Safety Analysis of Stacy's Critical Territory Criticality with Monte Carlo Transport Calculations
| Main Author: | Zuhair, Zuhair |
|---|---|
| Format: | Article info application/pdf eJournal |
| Bahasa: | eng |
| Terbitan: |
Natural B, Journal of Health and Environmental Sciences
, 2013
|
| Subjects: | |
| Online Access: |
https://natural-b.ub.ac.id/index.php/natural-b/article/view/190 https://natural-b.ub.ac.id/index.php/natural-b/article/view/190/164 https://natural-b.ub.ac.id/index.php/natural-b/article/downloadSuppFile/190/67 |
| ctrlnum |
article-190 |
|---|---|
| fullrecord |
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<dc schemaLocation="http://www.openarchives.org/OAI/2.0/oai_dc/ http://www.openarchives.org/OAI/2.0/oai_dc.xsd"><title lang="en-US">Safety Analysis of Stacy's Critical Territory Criticality with Monte Carlo Transport Calculations</title><creator>Zuhair, Zuhair</creator><subject lang="en-US">criticality, uranyl nitrate solution, STACY, cylindrical core, MCNP-4C, MCNPX</subject><description lang="en-US">A set of experiment has been done at STACY facility and many fundamental parameters of uranyl nitrate solution have been found out. Criticality is one of main parameters in predicting neutronic characteristic of STACY experiment beside solution level reactivity, void reactivity, kinetic parameter and temperature reactivity which dominates transient phenomenon in abnormal condition. Criticality experiment performed at STACY core uses 9.97% 235U -enriched uranyl nitrate solution with 80-cm-diameter cylindrical and 150-cm-height tank. Eight critical configurations in unrelected and water-reflected conditions were selected in this paper for criticality safety calculation with Monte Carlo transport code MCNPX. For all configurations, MCNPX calculations show good consistency with the trend of producing underestimated keff. Calculation biases with experimental data (keff = 1) for water-reflected configurations, i.e. 0.01-0.18%, were slightly better than those of unreflected configurations (0.14-0.41%). MCNPX calculation results which are better than the prediction of MCNP-4C concludes that MCNPX is more eligible to be applied to criticality safety analysis of uranyl nitrate solution in commercial nuclear fuel cycle facility.</description><publisher lang="en-US">Natural B, Journal of Health and Environmental Sciences</publisher><contributor lang="en-US"/><date>2013-05-10</date><type>Journal:Article</type><type>Other:info:eu-repo/semantics/publishedVersion</type><type>Journal:Article</type><type>File:application/pdf</type><identifier>https://natural-b.ub.ac.id/index.php/natural-b/article/view/190</identifier><identifier>10.21776/ub.natural-b.2013.002.01.3</identifier><source lang="en-US">Natural B, Journal of Health and Environmental Sciences; Vol 2, No 1 (2013); 12-18</source><source>2301-4202</source><source>2088-4613</source><language>eng</language><relation>https://natural-b.ub.ac.id/index.php/natural-b/article/view/190/164</relation><relation>https://natural-b.ub.ac.id/index.php/natural-b/article/downloadSuppFile/190/67</relation><recordID>article-190</recordID></dc>
|
| language |
eng |
| format |
Journal:Article Journal Other:info:eu-repo/semantics/publishedVersion Other File:application/pdf File Journal:eJournal |
| author |
Zuhair, Zuhair |
| title |
Safety Analysis of Stacy's Critical Territory Criticality with Monte Carlo Transport Calculations |
| publisher |
Natural B, Journal of Health and Environmental Sciences |
| publishDate |
2013 |
| topic |
criticality uranyl nitrate solution STACY cylindrical core MCNP-4C MCNPX |
| url |
https://natural-b.ub.ac.id/index.php/natural-b/article/view/190 https://natural-b.ub.ac.id/index.php/natural-b/article/view/190/164 https://natural-b.ub.ac.id/index.php/natural-b/article/downloadSuppFile/190/67 |
| contents |
A set of experiment has been done at STACY facility and many fundamental parameters of uranyl nitrate solution have been found out. Criticality is one of main parameters in predicting neutronic characteristic of STACY experiment beside solution level reactivity, void reactivity, kinetic parameter and temperature reactivity which dominates transient phenomenon in abnormal condition. Criticality experiment performed at STACY core uses 9.97% 235U -enriched uranyl nitrate solution with 80-cm-diameter cylindrical and 150-cm-height tank. Eight critical configurations in unrelected and water-reflected conditions were selected in this paper for criticality safety calculation with Monte Carlo transport code MCNPX. For all configurations, MCNPX calculations show good consistency with the trend of producing underestimated keff. Calculation biases with experimental data (keff = 1) for water-reflected configurations, i.e. 0.01-0.18%, were slightly better than those of unreflected configurations (0.14-0.41%). MCNPX calculation results which are better than the prediction of MCNP-4C concludes that MCNPX is more eligible to be applied to criticality safety analysis of uranyl nitrate solution in commercial nuclear fuel cycle facility. |
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Universitas Brawijaya |
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mill.onesearch.id |
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Perpustakaan Universitas Brawijaya |
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480 |
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Natural B |
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MALANG |
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JAWA TIMUR |
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2016-09-22T21:26:29Z |
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2019-08-10T04:17:07Z |
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