Measurement of the neutron capture cross-section of [sup.238]U using the neutron activation technique
The [sup.238]U(n, γ)[sup.239]U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the [sup.7]Li(p, n)[sup.7]Be reaction has been determined using activation and off-line y-ray spectrometric technique. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-s...
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Veröffentlicht in: | Journal of radioanalytical and nuclear chemistry 2012-08, Vol.293 (2), p.469 |
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creator | Naik, H Surayanarayana, S.V Mulik, V.K Prajapati, P.M Shivashankar, B.S Jagadeesan, K.C Thakare, S.V Raj, D Sharma, S.C Bhagwat, P.V Dhole, S.D Ganesan, S Bhoraskar, V.N Goswami, A |
description | The [sup.238]U(n, γ)[sup.239]U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the [sup.7]Li(p, n)[sup.7]Be reaction has been determined using activation and off-line y-ray spectrometric technique. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same [sup.7]Li(p, n)[sup.7]Be reaction have been also determined using the above technique. The experimentally determined [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237U reaction cross-sections were compared with the evaluated data of ENDF/B-VII, JENDL-4.0, JEFF-3.1 and CENDL-3.1. The experimental values were found to be in general agreement with the evaluated value based on ENDF/B-VII, and JENDL-4.0 but not with the JEFF-3.1 and CENDL-3.1. The present data along with literature data in a wide range of neutron energies were interpreted in terms of competition between different reaction channels including fission. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were also found to be in agreement experimental data. Keywords [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections * [sup.7]Li(p, n)[sup.7]Be reaction * Average neutron energy * [E.sub.n] = 3.7 ± 0.3 MeV and 9.85 ± 0.38 MeV * Off-line γ-ray spectrometric technique * TALYS calculation |
doi_str_mv | 10.1007/s10967-012-1815-x |
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The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same [sup.7]Li(p, n)[sup.7]Be reaction have been also determined using the above technique. The experimentally determined [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237U reaction cross-sections were compared with the evaluated data of ENDF/B-VII, JENDL-4.0, JEFF-3.1 and CENDL-3.1. The experimental values were found to be in general agreement with the evaluated value based on ENDF/B-VII, and JENDL-4.0 but not with the JEFF-3.1 and CENDL-3.1. The present data along with literature data in a wide range of neutron energies were interpreted in terms of competition between different reaction channels including fission. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were also found to be in agreement experimental data. Keywords [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections * [sup.7]Li(p, n)[sup.7]Be reaction * Average neutron energy * [E.sub.n] = 3.7 ± 0.3 MeV and 9.85 ± 0.38 MeV * Off-line γ-ray spectrometric technique * TALYS calculation</description><identifier>ISSN: 0236-5731</identifier><identifier>DOI: 10.1007/s10967-012-1815-x</identifier><language>eng</language><publisher>Springer</publisher><subject>Comparative analysis ; Gamma rays ; Measurement ; Methods ; Toy industry ; Uranium</subject><ispartof>Journal of radioanalytical and nuclear chemistry, 2012-08, Vol.293 (2), p.469</ispartof><rights>COPYRIGHT 2012 Springer</rights><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>314,776,780,27903,27904</link.rule.ids></links><search><creatorcontrib>Naik, H</creatorcontrib><creatorcontrib>Surayanarayana, S.V</creatorcontrib><creatorcontrib>Mulik, V.K</creatorcontrib><creatorcontrib>Prajapati, P.M</creatorcontrib><creatorcontrib>Shivashankar, B.S</creatorcontrib><creatorcontrib>Jagadeesan, K.C</creatorcontrib><creatorcontrib>Thakare, S.V</creatorcontrib><creatorcontrib>Raj, D</creatorcontrib><creatorcontrib>Sharma, S.C</creatorcontrib><creatorcontrib>Bhagwat, P.V</creatorcontrib><creatorcontrib>Dhole, S.D</creatorcontrib><creatorcontrib>Ganesan, S</creatorcontrib><creatorcontrib>Bhoraskar, V.N</creatorcontrib><creatorcontrib>Goswami, A</creatorcontrib><title>Measurement of the neutron capture cross-section of [sup.238]U using the neutron activation technique</title><title>Journal of radioanalytical and nuclear chemistry</title><description>The [sup.238]U(n, γ)[sup.239]U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the [sup.7]Li(p, n)[sup.7]Be reaction has been determined using activation and off-line y-ray spectrometric technique. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same [sup.7]Li(p, n)[sup.7]Be reaction have been also determined using the above technique. The experimentally determined [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237U reaction cross-sections were compared with the evaluated data of ENDF/B-VII, JENDL-4.0, JEFF-3.1 and CENDL-3.1. The experimental values were found to be in general agreement with the evaluated value based on ENDF/B-VII, and JENDL-4.0 but not with the JEFF-3.1 and CENDL-3.1. The present data along with literature data in a wide range of neutron energies were interpreted in terms of competition between different reaction channels including fission. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were also found to be in agreement experimental data. Keywords [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections * [sup.7]Li(p, n)[sup.7]Be reaction * Average neutron energy * [E.sub.n] = 3.7 ± 0.3 MeV and 9.85 ± 0.38 MeV * Off-line γ-ray spectrometric technique * TALYS calculation</description><subject>Comparative analysis</subject><subject>Gamma rays</subject><subject>Measurement</subject><subject>Methods</subject><subject>Toy industry</subject><subject>Uranium</subject><issn>0236-5731</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2012</creationdate><recordtype>article</recordtype><sourceid/><recordid>eNpVjk1LAzEQhnNQsFZ_gLf9A1mTTPN1LMUvqHixJxHJJpN2pc3WTVb8-Qb1InN44XmfGYaQK85azpi-zpxZpSnjgnLDJf06ITMmQFGpgZ-R85zfGWPWGJgRfESXpxEPmEozxKbssEk4lXFIjXfHUqvGj0PONKMvfaVVesnTsRVgXjfNlPu0_bflqvbpftSCfpf6jwkvyGl0-4yXfzknm9ub59U9XT_dPayWa7qtLxcKUSm_6Jy1QQS50NoFL6T0TEcuDdrgo-oEuC4EDmphO--FQ8mMRq0hdDAn7e_drdvjW5_iUEbn6wQ89H5IGPvKl6DAMsEMwDdnslyp</recordid><startdate>20120801</startdate><enddate>20120801</enddate><creator>Naik, H</creator><creator>Surayanarayana, S.V</creator><creator>Mulik, V.K</creator><creator>Prajapati, P.M</creator><creator>Shivashankar, B.S</creator><creator>Jagadeesan, K.C</creator><creator>Thakare, S.V</creator><creator>Raj, D</creator><creator>Sharma, S.C</creator><creator>Bhagwat, P.V</creator><creator>Dhole, S.D</creator><creator>Ganesan, S</creator><creator>Bhoraskar, V.N</creator><creator>Goswami, A</creator><general>Springer</general><scope/></search><sort><creationdate>20120801</creationdate><title>Measurement of the neutron capture cross-section of [sup.238]U using the neutron activation technique</title><author>Naik, H ; Surayanarayana, S.V ; Mulik, V.K ; Prajapati, P.M ; Shivashankar, B.S ; Jagadeesan, K.C ; Thakare, S.V ; Raj, D ; Sharma, S.C ; Bhagwat, P.V ; Dhole, S.D ; Ganesan, S ; Bhoraskar, V.N ; Goswami, A</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-g109t-3f66c4ba99d2d5477adc255c07f158e9dcf6b23abdd13649bcc2ae5087e773db3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2012</creationdate><topic>Comparative analysis</topic><topic>Gamma rays</topic><topic>Measurement</topic><topic>Methods</topic><topic>Toy industry</topic><topic>Uranium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Naik, H</creatorcontrib><creatorcontrib>Surayanarayana, S.V</creatorcontrib><creatorcontrib>Mulik, V.K</creatorcontrib><creatorcontrib>Prajapati, P.M</creatorcontrib><creatorcontrib>Shivashankar, B.S</creatorcontrib><creatorcontrib>Jagadeesan, K.C</creatorcontrib><creatorcontrib>Thakare, S.V</creatorcontrib><creatorcontrib>Raj, D</creatorcontrib><creatorcontrib>Sharma, S.C</creatorcontrib><creatorcontrib>Bhagwat, P.V</creatorcontrib><creatorcontrib>Dhole, S.D</creatorcontrib><creatorcontrib>Ganesan, S</creatorcontrib><creatorcontrib>Bhoraskar, V.N</creatorcontrib><creatorcontrib>Goswami, A</creatorcontrib><jtitle>Journal of radioanalytical and nuclear chemistry</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Naik, H</au><au>Surayanarayana, S.V</au><au>Mulik, V.K</au><au>Prajapati, P.M</au><au>Shivashankar, B.S</au><au>Jagadeesan, K.C</au><au>Thakare, S.V</au><au>Raj, D</au><au>Sharma, S.C</au><au>Bhagwat, P.V</au><au>Dhole, S.D</au><au>Ganesan, S</au><au>Bhoraskar, V.N</au><au>Goswami, A</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Measurement of the neutron capture cross-section of [sup.238]U using the neutron activation technique</atitle><jtitle>Journal of radioanalytical and nuclear chemistry</jtitle><date>2012-08-01</date><risdate>2012</risdate><volume>293</volume><issue>2</issue><spage>469</spage><pages>469-</pages><issn>0236-5731</issn><abstract>The [sup.238]U(n, γ)[sup.239]U reaction cross-section at average neutron energy of 3.7 ± 0.3 MeV from the [sup.7]Li(p, n)[sup.7]Be reaction has been determined using activation and off-line y-ray spectrometric technique. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections at average neutron energy of 9.85 ± 0.38 MeV from the same [sup.7]Li(p, n)[sup.7]Be reaction have been also determined using the above technique. The experimentally determined [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237U reaction cross-sections were compared with the evaluated data of ENDF/B-VII, JENDL-4.0, JEFF-3.1 and CENDL-3.1. The experimental values were found to be in general agreement with the evaluated value based on ENDF/B-VII, and JENDL-4.0 but not with the JEFF-3.1 and CENDL-3.1. The present data along with literature data in a wide range of neutron energies were interpreted in terms of competition between different reaction channels including fission. The [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections were also calculated theoretically using the TALYS 1.2 computer code and were also found to be in agreement experimental data. Keywords [sup.238]U(n, γ)[sup.239]U and [sup.238]U(n, 2n)[sup.237]U reaction cross-sections * [sup.7]Li(p, n)[sup.7]Be reaction * Average neutron energy * [E.sub.n] = 3.7 ± 0.3 MeV and 9.85 ± 0.38 MeV * Off-line γ-ray spectrometric technique * TALYS calculation</abstract><pub>Springer</pub><doi>10.1007/s10967-012-1815-x</doi></addata></record> |
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subjects | Comparative analysis Gamma rays Measurement Methods Toy industry Uranium |
title | Measurement of the neutron capture cross-section of [sup.238]U using the neutron activation technique |
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