Multigroup cross section generation capability in GRIFFIN

Conference · Fri Jul 01 04:00:00 EDT 2022

OSTI ID:23178686

Park, Hansol; Lee, Changho; Jung, Yeon Sang ^[1]; Wang, Yaqi; Calvin, Olin; Ortensi, Javier ^[2]

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1. Argonne National Laboratory, Nuclear Science and Engineering Division, 9700 S. Cass Ave, Lemont, IL 60439 (United States)
2. Idaho National Laboratory, Nuclear Science and Technology Division, 1955 N. Fremont Ave., Idaho Falls, ID 83415 (United States)

GRIFFIN is an advanced reactor multiphysics application built on the object-oriented simulation environment (MOOSE) and is jointly developed by Idaho National Laboratory and Argonne National Laboratory. The cross section application programming interface, originally developed for the PROTEUS code, has been integrated into GRIFFIN to prepare cross sections for thermal reactor applications with heterogeneous geometries. Additional improvements have been made by implementing an on-the-fly slowing down method, a double heterogeneity treatment capability, and updating the procedure to generate the fine multigroup library. The cross section preparation capability in GRIFFIN was verified for graphite-moderated TRISO fuel-based reactor benchmark problems: unit-cell problems of VHTR and EMPIRE micro reactor and HTTR assembly problems. Eigenvalues and multigroup cross sections of GRIFFIN agreed very well with those of the continuous-energy Monte Carlo code Serpent2 within 200 pcm in eigenvalue and 2% in cross sections. (authors)

• Research Organization: American Nuclear Society - ANS, La Grange Park, IL 60526 (United States)
• OSTI ID: 23178686
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
COMPUTERIZED SIMULATION
G CODES
GROUP CONSTANTS
HTGR TYPE REACTORS
VALIDATION