Zircaloy-Clad Fuel Rod Burst Behavior under Simulated Loss-of-Coolant Condition in Pressurized Water Reactors
To study behaviors of zircaloy-clad fuel during loss-of-coolant accidents in PWR, simulated fuel rods having five pressure levels were heated in steam or vacuum at heating rates between 3 and 47°C/sec. The extent of ballooning of fuel rod is chiefly found within 30 mm from the center of rupture open...
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| Veröffentlicht in: | Journal of nuclear science and technology 1978-10, Vol.15 (10), p.736-744 |
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| container_issue | 10 |
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| container_title | Journal of nuclear science and technology |
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| creator | FURUTA, Teruo KAWASAKI, Satoru HASHIMOTO, Masao OTOMO, Takashi |
| description | To study behaviors of zircaloy-clad fuel during loss-of-coolant accidents in PWR, simulated fuel rods having five pressure levels were heated in steam or vacuum at heating rates between 3 and 47°C/sec. The extent of ballooning of fuel rod is chiefly found within 30 mm from the center of rupture opening. The maximum diametral expansion is mainly related to the burst temperature, as it decreases between about 830°C and about 920°C. The maximum diametral expansions in vacuum are larger than those in steam. The average wall thickness varied with ballooning depends on heating method and atmosphere, and is represented to be about two-third of maximum diametral expansion. Oxide thickness on inner surface is apparently thicker than that on outer, when amount of supplied steam to inner surface is less. The porous thicker inner oxide consists of monoclinic and tetragonal zirconia, and higher hydrogen content is closely associated with the occurrence of tetragonal zirconia. |
| doi_str_mv | 10.1080/18811248.1978.9735581 |
| format | Article |
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The extent of ballooning of fuel rod is chiefly found within 30 mm from the center of rupture opening. The maximum diametral expansion is mainly related to the burst temperature, as it decreases between about 830°C and about 920°C. The maximum diametral expansions in vacuum are larger than those in steam. The average wall thickness varied with ballooning depends on heating method and atmosphere, and is represented to be about two-third of maximum diametral expansion. Oxide thickness on inner surface is apparently thicker than that on outer, when amount of supplied steam to inner surface is less. The porous thicker inner oxide consists of monoclinic and tetragonal zirconia, and higher hydrogen content is closely associated with the occurrence of tetragonal zirconia.</description><identifier>ISSN: 0022-3131</identifier><identifier>EISSN: 1881-1248</identifier><identifier>DOI: 10.1080/18811248.1978.9735581</identifier><language>eng</language><publisher>Tokyo: Taylor & Francis Group</publisher><subject>atmosphere ; burst ; fuel cans ; fuel rods ; heating ; hydrogen ; loss of coolant ; reactor accidents ; steam ; temperature dependence ; thickness ; vacuum states ; zircaloy ; zirconium oxides</subject><ispartof>Journal of nuclear science and technology, 1978-10, Vol.15 (10), p.736-744</ispartof><rights>Copyright Taylor & Francis Group, LLC 1978</rights><rights>Copyright Japan Science and Technology Agency 1978</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c2981-735873e23d49fd2a87297bfc46ce3f129d813eff34282f94f8bf3a0f49ae02e83</citedby><cites>FETCH-LOGICAL-c2981-735873e23d49fd2a87297bfc46ce3f129d813eff34282f94f8bf3a0f49ae02e83</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,776,780,27903,27904</link.rule.ids></links><search><creatorcontrib>FURUTA, Teruo</creatorcontrib><creatorcontrib>KAWASAKI, Satoru</creatorcontrib><creatorcontrib>HASHIMOTO, Masao</creatorcontrib><creatorcontrib>OTOMO, Takashi</creatorcontrib><title>Zircaloy-Clad Fuel Rod Burst Behavior under Simulated Loss-of-Coolant Condition in Pressurized Water Reactors</title><title>Journal of nuclear science and technology</title><description>To study behaviors of zircaloy-clad fuel during loss-of-coolant accidents in PWR, simulated fuel rods having five pressure levels were heated in steam or vacuum at heating rates between 3 and 47°C/sec. The extent of ballooning of fuel rod is chiefly found within 30 mm from the center of rupture opening. The maximum diametral expansion is mainly related to the burst temperature, as it decreases between about 830°C and about 920°C. The maximum diametral expansions in vacuum are larger than those in steam. The average wall thickness varied with ballooning depends on heating method and atmosphere, and is represented to be about two-third of maximum diametral expansion. Oxide thickness on inner surface is apparently thicker than that on outer, when amount of supplied steam to inner surface is less. The porous thicker inner oxide consists of monoclinic and tetragonal zirconia, and higher hydrogen content is closely associated with the occurrence of tetragonal zirconia.</description><subject>atmosphere</subject><subject>burst</subject><subject>fuel cans</subject><subject>fuel rods</subject><subject>heating</subject><subject>hydrogen</subject><subject>loss of coolant</subject><subject>reactor accidents</subject><subject>steam</subject><subject>temperature dependence</subject><subject>thickness</subject><subject>vacuum states</subject><subject>zircaloy</subject><subject>zirconium oxides</subject><issn>0022-3131</issn><issn>1881-1248</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1978</creationdate><recordtype>article</recordtype><recordid>eNp9UE1LAzEQDaJgrf4EIeB56-aju8lNXawKBaUqgpeQbhJM2W7qZFepv94srVdPw8y892beQ-ic5BOSi_ySCEEI5WJCZCkmsmTTqSAHaDTMs2FxiEZ5TmnGCCPH6CTGVWoLXogRWr97qHUTtlnVaINnvW3wIhh800Ps8I390F8-AO5bYwE_-3Xf6M4aPA8xZsFlVQiNbjtchdb4zocW-xY_gY2xB_-TgG8JDnhhdd0FiKfoyOkm2rN9HaPX2e1LdZ_NH-8equt5VlOZfk4ORMksZYZLZ6gWJZXl0tW8qC1zhEojCLPOMU4FdZI7sXRM545LbXNqBRuji53uBsJnb2OnVqGHNp1UhJeFkJITmlDTHaqGZAesUxvwaw1bRXI1JKv-klVDsmqfbOJd7Xi-dQHW-jtAY1Snt00AB7qtfVTsf4lf22iAQw</recordid><startdate>19781001</startdate><enddate>19781001</enddate><creator>FURUTA, Teruo</creator><creator>KAWASAKI, Satoru</creator><creator>HASHIMOTO, Masao</creator><creator>OTOMO, Takashi</creator><general>Taylor & Francis Group</general><general>Taylor & Francis Ltd</general><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>19781001</creationdate><title>Zircaloy-Clad Fuel Rod Burst Behavior under Simulated Loss-of-Coolant Condition in Pressurized Water Reactors</title><author>FURUTA, Teruo ; KAWASAKI, Satoru ; HASHIMOTO, Masao ; OTOMO, Takashi</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c2981-735873e23d49fd2a87297bfc46ce3f129d813eff34282f94f8bf3a0f49ae02e83</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1978</creationdate><topic>atmosphere</topic><topic>burst</topic><topic>fuel cans</topic><topic>fuel rods</topic><topic>heating</topic><topic>hydrogen</topic><topic>loss of coolant</topic><topic>reactor accidents</topic><topic>steam</topic><topic>temperature dependence</topic><topic>thickness</topic><topic>vacuum states</topic><topic>zircaloy</topic><topic>zirconium oxides</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>FURUTA, Teruo</creatorcontrib><creatorcontrib>KAWASAKI, Satoru</creatorcontrib><creatorcontrib>HASHIMOTO, Masao</creatorcontrib><creatorcontrib>OTOMO, Takashi</creatorcontrib><collection>CrossRef</collection><jtitle>Journal of nuclear science and technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>FURUTA, Teruo</au><au>KAWASAKI, Satoru</au><au>HASHIMOTO, Masao</au><au>OTOMO, Takashi</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Zircaloy-Clad Fuel Rod Burst Behavior under Simulated Loss-of-Coolant Condition in Pressurized Water Reactors</atitle><jtitle>Journal of nuclear science and technology</jtitle><date>1978-10-01</date><risdate>1978</risdate><volume>15</volume><issue>10</issue><spage>736</spage><epage>744</epage><pages>736-744</pages><issn>0022-3131</issn><eissn>1881-1248</eissn><abstract>To study behaviors of zircaloy-clad fuel during loss-of-coolant accidents in PWR, simulated fuel rods having five pressure levels were heated in steam or vacuum at heating rates between 3 and 47°C/sec. The extent of ballooning of fuel rod is chiefly found within 30 mm from the center of rupture opening. The maximum diametral expansion is mainly related to the burst temperature, as it decreases between about 830°C and about 920°C. The maximum diametral expansions in vacuum are larger than those in steam. The average wall thickness varied with ballooning depends on heating method and atmosphere, and is represented to be about two-third of maximum diametral expansion. Oxide thickness on inner surface is apparently thicker than that on outer, when amount of supplied steam to inner surface is less. The porous thicker inner oxide consists of monoclinic and tetragonal zirconia, and higher hydrogen content is closely associated with the occurrence of tetragonal zirconia.</abstract><cop>Tokyo</cop><pub>Taylor & Francis Group</pub><doi>10.1080/18811248.1978.9735581</doi><tpages>9</tpages><oa>free_for_read</oa></addata></record> |
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| ispartof | Journal of nuclear science and technology, 1978-10, Vol.15 (10), p.736-744 |
| issn | 0022-3131 1881-1248 |
| language | eng |
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| source | Elektronische Zeitschriftenbibliothek - Frei zugängliche E-Journals; J-STAGE (Japan Science & Technology Information Aggregator, Electronic) Freely Available Titles - Japanese; Alma/SFX Local Collection; Free Full-Text Journals in Chemistry |
| subjects | atmosphere burst fuel cans fuel rods heating hydrogen loss of coolant reactor accidents steam temperature dependence thickness vacuum states zircaloy zirconium oxides |
| title | Zircaloy-Clad Fuel Rod Burst Behavior under Simulated Loss-of-Coolant Condition in Pressurized Water Reactors |
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