Verification of High-Fidelity Neutronics Code PROTEUS for C5G7 Benchmark Problems

Journal Article · Sat Jul 01 04:00:00 EDT 2017 · Transactions of the American Nuclear Society

OSTI ID:23050315

Jung, Y. S.; Lee, C. H.; Smith, M. A. ^[1]

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1. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, IL, 60439 (United States)

Under the DOE Nuclear Energy Advanced Modeling and Simulation (NEAMS) program, the 3D whole core transport code PROTEUS has been developed at Argonne National Laboratory to perform the detailed 3D transport calculation for various reactor types including irregular or complex geometric reactors. PROTEUS includes two distinct transport solvers: SN and MOC. Among them, the MOC solver based on the extruded geometry, thus named MOCEX, can produce the faithful 3-D transport solutions by employing the rigorous and robust 2D/3D MOC formulation. This formulation overcomes the drawbacks of a full 3D MOC method requiring enormous memory and computational resources and resolves the instability issues of the 2D/1D method as well. The solution of MOCEX converges to that of a Monte Carlo code as the discretization of angle, space and energy is refined, unlike the 2D/1D method. As a verification and validation (V and V) effort of PROTEUS-MOCEX, this paper presents verification test results using the well-known 3D C5G7 benchmark problems by solving and comparing eigenvalues and pin powers with MCNP solutions.

• OSTI ID: 23050315
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 116; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BENCHMARKS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
GEOMETRY
MONTE CARLO METHOD
NEUTRON TRANSPORT
NUCLEAR ENERGY
THREE-DIMENSIONAL CALCULATIONS
VALIDATION
VERIFICATION