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Comparison of MCB and MONTEBURNS Monte Carlo burnup codes on a one-pass deep burn
KTH, School of Engineering Sciences (SCI), Physics, Nuclear Power Safety.
2006 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 33, no 14-15, 1176-1188 p.Article in journal (Refereed) Published
Abstract [en]

Numerical applications implemented on the Monte Carlo method have developed in line with the increase of computer power; nowadays, in the field of nuclear reactor physics, it is possible to perform burnup simulations in a detailed 3D geometry and a continuous energy description by the Monte Carlo method; moreover, the required computing time can be abundantly reduced by taking advantage of a computer cluster. In this paper we focused on comparing the results of the two major Monte Carlo burnup codes, MONTEBURNS and MCB, when they share the same MCNP geometry, nuclear data library, core thermal power, and they apply the same refueling and shuffling schedule. While simulating a total operation time of the Gas Turbine-Modular Helium Reactor of 2100 effective full power days and a one-pass deep burn in-core fuel management schedule, we have found that the two Monte Carlo codes produce very similar results both on the criticality value of the core and the transmutation of the key actinides.

Place, publisher, year, edition, pages
2006. Vol. 33, no 14-15, 1176-1188 p.
Keyword [en]
equations
Identifiers
URN: urn:nbn:se:kth:diva-16176DOI: 10.1016/j.anucene.2006.08.006ISI: 000242523700003Scopus ID: 2-s2.0-33750473378OAI: oai:DiVA.org:kth-16176DiVA: diva2:334218
Note
QC 20100525Available from: 2010-08-05 Created: 2010-08-05 Last updated: 2017-12-12Bibliographically approved

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