FASTGRASS implementation in BISON and Fission gas behavior characterization in UO₂ and connection to validating MARMOT

Technical Report · Wed Sep 30 00:00:00 EDT 2015

DOI:https://doi.org/10.2172/1227388· OSTI ID:1227388

Yun, Di ^[1]; Mo, Kun ^[1]; Ye, Bei ^[1]; Jamison, Laura M. ^[1]; Miao, Yinbin ^[1]; Lian, Jie ^[2]; Yao, Tiankei ^[2]

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1. Argonne National Lab. (ANL), Argonne, IL (United States)
2. Rensselaer Polytechnic Inst., Troy, NY (United States)

This activity is supported by the US Nuclear Energy Advanced Modeling and Simulation (NEAMS) Fuels Product Line (FPL). Two major accomplishments in FY 15 are summarized in this report: (1) implementation of the FASTGRASS module in the BISON code; and (2) a Xe implantation experiment for large-grained UO₂. Both BISON AND MARMOT codes have been developed by Idaho National Laboratory (INL) to enable next generation fuel performance modeling capability as part of the NEAMS Program FPL. To contribute to the development of the Moose-Bison-Marmot (MBM) code suite, we have implemented the FASTGRASS fission gas model as a module in the BISON code. Based on rate theory formulations, the coupled FASTGRASS module in BISON is capable of modeling LWR oxide fuel fission gas behavior and fission gas release. In addition, we conducted a Xe implantation experiment at the Argonne Tandem Linac Accelerator System (ATLAS) in order to produce the needed UO₂ samples with desired bubble morphology. With these samples, further experiments to study the fission gas diffusivity are planned to provide validation data for the Fission Gas Release Model in MARMOT codes.

• Research Organization: Argonne National Lab. (ANL), Argonne, IL (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Office of Defense Nuclear Nonproliferation
• DOE Contract Number: AC02-06CH11357
• OSTI ID: 1227388
• Report Number(s): ANL/NE-15/26; 121540; TRN: US1500912
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
URANIUM DIOXIDE
FISSION PRODUCTS
COMPUTERIZED SIMULATION
FISSION PRODUCT RELEASE
NUCLEAR FUELS
IMPLEMENTATION
VALIDATION
BUBBLES
MORPHOLOGY
PERFORMANCE
B CODES
M CODES
ION IMPLANTATION
XENON IONS
MEV RANGE 10-100
TEMPERATURE RANGE 0400-1000 K
WATER COOLED REACTORS
WATER MODERATED REACTORS