Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor
•IRT MEPhI and IRT-T are pool-type university-based research reactors.•Full 3-D models for these reactors using MCU-PTR Monte Carlo code are developed.•Validation of the MCU-PTR code against experimental data is performed.•The measured critical cases during the calibration of the control rods are an...
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| Veröffentlicht in: | Annals of nuclear energy 2016-10, Vol.96, p.332-343 |
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| creator | Shchurovskaya, M.V. Alferov, V.P. Geraskin, N.I. Radaev, A.I. Naymushin, A.G. Chertkov, Yu.B. Anikin, M.N. Lebedev, I.I. |
| description | •IRT MEPhI and IRT-T are pool-type university-based research reactors.•Full 3-D models for these reactors using MCU-PTR Monte Carlo code are developed.•Validation of the MCU-PTR code against experimental data is performed.•The measured critical cases during the calibration of the control rods are analyzed.•Satisfactory agreement with the experimental results was found.
This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at the National Research Nuclear University MEPhI and the IRT-T reactor at the National Research Tomsk Polytechnic University. Calculations were performed using the continuous energy Monte Carlo code MCU-PTR. Full 3-D models for the IRT MEPhI and IRT-T reactors were developed. Measured critical cases during the control rod calibrations are analyzed in benchmarking studies. A procedure for the comparison of the measured and the calculated control rod worth based on the detailed calibration simulation is proposed. |
| doi_str_mv | 10.1016/j.anucene.2016.06.015 |
| format | Article |
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This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at the National Research Nuclear University MEPhI and the IRT-T reactor at the National Research Tomsk Polytechnic University. Calculations were performed using the continuous energy Monte Carlo code MCU-PTR. Full 3-D models for the IRT MEPhI and IRT-T reactors were developed. Measured critical cases during the control rod calibrations are analyzed in benchmarking studies. A procedure for the comparison of the measured and the calculated control rod worth based on the detailed calibration simulation is proposed.</description><identifier>ISSN: 0306-4549</identifier><identifier>EISSN: 1873-2100</identifier><identifier>DOI: 10.1016/j.anucene.2016.06.015</identifier><language>eng</language><publisher>Elsevier Ltd</publisher><subject>Calibration ; Computer simulation ; Control rods ; Control rods calibration ; MCU-PTR code ; Monte Carlo code ; Nuclear engineering ; Nuclear power generation ; Nuclear reactor components ; Nuclear reactors ; Nuclear research reactors ; Research reactor ; Validation of neutronics codes</subject><ispartof>Annals of nuclear energy, 2016-10, Vol.96, p.332-343</ispartof><rights>2016 Elsevier Ltd</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c475t-5777d76130960bb367872c194dd96b1afcaf2f7af166fc63221567feec9908623</citedby><cites>FETCH-LOGICAL-c475t-5777d76130960bb367872c194dd96b1afcaf2f7af166fc63221567feec9908623</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://dx.doi.org/10.1016/j.anucene.2016.06.015$$EHTML$$P50$$Gelsevier$$H</linktohtml><link.rule.ids>314,777,781,3537,27905,27906,45976</link.rule.ids></links><search><creatorcontrib>Shchurovskaya, M.V.</creatorcontrib><creatorcontrib>Alferov, V.P.</creatorcontrib><creatorcontrib>Geraskin, N.I.</creatorcontrib><creatorcontrib>Radaev, A.I.</creatorcontrib><creatorcontrib>Naymushin, A.G.</creatorcontrib><creatorcontrib>Chertkov, Yu.B.</creatorcontrib><creatorcontrib>Anikin, M.N.</creatorcontrib><creatorcontrib>Lebedev, I.I.</creatorcontrib><title>Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor</title><title>Annals of nuclear energy</title><description>•IRT MEPhI and IRT-T are pool-type university-based research reactors.•Full 3-D models for these reactors using MCU-PTR Monte Carlo code are developed.•Validation of the MCU-PTR code against experimental data is performed.•The measured critical cases during the calibration of the control rods are analyzed.•Satisfactory agreement with the experimental results was found.
This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at the National Research Nuclear University MEPhI and the IRT-T reactor at the National Research Tomsk Polytechnic University. Calculations were performed using the continuous energy Monte Carlo code MCU-PTR. Full 3-D models for the IRT MEPhI and IRT-T reactors were developed. Measured critical cases during the control rod calibrations are analyzed in benchmarking studies. A procedure for the comparison of the measured and the calculated control rod worth based on the detailed calibration simulation is proposed.</description><subject>Calibration</subject><subject>Computer simulation</subject><subject>Control rods</subject><subject>Control rods calibration</subject><subject>MCU-PTR code</subject><subject>Monte Carlo code</subject><subject>Nuclear engineering</subject><subject>Nuclear power generation</subject><subject>Nuclear reactor components</subject><subject>Nuclear reactors</subject><subject>Nuclear research reactors</subject><subject>Research reactor</subject><subject>Validation of neutronics codes</subject><issn>0306-4549</issn><issn>1873-2100</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2016</creationdate><recordtype>article</recordtype><recordid>eNqNkE9LAzEQxYMoWKsfQcjRy9ZMdpPsnkSKfwoVQerJQ8hmJzZlu6nJrtBv75Z6V3gwM_B7D-YRcg1sBgzk7WZmusFihzM-njM2CsQJmUCp8owDY6dkwnIms0IU1Tm5SGnDGPCyKCbkYx66PoaWxtBQa1pfR9P70NHkt0N7XIfku0_6MoJI5ya2gdrQIHUh0n6NdPG2yvr9DmnEhCba9bgY24d4Sc6caRNe_c4peX98WM2fs-Xr02J-v8xsoUSfCaVUoyTkrJKsrnOpSsUtVEXTVLIG46xx3CnjQEpnZc45CKkcoq0qVkqeT8nNMXcXw9eAqddbnyy2rekwDElDyYWQQij4BzomAldSjKg4ojaGlCI6vYt-a-JeA9OH3vVG__auD71rNgoOvrujD8eXvz1GnazHzmLjI9peN8H_kfADr8iN9w</recordid><startdate>20161001</startdate><enddate>20161001</enddate><creator>Shchurovskaya, M.V.</creator><creator>Alferov, V.P.</creator><creator>Geraskin, N.I.</creator><creator>Radaev, A.I.</creator><creator>Naymushin, A.G.</creator><creator>Chertkov, Yu.B.</creator><creator>Anikin, M.N.</creator><creator>Lebedev, I.I.</creator><general>Elsevier Ltd</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7ST</scope><scope>C1K</scope><scope>SOI</scope><scope>7SP</scope><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20161001</creationdate><title>Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor</title><author>Shchurovskaya, M.V. ; Alferov, V.P. ; Geraskin, N.I. ; Radaev, A.I. ; Naymushin, A.G. ; Chertkov, Yu.B. ; Anikin, M.N. ; Lebedev, I.I.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c475t-5777d76130960bb367872c194dd96b1afcaf2f7af166fc63221567feec9908623</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2016</creationdate><topic>Calibration</topic><topic>Computer simulation</topic><topic>Control rods</topic><topic>Control rods calibration</topic><topic>MCU-PTR code</topic><topic>Monte Carlo code</topic><topic>Nuclear engineering</topic><topic>Nuclear power generation</topic><topic>Nuclear reactor components</topic><topic>Nuclear reactors</topic><topic>Nuclear research reactors</topic><topic>Research reactor</topic><topic>Validation of neutronics codes</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Shchurovskaya, M.V.</creatorcontrib><creatorcontrib>Alferov, V.P.</creatorcontrib><creatorcontrib>Geraskin, N.I.</creatorcontrib><creatorcontrib>Radaev, A.I.</creatorcontrib><creatorcontrib>Naymushin, A.G.</creatorcontrib><creatorcontrib>Chertkov, Yu.B.</creatorcontrib><creatorcontrib>Anikin, M.N.</creatorcontrib><creatorcontrib>Lebedev, I.I.</creatorcontrib><collection>CrossRef</collection><collection>Environment Abstracts</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Environment Abstracts</collection><collection>Electronics & Communications Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Annals of nuclear energy</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Shchurovskaya, M.V.</au><au>Alferov, V.P.</au><au>Geraskin, N.I.</au><au>Radaev, A.I.</au><au>Naymushin, A.G.</au><au>Chertkov, Yu.B.</au><au>Anikin, M.N.</au><au>Lebedev, I.I.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor</atitle><jtitle>Annals of nuclear energy</jtitle><date>2016-10-01</date><risdate>2016</risdate><volume>96</volume><spage>332</spage><epage>343</epage><pages>332-343</pages><issn>0306-4549</issn><eissn>1873-2100</eissn><abstract>•IRT MEPhI and IRT-T are pool-type university-based research reactors.•Full 3-D models for these reactors using MCU-PTR Monte Carlo code are developed.•Validation of the MCU-PTR code against experimental data is performed.•The measured critical cases during the calibration of the control rods are analyzed.•Satisfactory agreement with the experimental results was found.
This paper presents the results of the validation of a research reactor calculation using Monte Carlo code against experimental data. Validation efforts are carried out for two university-based research reactors in Russia: the IRT MEPhI reactor at the National Research Nuclear University MEPhI and the IRT-T reactor at the National Research Tomsk Polytechnic University. Calculations were performed using the continuous energy Monte Carlo code MCU-PTR. Full 3-D models for the IRT MEPhI and IRT-T reactors were developed. Measured critical cases during the control rod calibrations are analyzed in benchmarking studies. A procedure for the comparison of the measured and the calculated control rod worth based on the detailed calibration simulation is proposed.</abstract><pub>Elsevier Ltd</pub><doi>10.1016/j.anucene.2016.06.015</doi><tpages>12</tpages><oa>free_for_read</oa></addata></record> |
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| ispartof | Annals of nuclear energy, 2016-10, Vol.96, p.332-343 |
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| language | eng |
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| source | Elsevier ScienceDirect Journals |
| subjects | Calibration Computer simulation Control rods Control rods calibration MCU-PTR code Monte Carlo code Nuclear engineering Nuclear power generation Nuclear reactor components Nuclear reactors Nuclear research reactors Research reactor Validation of neutronics codes |
| title | Control rod calibration simulation using Monte Carlo code for the IRT-type research reactor |
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