MOCUM Verification with a Heterogeneous MOX Whole Core C5G7 Benchmark Problem

Journal Article · Fri Jul 01 04:00:00 EDT 2016 · Transactions of the American Nuclear Society

OSTI ID:23042846

Oredeko, Ayoola; Yang, Xue ^[1]; Wu, Zeyun ^[2]

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1. Texas A and M University-Kingsville: 700 University Blvd. MSC 191, Kingsville, TX, 78363 (United States)
2. NIST Center for Neutron Research, 100 Bureau Drive, Mail Stop 6101, Gaithersburg, MD 20899 (United States)

Recent advancements in computer technology has allowed for the possibility to solve complex reactor problems without homogenization, but the present benchmark problems are all limited to small scale with few fuel assemblies and homogeneity at the core level. Therefore, to verify the capabilities of the advanced neutronics codes, heterogeneous full core model shall be developed. Recently several whole-core benchmark problems such as BEAVRS and VERA are developed with measured data to which computational codes can be compared. With a particular research interest on the MOX fuel, this study develops a two-dimensional (2-D) whole core MOX neutronics benchmark based on the C5G7 benchmark concept. The developed MOX core benchmark will then be used to verify the accuracy of the MOCUM code, which is developed using the method of characteristic (MOC) as the flux solver with an advanced geometry processor designed for arbitrary core geometries. MOCUM results will be compared against MCNP5 results as the reference solutions. (authors)

• OSTI ID: 23042846
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 115; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BENCHMARKS
FUEL ASSEMBLIES
GEOMETRY
MIXED OXIDE FUELS
TWO-DIMENSIONAL CALCULATIONS
VERIFICATION