Testing of ENDF/B-VIII.0 in the GNDS format with LLNL transport codes - 25606

Conference · Wed Aug 15 00:00:00 EDT 2018

OSTI ID:23055126

Descalle, Marie-Anne; Beck, Bret; Mattoon, Caleb; Jurgenson, Eric; McKinley, Scott; Bailey, Teresa; Tagani, Bujar ^[1]

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1. Lawrence Livermore National Laboratory 7000 East Avenue, Livermore, CA, 94550 (United States)

ENDF/B-VIII.0 was released in the Evaluated Nuclear Data Format and the Generalized Nuclear Data Structure format (GNDS), a new international standard for storing nuclear data developed under the auspices of the Nuclear Energy Agency Working Party on Evaluation Cooperation Subgroup 38. GNDS relies on modern coding practices, and offers a structured, flexible and physics-based standard for storing and exchanging nuclear data to address limitations in legacy nuclear data formats such as ENDF-6. GNDS supports the storage of evaluated nuclear data as well as processed data suitable for both deterministic (i.e., multi-group) and Monte Carlo transport codes. Lawrence Livermore National Laboratory has implemented a complete suite of codes to test GNDS data. Simulations for the ENDF/B-VIII.0 cross-section library in GNDS format are presented. Deterministic and Monte Carlo radiation transport simulations with the Ardra and Mercury codes respectively, are validated against reactivities in fast criticality safety benchmark assemblies. Finally, Mercury simulations of {sup 238}U(n,f), {sup 237}Np(n,f) and {sup 239}Pu(n,f) reaction rates in Godiva, Jezebel and Flattop are compared to MCNP results and measured data. (authors)

• Research Organization: American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 23055126
• Resource Relation: Conference: RPSD 2018: 20. Topical Meeting of the Radiation Protection and Shielding Division of ANS, Santa Fe, NM (United States), 26-31 Aug 2018; Other Information: Country of input: France; 13 refs.; available on CD Rom from American Nuclear Society - ANS, 555 North Kensington Avenue, La Grange Park, IL 60526 (US)
• Country of Publication: United States
• Language: English

Related Subjects

61 RADIATION PROTECTION AND DOSIMETRY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
97 MATHEMATICAL METHODS AND COMPUTING
BENCHMARKS
COMPARATIVE EVALUATIONS
COMPUTERIZED SIMULATION
CRITICALITY
LAWRENCE LIVERMORE NATIONAL LABORATORY
MONTE CARLO METHOD
NEPTUNIUM 237
NUCLEAR DATA COLLECTIONS
NUCLEAR ENERGY
PLUTONIUM 239
RADIATION TRANSPORT
REACTION KINETICS
REACTIVITY
TESTING
URANIUM 238