Fracture analysis of the set-in nozzle of a PWR reactor pressure vessel – Part 1: Determination of critical crack
•The SIFs of the corner cracks are provided under accidental conditions of the PWR.•The material’s embrittlement due to nuclear environment is presented.•The critical crack depth at the nozzle-cylinder intersection is determined. In this study, fracture mechanics analysis of the set-in nozzle of a r...
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| Veröffentlicht in: | Engineering fracture mechanics 2018-04, Vol.192, p.343-361 |
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| container_title | Engineering fracture mechanics |
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| creator | Murtaza, Usman Tariq Javed Hyder, M. |
| description | •The SIFs of the corner cracks are provided under accidental conditions of the PWR.•The material’s embrittlement due to nuclear environment is presented.•The critical crack depth at the nozzle-cylinder intersection is determined.
In this study, fracture mechanics analysis of the set-in nozzle of a reactor pressure vessel (RPV) is being presented. The selected RPV belongs to a 300MW pressurized water reactor (PWR). For the purpose, a wide range of elliptical surface cracks was analyzed at the nozzle-cylinder intersection under two accidental conditions of the reactor: small-break loss of coolant accident (SB-LOCA), and Rancho-Seco transient (RST). It has been demonstrated that at the location being investigated ‘a=0.05t’ is the critical crack depth; where ‘a’ is the depth/minor axis of the crack and ‘t’ is the thickness of the wall. |
| doi_str_mv | 10.1016/j.engfracmech.2016.03.049 |
| format | Article |
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In this study, fracture mechanics analysis of the set-in nozzle of a reactor pressure vessel (RPV) is being presented. The selected RPV belongs to a 300MW pressurized water reactor (PWR). For the purpose, a wide range of elliptical surface cracks was analyzed at the nozzle-cylinder intersection under two accidental conditions of the reactor: small-break loss of coolant accident (SB-LOCA), and Rancho-Seco transient (RST). It has been demonstrated that at the location being investigated ‘a=0.05t’ is the critical crack depth; where ‘a’ is the depth/minor axis of the crack and ‘t’ is the thickness of the wall.</description><identifier>ISSN: 0013-7944</identifier><identifier>EISSN: 1873-7315</identifier><identifier>DOI: 10.1016/j.engfracmech.2016.03.049</identifier><language>eng</language><publisher>New York: Elsevier Ltd</publisher><subject>Cracks ; Cylinders ; Fracture mechanics ; Fractures ; Loss of coolant accidents ; Nozzles ; Pressure vessels ; Pressurized water ; Pressurized water reactors ; RPV ; RST ; SB-LOCA ; Set-in nozzle ; Surface cracks ; Wall thickness</subject><ispartof>Engineering fracture mechanics, 2018-04, Vol.192, p.343-361</ispartof><rights>2016 Elsevier Ltd</rights><rights>Copyright Elsevier BV Apr 1, 2018</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c402t-efd20a87ea746677b71f13077de2a6bf8e677a05be234b739720f1d3ce04a7873</citedby><cites>FETCH-LOGICAL-c402t-efd20a87ea746677b71f13077de2a6bf8e677a05be234b739720f1d3ce04a7873</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.engfracmech.2016.03.049$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>315,781,785,3551,27928,27929,45999</link.rule.ids></links><search><creatorcontrib>Murtaza, Usman Tariq</creatorcontrib><creatorcontrib>Javed Hyder, M.</creatorcontrib><title>Fracture analysis of the set-in nozzle of a PWR reactor pressure vessel – Part 1: Determination of critical crack</title><title>Engineering fracture mechanics</title><description>•The SIFs of the corner cracks are provided under accidental conditions of the PWR.•The material’s embrittlement due to nuclear environment is presented.•The critical crack depth at the nozzle-cylinder intersection is determined.
In this study, fracture mechanics analysis of the set-in nozzle of a reactor pressure vessel (RPV) is being presented. The selected RPV belongs to a 300MW pressurized water reactor (PWR). For the purpose, a wide range of elliptical surface cracks was analyzed at the nozzle-cylinder intersection under two accidental conditions of the reactor: small-break loss of coolant accident (SB-LOCA), and Rancho-Seco transient (RST). It has been demonstrated that at the location being investigated ‘a=0.05t’ is the critical crack depth; where ‘a’ is the depth/minor axis of the crack and ‘t’ is the thickness of the wall.</description><subject>Cracks</subject><subject>Cylinders</subject><subject>Fracture mechanics</subject><subject>Fractures</subject><subject>Loss of coolant accidents</subject><subject>Nozzles</subject><subject>Pressure vessels</subject><subject>Pressurized water</subject><subject>Pressurized water reactors</subject><subject>RPV</subject><subject>RST</subject><subject>SB-LOCA</subject><subject>Set-in nozzle</subject><subject>Surface cracks</subject><subject>Wall thickness</subject><issn>0013-7944</issn><issn>1873-7315</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNqNkMFOwzAQRC0EEqXwD0acE9ZxEifcUKGAVIkKgTharrOhLmlSbLdSe-If-EO-BEflwJHTjkbzVpoh5JxBzIDll4sY27faKr1EPY-TYMXAY0jLAzJgheCR4Cw7JAMAFnSZpsfkxLkFAIi8gAFx48D6tUWqWtVsnXG0q6mfI3XoI9PSttvtGuxNRaevT9RiyHeWriw613ObcLGh359fdKqsp-yK3qBHuzSt8qZre1Rb441WTRBKv5-So1o1Ds9-75C8jG-fR_fR5PHuYXQ9iXQKiY-wrhJQhUAl0jwXYiZYzTgIUWGi8lldYDAVZDNMeDoTvBQJ1KziGiFVInQfkov935XtPtbovFx0axtqOplAniUZL6AIqXKf0rZzzmItV9Ysld1KBrLfWC7kn41lv7EELsPGgR3tWQw1NgatdNpgq7EyFrWXVWf-8eUHzPKMGQ</recordid><startdate>20180401</startdate><enddate>20180401</enddate><creator>Murtaza, Usman Tariq</creator><creator>Javed Hyder, M.</creator><general>Elsevier Ltd</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7SR</scope><scope>7TB</scope><scope>8BQ</scope><scope>8FD</scope><scope>FR3</scope><scope>JG9</scope><scope>KR7</scope></search><sort><creationdate>20180401</creationdate><title>Fracture analysis of the set-in nozzle of a PWR reactor pressure vessel – Part 1: Determination of critical crack</title><author>Murtaza, Usman Tariq ; Javed Hyder, M.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c402t-efd20a87ea746677b71f13077de2a6bf8e677a05be234b739720f1d3ce04a7873</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>Cracks</topic><topic>Cylinders</topic><topic>Fracture mechanics</topic><topic>Fractures</topic><topic>Loss of coolant accidents</topic><topic>Nozzles</topic><topic>Pressure vessels</topic><topic>Pressurized water</topic><topic>Pressurized water reactors</topic><topic>RPV</topic><topic>RST</topic><topic>SB-LOCA</topic><topic>Set-in nozzle</topic><topic>Surface cracks</topic><topic>Wall thickness</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Murtaza, Usman Tariq</creatorcontrib><creatorcontrib>Javed Hyder, M.</creatorcontrib><collection>CrossRef</collection><collection>Engineered Materials Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Civil Engineering Abstracts</collection><jtitle>Engineering fracture mechanics</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Murtaza, Usman Tariq</au><au>Javed Hyder, M.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Fracture analysis of the set-in nozzle of a PWR reactor pressure vessel – Part 1: Determination of critical crack</atitle><jtitle>Engineering fracture mechanics</jtitle><date>2018-04-01</date><risdate>2018</risdate><volume>192</volume><spage>343</spage><epage>361</epage><pages>343-361</pages><issn>0013-7944</issn><eissn>1873-7315</eissn><abstract>•The SIFs of the corner cracks are provided under accidental conditions of the PWR.•The material’s embrittlement due to nuclear environment is presented.•The critical crack depth at the nozzle-cylinder intersection is determined.
In this study, fracture mechanics analysis of the set-in nozzle of a reactor pressure vessel (RPV) is being presented. The selected RPV belongs to a 300MW pressurized water reactor (PWR). For the purpose, a wide range of elliptical surface cracks was analyzed at the nozzle-cylinder intersection under two accidental conditions of the reactor: small-break loss of coolant accident (SB-LOCA), and Rancho-Seco transient (RST). It has been demonstrated that at the location being investigated ‘a=0.05t’ is the critical crack depth; where ‘a’ is the depth/minor axis of the crack and ‘t’ is the thickness of the wall.</abstract><cop>New York</cop><pub>Elsevier Ltd</pub><doi>10.1016/j.engfracmech.2016.03.049</doi><tpages>19</tpages></addata></record> |
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| ispartof | Engineering fracture mechanics, 2018-04, Vol.192, p.343-361 |
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| language | eng |
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| source | Elsevier ScienceDirect Journals Complete |
| subjects | Cracks Cylinders Fracture mechanics Fractures Loss of coolant accidents Nozzles Pressure vessels Pressurized water Pressurized water reactors RPV RST SB-LOCA Set-in nozzle Surface cracks Wall thickness |
| title | Fracture analysis of the set-in nozzle of a PWR reactor pressure vessel – Part 1: Determination of critical crack |
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