Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code
The aim of this work is to study the fuel depletion of 30 kW miniature neutron source reactor (MNSR). Under operating conditions of two hours per day for five days a week at a peak thermal neutron flux of 1.0E+12 n/cm 2 s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing...
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| Veröffentlicht in: | Moscow University physics bulletin 2019-11, Vol.74 (6), p.706-709 |
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| creator | Al Zain, Jamal El Hajjaji, O. El Bardouni, T. |
| description | The aim of this work is to study the fuel depletion of 30 kW miniature neutron source reactor (MNSR). Under operating conditions of two hours per day for five days a week at a peak thermal neutron flux of 1.0E+12 n/cm
2
s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing to generate the fuel group constants and the infinite multiplication factor versus the MNSR reactor operating time, at different burn-up values. The amounts of uranium burnt up and plutonium produced in the reactor core are calculated using the DRAGON5 transport lattice code. The results are in good agreement with previous studies. |
| doi_str_mv | 10.3103/S0027134919060031 |
| format | Article |
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2
s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing to generate the fuel group constants and the infinite multiplication factor versus the MNSR reactor operating time, at different burn-up values. The amounts of uranium burnt up and plutonium produced in the reactor core are calculated using the DRAGON5 transport lattice code. The results are in good agreement with previous studies.</description><identifier>ISSN: 0027-1349</identifier><identifier>EISSN: 1934-8460</identifier><identifier>DOI: 10.3103/S0027134919060031</identifier><language>eng</language><publisher>Moscow: Pleiades Publishing</publisher><subject>Depletion ; Engineering Physics ; Mathematical and Computational Physics ; Multiplication ; Neutron flux ; Neutrons ; Nuclear fuels ; Physics ; Physics and Astronomy ; Plutonium ; Theoretical ; Thermal neutrons ; Uranium</subject><ispartof>Moscow University physics bulletin, 2019-11, Vol.74 (6), p.706-709</ispartof><rights>Pleiades Publishing, Ltd. 2019</rights><rights>2019© Pleiades Publishing, Ltd. 2019</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c316t-bb06f306159500495a9e06dff9193e24f94f5ecfd707c726cfbd7232998e80633</citedby><cites>FETCH-LOGICAL-c316t-bb06f306159500495a9e06dff9193e24f94f5ecfd707c726cfbd7232998e80633</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://link.springer.com/content/pdf/10.3103/S0027134919060031$$EPDF$$P50$$Gspringer$$H</linktopdf><linktohtml>$$Uhttps://link.springer.com/10.3103/S0027134919060031$$EHTML$$P50$$Gspringer$$H</linktohtml><link.rule.ids>314,780,784,27924,27925,41488,42557,51319</link.rule.ids></links><search><creatorcontrib>Al Zain, Jamal</creatorcontrib><creatorcontrib>El Hajjaji, O.</creatorcontrib><creatorcontrib>El Bardouni, T.</creatorcontrib><title>Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code</title><title>Moscow University physics bulletin</title><addtitle>Moscow Univ. Phys</addtitle><description>The aim of this work is to study the fuel depletion of 30 kW miniature neutron source reactor (MNSR). Under operating conditions of two hours per day for five days a week at a peak thermal neutron flux of 1.0E+12 n/cm
2
s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing to generate the fuel group constants and the infinite multiplication factor versus the MNSR reactor operating time, at different burn-up values. The amounts of uranium burnt up and plutonium produced in the reactor core are calculated using the DRAGON5 transport lattice code. The results are in good agreement with previous studies.</description><subject>Depletion</subject><subject>Engineering Physics</subject><subject>Mathematical and Computational Physics</subject><subject>Multiplication</subject><subject>Neutron flux</subject><subject>Neutrons</subject><subject>Nuclear fuels</subject><subject>Physics</subject><subject>Physics and Astronomy</subject><subject>Plutonium</subject><subject>Theoretical</subject><subject>Thermal neutrons</subject><subject>Uranium</subject><issn>0027-1349</issn><issn>1934-8460</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2019</creationdate><recordtype>article</recordtype><recordid>eNp1kEFLAzEQhYMoWKs_wFvA8-ok2U02x9LaKmgLW3tettlJu6VuarJ76L83pYIH8TQD73tvmEfIPYNHwUA8LQG4YiLVTIMEEOyCDJgWaZKnEi7J4CQnJ_2a3ISwA8gkF3pAijn2nXdtY-iy6-sjdZZOe9zTCR722DWupdZ52m2Rvs-XBS0wYOXNNi6V6aKyCk27oZNiNFvMMzp2Nd6SK1vtA979zCFZTZ8_xi_J22L2Oh69JUYw2SXrNUgrQLJMZwCpziqNIGtr4wsCeWp1ajM0tlagjOLS2HWtuOBa55iDFGJIHs65B---egxduXO9b-PJkgulFPAs15FiZ8p4F4JHWx5881n5Y8mgPFVX_qkuevjZEyLbbtD_Jv9v-gYJhG0O</recordid><startdate>20191101</startdate><enddate>20191101</enddate><creator>Al Zain, Jamal</creator><creator>El Hajjaji, O.</creator><creator>El Bardouni, T.</creator><general>Pleiades Publishing</general><general>Springer Nature B.V</general><scope>AAYXX</scope><scope>CITATION</scope></search><sort><creationdate>20191101</creationdate><title>Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code</title><author>Al Zain, Jamal ; El Hajjaji, O. ; El Bardouni, T.</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c316t-bb06f306159500495a9e06dff9193e24f94f5ecfd707c726cfbd7232998e80633</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2019</creationdate><topic>Depletion</topic><topic>Engineering Physics</topic><topic>Mathematical and Computational Physics</topic><topic>Multiplication</topic><topic>Neutron flux</topic><topic>Neutrons</topic><topic>Nuclear fuels</topic><topic>Physics</topic><topic>Physics and Astronomy</topic><topic>Plutonium</topic><topic>Theoretical</topic><topic>Thermal neutrons</topic><topic>Uranium</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Al Zain, Jamal</creatorcontrib><creatorcontrib>El Hajjaji, O.</creatorcontrib><creatorcontrib>El Bardouni, T.</creatorcontrib><collection>CrossRef</collection><jtitle>Moscow University physics bulletin</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Al Zain, Jamal</au><au>El Hajjaji, O.</au><au>El Bardouni, T.</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code</atitle><jtitle>Moscow University physics bulletin</jtitle><stitle>Moscow Univ. Phys</stitle><date>2019-11-01</date><risdate>2019</risdate><volume>74</volume><issue>6</issue><spage>706</spage><epage>709</epage><pages>706-709</pages><issn>0027-1349</issn><eissn>1934-8460</eissn><abstract>The aim of this work is to study the fuel depletion of 30 kW miniature neutron source reactor (MNSR). Under operating conditions of two hours per day for five days a week at a peak thermal neutron flux of 1.0E+12 n/cm
2
s, the estimated core life is 10 years (200 days). The DRAGON5 code is utilizing to generate the fuel group constants and the infinite multiplication factor versus the MNSR reactor operating time, at different burn-up values. The amounts of uranium burnt up and plutonium produced in the reactor core are calculated using the DRAGON5 transport lattice code. The results are in good agreement with previous studies.</abstract><cop>Moscow</cop><pub>Pleiades Publishing</pub><doi>10.3103/S0027134919060031</doi><tpages>4</tpages></addata></record> |
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| source | SpringerNature Journals |
| subjects | Depletion Engineering Physics Mathematical and Computational Physics Multiplication Neutron flux Neutrons Nuclear fuels Physics Physics and Astronomy Plutonium Theoretical Thermal neutrons Uranium |
| title | Neutronic Study of Fuel Depletion for the MNSR Research Reactor Using DRAGON5 Code |
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