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1998•Transactions of the American Nuclear SocietyRequires access

Calculation of the weapons-grade MOX VVER multiassembly benchmarks

Kalugin, A.P. Lazarenko, A.G. Kalashnikov, Jess C Gehin

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Abstract

Within the framework of the joint US-Russian fissile materials disposition program, a set of VVER benchmarks was formulated to verify and validate computer codes with reference to the problem of using mixed-oxide (MOX) fuel in VVER reactors. This set consists of pin cell, single assembly, and multiassembly geometries with low-enriched uranium (LEU) and weapons-grade MOX fuel. Multiassembly geometries (variants V13 and V14) are of the most interest because they give information about an accuracy of neutron flux distribution calculation near the boundary between MOX and LEU. In this analysis, a uniform MOX bundle and a graded MOX bundle are studied. Benchmark calculations are performed for several states and for a depletion to 60 MWd/kg. The report is devoted to an intercomparison of calculation results for such geometries obtained with various codes.

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What this paper is about

Within the framework of the joint US-Russian fissile materials disposition program, a set of VVER benchmarks was formulated to verify and validate computer codes with reference to the problem of using mixed-oxide (MOX) fuel in VVER reactors. This set consists of pin cell, single assembly, and multiassembly geometries with low-enriched uranium (LEU) and weapons-grade MOX fuel. Multiassembly geometries (variants V13 and V14) are of the most interest because they give information about an accuracy of neutron flux distribution calculation near the boundary between MOX and LEU. In this analysis, a uniform MOX bundle and a graded MOX bundle are studied. Benchmark calculations are performed for several states and for a depletion to 60 MWd/kg. The report is devoted to an intercomparison of calculation results for such geometries obtained with various codes.

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Available abstract

Within the framework of the joint US-Russian fissile materials disposition program, a set of VVER benchmarks was formulated to verify and validate computer codes with reference to the problem of using mixed-oxide (MOX) fuel in VVER reactors. This set consists of pin cell, single assembly, and multiassembly geometries with low-enriched uranium (LEU) and weapons-grade MOX fuel. Multiassembly geometries (variants V13 and V14) are of the most interest because they give information about an accuracy of neutron flux distribution calculation near the boundary between MOX and LEU. In this analysis, a uniform MOX bundle and a graded MOX bundle are studied. Benchmark calculations are performed for several states and for a depletion to 60 MWd/kg. The report is devoted to an intercomparison of calculation results for such geometries obtained with various codes.

Key concepts: MOX fuel, VVER, Fissile material, Nuclear engineering, Bundle, Benchmark (surveying), Enriched uranium, Plutonium

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