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Benchmark Calculations of the Saxton Plutonium Program Critical Experiments
The Saxton critical experiments, which used mixed-oxide (MOX) fuel of 6.6 wt% PuO 2 in natural UO 2 and UO 2 fuel of 5.74 wt% 235 U, are analyzed with MCNP-4B and continuous-energy cross-section libraries ENDF/B-V and ENDF/B-VI. An excellent agreement of calculated and experimental effective multipl...
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| Published in: | Nuclear technology 1999-09, Vol.127 (3), p.315-331 |
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| Main Authors: | , , |
| Format: | Article |
| Language: | English |
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| container_end_page | 331 |
| container_issue | 3 |
| container_start_page | 315 |
| container_title | Nuclear technology |
| container_volume | 127 |
| creator | Abdurrahman, Naeem M. Radulescu, Georgeta Carron, Igor |
| description | The Saxton critical experiments, which used mixed-oxide (MOX) fuel of 6.6 wt% PuO
2
in natural UO
2
and UO
2
fuel of 5.74 wt%
235
U, are analyzed with MCNP-4B and continuous-energy cross-section libraries ENDF/B-V and ENDF/B-VI. An excellent agreement of calculated and experimental effective multiplication factors for the entire set of 1.3208-cm MOX lattices and 1.4224-cm MOX and UO
2
lattices was obtained. The analysis of criticality calculations for the five different lattice pitches show a bias with lattice pitch, which led to an increase of ~0.8% when doubling the lattice pitch. Good agreement between calculated and measured data was obtained for some of the relative power distribution experiments for MOX single-region cores and MOX/UO
2
multiregion cores; however, for others the agreement was less satisfactory. No significant difference in the results for relative power with the two libraries was observed. |
| doi_str_mv | 10.13182/NT99-A3004 |
| format | article |
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2
in natural UO
2
and UO
2
fuel of 5.74 wt%
235
U, are analyzed with MCNP-4B and continuous-energy cross-section libraries ENDF/B-V and ENDF/B-VI. An excellent agreement of calculated and experimental effective multiplication factors for the entire set of 1.3208-cm MOX lattices and 1.4224-cm MOX and UO
2
lattices was obtained. The analysis of criticality calculations for the five different lattice pitches show a bias with lattice pitch, which led to an increase of ~0.8% when doubling the lattice pitch. Good agreement between calculated and measured data was obtained for some of the relative power distribution experiments for MOX single-region cores and MOX/UO
2
multiregion cores; however, for others the agreement was less satisfactory. No significant difference in the results for relative power with the two libraries was observed.</description><identifier>ISSN: 0029-5450</identifier><identifier>EISSN: 1943-7471</identifier><identifier>DOI: 10.13182/NT99-A3004</identifier><identifier>CODEN: NUTYBB</identifier><language>eng</language><publisher>La Grange Park, IL: Taylor & Francis</publisher><subject>Applied sciences ; Computer simulation ; Control rods ; Energy ; Energy. Thermal use of fuels ; Exact sciences and technology ; Fission nuclear power plants ; Installations for energy generation and conversion: thermal and electrical energy ; Mixed oxide fuels ; Pressurized water reactors ; Reactor cores ; Uranium dioxide</subject><ispartof>Nuclear technology, 1999-09, Vol.127 (3), p.315-331</ispartof><rights>Copyright © Taylor & Francis Group, LLC 1999</rights><rights>1999 INIST-CNRS</rights><lds50>peer_reviewed</lds50><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c297t-272a7b06fc845df7ed0325f0d7990ccdb9b2a08d64af6cad7cbcc90d29079fc03</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,776,780,27901,27902</link.rule.ids><backlink>$$Uhttp://pascal-francis.inist.fr/vibad/index.php?action=getRecordDetail&idt=1907070$$DView record in Pascal Francis$$Hfree_for_read</backlink></links><search><creatorcontrib>Abdurrahman, Naeem M.</creatorcontrib><creatorcontrib>Radulescu, Georgeta</creatorcontrib><creatorcontrib>Carron, Igor</creatorcontrib><title>Benchmark Calculations of the Saxton Plutonium Program Critical Experiments</title><title>Nuclear technology</title><description>The Saxton critical experiments, which used mixed-oxide (MOX) fuel of 6.6 wt% PuO
2
in natural UO
2
and UO
2
fuel of 5.74 wt%
235
U, are analyzed with MCNP-4B and continuous-energy cross-section libraries ENDF/B-V and ENDF/B-VI. An excellent agreement of calculated and experimental effective multiplication factors for the entire set of 1.3208-cm MOX lattices and 1.4224-cm MOX and UO
2
lattices was obtained. The analysis of criticality calculations for the five different lattice pitches show a bias with lattice pitch, which led to an increase of ~0.8% when doubling the lattice pitch. Good agreement between calculated and measured data was obtained for some of the relative power distribution experiments for MOX single-region cores and MOX/UO
2
multiregion cores; however, for others the agreement was less satisfactory. No significant difference in the results for relative power with the two libraries was observed.</description><subject>Applied sciences</subject><subject>Computer simulation</subject><subject>Control rods</subject><subject>Energy</subject><subject>Energy. Thermal use of fuels</subject><subject>Exact sciences and technology</subject><subject>Fission nuclear power plants</subject><subject>Installations for energy generation and conversion: thermal and electrical energy</subject><subject>Mixed oxide fuels</subject><subject>Pressurized water reactors</subject><subject>Reactor cores</subject><subject>Uranium dioxide</subject><issn>0029-5450</issn><issn>1943-7471</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>1999</creationdate><recordtype>article</recordtype><recordid>eNptkE9PwzAMxSMEEmNw4gv0gMQBFdymbZojVOOPmGAS41y5acIKaTOSVmzfnrANcUE-PFn6-dl-hJxGcBnRKI-vnuach9cUINkjo4gnNGQJi_bJCCDmYZqkcEiOnHv3LWOQjMjjjezEokX7ERSoxaCxb0znAqOCfiGDF1z1pgtmevDSDG0ws-bNYhsUtukbgTqYrJbSNq3sendMDhRqJ092Oiavt5N5cR9On-8eiutpKGLO-jBmMbIKMiXyJK0VkzXQOFVQM85BiLriVYyQ11mCKhNYM1EJwaGOOTCuBNAxOd_6Lq35HKTry7ZxQmqNnTSDK1mSMkop5J682JLCGuesVOXS34p2XUZQbhIrfxIrN4l5-mzni86_pix2onF_I36_L49lW6zplLEtfhmr67LHtTb2d4b-5_8NGs193g</recordid><startdate>19990901</startdate><enddate>19990901</enddate><creator>Abdurrahman, Naeem M.</creator><creator>Radulescu, Georgeta</creator><creator>Carron, Igor</creator><general>Taylor & Francis</general><general>American Nuclear Society</general><scope>IQODW</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>7TC</scope></search><sort><creationdate>19990901</creationdate><title>Benchmark Calculations of the Saxton Plutonium Program Critical Experiments</title><author>Abdurrahman, Naeem M. ; Radulescu, Georgeta ; Carron, Igor</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c297t-272a7b06fc845df7ed0325f0d7990ccdb9b2a08d64af6cad7cbcc90d29079fc03</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>1999</creationdate><topic>Applied sciences</topic><topic>Computer simulation</topic><topic>Control rods</topic><topic>Energy</topic><topic>Energy. Thermal use of fuels</topic><topic>Exact sciences and technology</topic><topic>Fission nuclear power plants</topic><topic>Installations for energy generation and conversion: thermal and electrical energy</topic><topic>Mixed oxide fuels</topic><topic>Pressurized water reactors</topic><topic>Reactor cores</topic><topic>Uranium dioxide</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Abdurrahman, Naeem M.</creatorcontrib><creatorcontrib>Radulescu, Georgeta</creatorcontrib><creatorcontrib>Carron, Igor</creatorcontrib><collection>Pascal-Francis</collection><collection>CrossRef</collection><collection>Mechanical Engineering Abstracts</collection><jtitle>Nuclear technology</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Abdurrahman, Naeem M.</au><au>Radulescu, Georgeta</au><au>Carron, Igor</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Benchmark Calculations of the Saxton Plutonium Program Critical Experiments</atitle><jtitle>Nuclear technology</jtitle><date>1999-09-01</date><risdate>1999</risdate><volume>127</volume><issue>3</issue><spage>315</spage><epage>331</epage><pages>315-331</pages><issn>0029-5450</issn><eissn>1943-7471</eissn><coden>NUTYBB</coden><abstract>The Saxton critical experiments, which used mixed-oxide (MOX) fuel of 6.6 wt% PuO
2
in natural UO
2
and UO
2
fuel of 5.74 wt%
235
U, are analyzed with MCNP-4B and continuous-energy cross-section libraries ENDF/B-V and ENDF/B-VI. An excellent agreement of calculated and experimental effective multiplication factors for the entire set of 1.3208-cm MOX lattices and 1.4224-cm MOX and UO
2
lattices was obtained. The analysis of criticality calculations for the five different lattice pitches show a bias with lattice pitch, which led to an increase of ~0.8% when doubling the lattice pitch. Good agreement between calculated and measured data was obtained for some of the relative power distribution experiments for MOX single-region cores and MOX/UO
2
multiregion cores; however, for others the agreement was less satisfactory. No significant difference in the results for relative power with the two libraries was observed.</abstract><cop>La Grange Park, IL</cop><pub>Taylor & Francis</pub><doi>10.13182/NT99-A3004</doi><tpages>17</tpages></addata></record> |
| fulltext | fulltext |
| identifier | ISSN: 0029-5450 |
| ispartof | Nuclear technology, 1999-09, Vol.127 (3), p.315-331 |
| issn | 0029-5450 1943-7471 |
| language | eng |
| recordid | cdi_pascalfrancis_primary_1907070 |
| source | Taylor and Francis Science and Technology Collection |
| subjects | Applied sciences Computer simulation Control rods Energy Energy. Thermal use of fuels Exact sciences and technology Fission nuclear power plants Installations for energy generation and conversion: thermal and electrical energy Mixed oxide fuels Pressurized water reactors Reactor cores Uranium dioxide |
| title | Benchmark Calculations of the Saxton Plutonium Program Critical Experiments |
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