Fuel Element Transfer Cask Modelling Using MCNP Technique
After operating for more than 25 years, some of the Reaktor TRIGA Puspati (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank....
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| creator | Darmawan, Rosli Topah, Budiman Nairn |
| description | After operating for more than 25 years, some of the Reaktor TRIGA Puspati (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement. |
| doi_str_mv | 10.1063/1.3295593 |
| format | Conference Proceeding |
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A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement.</description><identifier>ISSN: 0094-243X</identifier><identifier>ISBN: 0735407398</identifier><identifier>ISBN: 9780735407398</identifier><identifier>EISSN: 1551-7616</identifier><identifier>DOI: 10.1063/1.3295593</identifier><language>eng</language><publisher>United States</publisher><subject>CALCULATION METHODS ; ENERGY SOURCES ; ENRICHED URANIUM REACTORS ; FUEL ELEMENTS ; FUELS ; HOMOGENEOUS REACTORS ; HYDRIDE MODERATED REACTORS ; MATERIALS ; MONTE CARLO METHOD ; NUCLEAR FUELS ; REACTOR COMPONENTS ; REACTOR FUELING ; REACTOR MATERIALS ; REACTORS ; RECOMMENDATIONS ; RESEARCH AND TEST REACTORS ; SHIELDING ; SIMULATION ; SOLID HOMOGENEOUS REACTORS ; SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS ; SPENT FUELS ; TRIGA TYPE REACTORS ; WATER COOLED REACTORS ; WATER MODERATED REACTORS</subject><ispartof>AIP conference proceedings, 2009, Vol.1202 (1), p.175-180</ispartof><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>230,314,780,784,885,27923,27924</link.rule.ids><backlink>$$Uhttps://www.osti.gov/biblio/21366878$$D View this record in Osti.gov$$Hfree_for_read</backlink></links><search><creatorcontrib>Darmawan, Rosli</creatorcontrib><creatorcontrib>Topah, Budiman Nairn</creatorcontrib><title>Fuel Element Transfer Cask Modelling Using MCNP Technique</title><title>AIP conference proceedings</title><description>After operating for more than 25 years, some of the Reaktor TRIGA Puspati (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement.</description><subject>CALCULATION METHODS</subject><subject>ENERGY SOURCES</subject><subject>ENRICHED URANIUM REACTORS</subject><subject>FUEL ELEMENTS</subject><subject>FUELS</subject><subject>HOMOGENEOUS REACTORS</subject><subject>HYDRIDE MODERATED REACTORS</subject><subject>MATERIALS</subject><subject>MONTE CARLO METHOD</subject><subject>NUCLEAR FUELS</subject><subject>REACTOR COMPONENTS</subject><subject>REACTOR FUELING</subject><subject>REACTOR MATERIALS</subject><subject>REACTORS</subject><subject>RECOMMENDATIONS</subject><subject>RESEARCH AND TEST REACTORS</subject><subject>SHIELDING</subject><subject>SIMULATION</subject><subject>SOLID HOMOGENEOUS REACTORS</subject><subject>SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS</subject><subject>SPENT FUELS</subject><subject>TRIGA TYPE REACTORS</subject><subject>WATER COOLED REACTORS</subject><subject>WATER MODERATED REACTORS</subject><issn>0094-243X</issn><issn>1551-7616</issn><isbn>0735407398</isbn><isbn>9780735407398</isbn><fulltext>true</fulltext><rsrctype>conference_proceeding</rsrctype><creationdate>2009</creationdate><recordtype>conference_proceeding</recordtype><recordid>eNotjrtOw0AQRVc8JJJAwR9YoqBy2NnZZ4msBJASoHAkOstej8HgrMHr_D9GoTm3Obo6jF0DXwLXeAdLFE4phydsBkpBajToUzbnBpWc4OwZm3HuZCokvl2weYyfnAtnjJ0xtz5Ql6w62lMYk3woQ2xoSLIyfiXbvqaua8N7sot_3GbPr0lO_iO0Pwe6ZOdN2UW6-t8F261XefaYbl4enrL7TdoLUGMqvRcVSKmEQe-lr3hTokVV1Vw3aAgbVwGUEomUrTk1iltf1UIZA7quDS7YzfG3j2NbRN-OU4HvQyA_FgJQa2vsZN0ere-hn-LiWOzb6Kf8MlB_iIWRCM5a7fAXzEBWbA</recordid><startdate>20090101</startdate><enddate>20090101</enddate><creator>Darmawan, Rosli</creator><creator>Topah, Budiman Nairn</creator><scope>7U5</scope><scope>8FD</scope><scope>L7M</scope><scope>OTOTI</scope></search><sort><creationdate>20090101</creationdate><title>Fuel Element Transfer Cask Modelling Using MCNP Technique</title><author>Darmawan, Rosli ; Topah, Budiman Nairn</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-o215t-4cc2b1445273cc4cb0fa3835bd06f37e3f9b11a43ee58d0ef508cbd257716dd73</frbrgroupid><rsrctype>conference_proceedings</rsrctype><prefilter>conference_proceedings</prefilter><language>eng</language><creationdate>2009</creationdate><topic>CALCULATION METHODS</topic><topic>ENERGY SOURCES</topic><topic>ENRICHED URANIUM REACTORS</topic><topic>FUEL ELEMENTS</topic><topic>FUELS</topic><topic>HOMOGENEOUS REACTORS</topic><topic>HYDRIDE MODERATED REACTORS</topic><topic>MATERIALS</topic><topic>MONTE CARLO METHOD</topic><topic>NUCLEAR FUELS</topic><topic>REACTOR COMPONENTS</topic><topic>REACTOR FUELING</topic><topic>REACTOR MATERIALS</topic><topic>REACTORS</topic><topic>RECOMMENDATIONS</topic><topic>RESEARCH AND TEST REACTORS</topic><topic>SHIELDING</topic><topic>SIMULATION</topic><topic>SOLID HOMOGENEOUS REACTORS</topic><topic>SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS</topic><topic>SPENT FUELS</topic><topic>TRIGA TYPE REACTORS</topic><topic>WATER COOLED REACTORS</topic><topic>WATER MODERATED REACTORS</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Darmawan, Rosli</creatorcontrib><creatorcontrib>Topah, Budiman Nairn</creatorcontrib><collection>Solid State and Superconductivity Abstracts</collection><collection>Technology Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>OSTI.GOV</collection></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Darmawan, Rosli</au><au>Topah, Budiman Nairn</au><format>book</format><genre>proceeding</genre><ristype>CONF</ristype><atitle>Fuel Element Transfer Cask Modelling Using MCNP Technique</atitle><btitle>AIP conference proceedings</btitle><date>2009-01-01</date><risdate>2009</risdate><volume>1202</volume><issue>1</issue><spage>175</spage><epage>180</epage><pages>175-180</pages><issn>0094-243X</issn><eissn>1551-7616</eissn><isbn>0735407398</isbn><isbn>9780735407398</isbn><abstract>After operating for more than 25 years, some of the Reaktor TRIGA Puspati (RTP) fuel elements would have been depleted. A few addition and fuel reconfiguration exercises have to be conducted in order to maintain RTP capacity. Presently, RTP spent fuels are stored at the storage area inside RTP tank. The need to transfer the fuel element outside of RTP tank may be prevalence in the near future. The preparation shall be started from now. A fuel element transfer cask has been designed according to the recommendation by the fuel manufacturer and experience of other countries. A modelling using MCNP code has been conducted to analyse the design. The result shows that the design of transfer cask fuel element is safe for handling outside the RTP tank according to recent regulatory requirement.</abstract><cop>United States</cop><doi>10.1063/1.3295593</doi><tpages>6</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0094-243X |
| ispartof | AIP conference proceedings, 2009, Vol.1202 (1), p.175-180 |
| issn | 0094-243X 1551-7616 |
| language | eng |
| recordid | cdi_osti_scitechconnect_21366878 |
| source | AIP Journals Complete |
| subjects | CALCULATION METHODS ENERGY SOURCES ENRICHED URANIUM REACTORS FUEL ELEMENTS FUELS HOMOGENEOUS REACTORS HYDRIDE MODERATED REACTORS MATERIALS MONTE CARLO METHOD NUCLEAR FUELS REACTOR COMPONENTS REACTOR FUELING REACTOR MATERIALS REACTORS RECOMMENDATIONS RESEARCH AND TEST REACTORS SHIELDING SIMULATION SOLID HOMOGENEOUS REACTORS SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS SPENT FUELS TRIGA TYPE REACTORS WATER COOLED REACTORS WATER MODERATED REACTORS |
| title | Fuel Element Transfer Cask Modelling Using MCNP Technique |
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