d02f14825e7555f3 |
---|---|
cites | cdi_FETCH-LOGICAL-c438t-25e92216a81cfa0b52d7a908e91ab829f2ae7559ca09b31b0d02f14825e7555f3 |
container_end_page | 67 |
container_issue | 1 |
container_start_page | 62 |
container_title | Journal of nuclear materials |
container_volume | 399 |
creator | Parvathavarthini, N. Dayal, R.K. |
description | Nitrogen-alloyed 316L stainless steel is being used as structural material for high temperature fast breeder reactor components with a design life of 40
years. With a view to increase the design life to 60
years and beyond, high nitrogen stainless steels are being considered for certain critical components which may be used at high temperatures. Since carbon and nitrogen have major influence on the sensitization kinetics, investigations were carried out to establish the sensitization behaviour of four heats of 316L SS containing (i) 0.07%N and 0.035%C, (ii) 0.120%N and 0.030%C, (iii) 0.150%N and 0.025%C and (iv) 0.22%N and 0.035%C. These stainless steels were subjected to heat treatments in the temperature range of 823–1023
K for various durations ranging from 1
h to 500
h. Using ASTM standard A262 Practice A and E tests, time–temperature-sensitization diagrams were constructed and from these diagrams, critical cooling rate above which there is no risk of sensitization was calculated. The data established in this work can be used to select optimum heat treatment parameters during heat treatments of fabricated components for fast reactors. |
doi_str_mv | 10.1016/j.jnucmat.2010.01.003 |
format | article |
fullrecord | <record><control><sourceid>proquest_cross</sourceid><recordid>TN_cdi_proquest_miscellaneous_1671308792</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><els_id>S0022311510000048</els_id><sourcerecordid>1671308792</sourcerecordid><originalsourceid>FETCH-LOGICAL-c438t-25e92216a81cfa0b52d7a908e91ab829f2ae7559ca09b31b0d02f14825e7555f3</originalsourceid><addsrcrecordid>eNqFkM-KFDEQh4O44LjrIyz0RfDSs5X0pv-cRBZXhQUv6znUpCtDhu5kTKUFPekz7Bv6JKaZweueEn75finqE-JawlaCbG8O20NY7Ix5q6BkILcAzQuxkX3X1Le9gpdiA6BU3UipX4nXzAcA0APojfjz6Gf6-_sp03ykhHlJVDMF9tn_wuxjqEaP-4QzVxjGyqbyYHGqbIyTD_uqVIir6ArmHCUKuQo-p7inUJiQ0YcVw4UzhbVb8ZpNxFxuRBNfiQuHE9Ob83kpvt1_fLz7XD98_fTl7sNDbW-bPtdK06CUbLGX1iHstBo7HKCnQeKuV4NTSJ3Wg0UYdo3cwQjKybK9XmPtmkvx7vTvMcXvC3E2s2dL04SB4sJGtp1soO8GVVB9Qm2KzImcOSY_Y_ppJJhVuTmYs3KzKjcgTVFeem_PI5CLJJcwWM__y0q1vWxlW7j3J66sTz88JcPWU7A0-kQ2mzH6Zyb9AzaWnlw</addsrcrecordid><sourcetype>Aggregation Database</sourcetype><iscdi>true</iscdi><recordtype>article</recordtype><pqid>1671308792</pqid></control><display><type>article</type><title>Time–temperature-sensitization diagrams and critical cooling rates of different nitrogen containing austenitic stainless steels</title><source>Elsevier</source><creator>Parvathavarthini, N. ; Dayal, R.K.</creator><creatorcontrib>Parvathavarthini, N. ; Dayal, R.K.</creatorcontrib><description>Nitrogen-alloyed 316L stainless steel is being used as structural material for high temperature fast breeder reactor components with a design life of 40
years. With a view to increase the design life to 60
years and beyond, high nitrogen stainless steels are being considered for certain critical components which may be used at high temperatures. Since carbon and nitrogen have major influence on the sensitization kinetics, investigations were carried out to establish the sensitization behaviour of four heats of 316L SS containing (i) 0.07%N and 0.035%C, (ii) 0.120%N and 0.030%C, (iii) 0.150%N and 0.025%C and (iv) 0.22%N and 0.035%C. These stainless steels were subjected to heat treatments in the temperature range of 823–1023
K for various durations ranging from 1
h to 500
h. Using ASTM standard A262 Practice A and E tests, time–temperature-sensitization diagrams were constructed and from these diagrams, critical cooling rate above which there is no risk of sensitization was calculated. The data established in this work can be used to select optimum heat treatment parameters during heat treatments of fabricated components for fast reactors.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2010.01.003</identifier><identifier>CODEN: JNUMAM</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Applied sciences ; Austenitic stainless steel ; Austenitic stainless steels ; Controled nuclear fusion plants ; Cooling rate ; Critical cooling rates ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Fuels ; Heat resistant steels ; Heat treatment ; Installations for energy generation and conversion: thermal and electrical energy ; Nuclear engineering ; Nuclear fuels ; Nuclear power generation ; Nuclear reactor components ; Nuclear reactors ; Sensitization ; Stainless steels ; TTS diagrams</subject><ispartof>Journal of nuclear materials, 2010-04, Vol.399 (1), p.62-67</ispartof><rights>2010 Elsevier B.V.</rights><rights>2015 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c438t-25e92216a81cfa0b52d7a908e91ab829f2ae7559ca09b31b0d02f14825e7555f3</citedby><cites>FETCH-LOGICAL-c438t-25e92216a81cfa0b52d7a908e91ab829f2ae7559ca09b31b0d02f14825e7555f3</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27923,27924</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=22681616$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Parvathavarthini, N.</creatorcontrib><creatorcontrib>Dayal, R.K.</creatorcontrib><title>Time–temperature-sensitization diagrams and critical cooling rates of different nitrogen containing austenitic stainless steels</title><title>Journal of nuclear materials</title><description>Nitrogen-alloyed 316L stainless steel is being used as structural material for high temperature fast breeder reactor components with a design life of 40
years. With a view to increase the design life to 60
years and beyond, high nitrogen stainless steels are being considered for certain critical components which may be used at high temperatures. Since carbon and nitrogen have major influence on the sensitization kinetics, investigations were carried out to establish the sensitization behaviour of four heats of 316L SS containing (i) 0.07%N and 0.035%C, (ii) 0.120%N and 0.030%C, (iii) 0.150%N and 0.025%C and (iv) 0.22%N and 0.035%C. These stainless steels were subjected to heat treatments in the temperature range of 823–1023
K for various durations ranging from 1
h to 500
h. Using ASTM standard A262 Practice A and E tests, time–temperature-sensitization diagrams were constructed and from these diagrams, critical cooling rate above which there is no risk of sensitization was calculated. The data established in this work can be used to select optimum heat treatment parameters during heat treatments of fabricated components for fast reactors.</description><subject>Applied sciences</subject><subject>Austenitic stainless steel</subject><subject>Austenitic stainless steels</subject><subject>Controled nuclear fusion plants</subject><subject>Cooling rate</subject><subject>Critical cooling rates</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Fuels</subject><subject>Heat resistant steels</subject><subject>Heat treatment</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Nuclear engineering</subject><subject>Nuclear fuels</subject><subject>Nuclear power generation</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Sensitization</subject><subject>Stainless steels</subject><subject>TTS diagrams</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2010</creationdate><recordtype>article</recordtype><recordid>eNqFkM-KFDEQh4O44LjrIyz0RfDSs5X0pv-cRBZXhQUv6znUpCtDhu5kTKUFPekz7Bv6JKaZweueEn75finqE-JawlaCbG8O20NY7Ix5q6BkILcAzQuxkX3X1Le9gpdiA6BU3UipX4nXzAcA0APojfjz6Gf6-_sp03ykhHlJVDMF9tn_wuxjqEaP-4QzVxjGyqbyYHGqbIyTD_uqVIir6ArmHCUKuQo-p7inUJiQ0YcVw4UzhbVb8ZpNxFxuRBNfiQuHE9Ob83kpvt1_fLz7XD98_fTl7sNDbW-bPtdK06CUbLGX1iHstBo7HKCnQeKuV4NTSJ3Wg0UYdo3cwQjKybK9XmPtmkvx7vTvMcXvC3E2s2dL04SB4sJGtp1soO8GVVB9Qm2KzImcOSY_Y_ppJJhVuTmYs3KzKjcgTVFeem_PI5CLJJcwWM__y0q1vWxlW7j3J66sTz88JcPWU7A0-kQ2mzH6Zyb9AzaWnlw</recordid><startdate>20100401</startdate><enddate>20100401</enddate><creator>Parvathavarthini, N.</creator><creator>Dayal, R.K.</creator><general>Elsevier B.V</general><general>Elsevier</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7SR</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope></search><sort><creationdate>20100401</creationdate><title>Time–temperature-sensitization diagrams and critical cooling rates of different nitrogen containing austenitic stainless steels</title><author>Parvathavarthini, N. ; Dayal, R.K.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c438t-25e92216a81cfa0b52d7a908e91ab829f2ae7559ca09b31b0d02f14825e7555f3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2010</creationdate><topic>Applied sciences</topic><topic>Austenitic stainless steel</topic><topic>Austenitic stainless steels</topic><topic>Controled nuclear fusion plants</topic><topic>Cooling rate</topic><topic>Critical cooling rates</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Fuels</topic><topic>Heat resistant steels</topic><topic>Heat treatment</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Nuclear engineering</topic><topic>Nuclear fuels</topic><topic>Nuclear power generation</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Sensitization</topic><topic>Stainless steels</topic><topic>TTS diagrams</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Parvathavarthini, N.</creatorcontrib><creatorcontrib>Dayal, R.K.</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Parvathavarthini, N.</au><au>Dayal, R.K.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Time–temperature-sensitization diagrams and critical cooling rates of different nitrogen containing austenitic stainless steels</atitle><jtitle>Journal of nuclear materials</jtitle><date>2010-04-01</date><risdate>2010</risdate><volume>399</volume><issue>1</issue><spage>62</spage><epage>67</epage><pages>62-67</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><coden>JNUMAM</coden><abstract>Nitrogen-alloyed 316L stainless steel is being used as structural material for high temperature fast breeder reactor components with a design life of 40
years. With a view to increase the design life to 60
years and beyond, high nitrogen stainless steels are being considered for certain critical components which may be used at high temperatures. Since carbon and nitrogen have major influence on the sensitization kinetics, investigations were carried out to establish the sensitization behaviour of four heats of 316L SS containing (i) 0.07%N and 0.035%C, (ii) 0.120%N and 0.030%C, (iii) 0.150%N and 0.025%C and (iv) 0.22%N and 0.035%C. These stainless steels were subjected to heat treatments in the temperature range of 823–1023
K for various durations ranging from 1
h to 500
h. Using ASTM standard A262 Practice A and E tests, time–temperature-sensitization diagrams were constructed and from these diagrams, critical cooling rate above which there is no risk of sensitization was calculated. The data established in this work can be used to select optimum heat treatment parameters during heat treatments of fabricated components for fast reactors.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2010.01.003</doi><tpages>6</tpages></addata></record> |
fulltext | fulltext |
identifier | ISSN: 0022-3115 |
ispartof | Journal of nuclear materials, 2010-04, Vol.399 (1), p.62-67 |
issn | 0022-3115 1873-4820 |
language | eng |
recordid | cdi_proquest_miscellaneous_1671308792 |
source | Elsevier |
subjects | Applied sciences Austenitic stainless steel Austenitic stainless steels Controled nuclear fusion plants Cooling rate Critical cooling rates Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Fuels Heat resistant steels Heat treatment Installations for energy generation and conversion: thermal and electrical energy Nuclear engineering Nuclear fuels Nuclear power generation Nuclear reactor components Nuclear reactors Sensitization Stainless steels TTS diagrams |
title | Time–temperature-sensitization diagrams and critical cooling rates of different nitrogen containing austenitic stainless steels |
url | http://sfxeu10.hosted.exlibrisgroup.com/loughborough?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-08T16%3A58%3A56IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-proquest_cross&rft_val_fmt=info:ofi/fmt:kev:mtx:journal&rft.genre=article&rft.atitle=Time%E2%80%93temperature-sensitization%20diagrams%20and%20critical%20cooling%20rates%20of%20different%20nitrogen%20containing%20austenitic%20stainless%20steels&rft.jtitle=Journal%20of%20nuclear%20materials&rft.au=Parvathavarthini,%20N.&rft.date=2010-04-01&rft.volume=399&rft.issue=1&rft.spage=62&rft.epage=67&rft.pages=62-67&rft.issn=0022-3115&rft.eissn=1873-4820&rft.coden=JNUMAM&rft_id=info:doi/10.1016/j.jnucmat.2010.01.003&rft_dat=%3Cproquest_cross%3E1671308792%3C/proquest_cross%3E%3Cgrp_id%3Ecdi_FETCH-LOGICAL-c438t-25e92216a81cfa0b52d7a908e91ab829f2ae7559ca09b31b0d02f14825e7555f3%3C/grp_id%3E%3Coa%3E%3C/oa%3E%3Curl%3E%3C/url%3E&rft_id=info:oai/&rft_pqid=1671308792&rft_id=info:pmid/&rfr_iscdi=true |