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SAS2H: The SCALE-4 analysis sequence for LWR fuel depletion

Conference ·
OSTI ID:5989657
;

The primary use of the SAS2H control module of SCALE (Standardized Computer Analyses for Licensing Evaluation) is for fuel depletion analyses of light-water-reactor (LWR) fuel. Spent fuel characteristics such as radiation sources, heat generation sources, and isotopic concentrations can be computed within SCALE using the SAS2 control module. At each time step, the SAS2 sequence performs a radiation transport analysis (via XSDRNPM-S) to obtain appropriate cross sections and spectral parameters for an ORIGEN-S point-depletion analysis. Each ORIGEN-S case produces the burnup-dependent fuel composition to be used in the next spectral calculation. A final ORIGEN-S case is used to perform the complete depletion/decay analysis using the burnup-dependent cross sections. A significantly enhanced version of the SAS2 control module, which is denoted as SAS2H, has been made available with the release of SCALE-4. The techniques used by SAS2H are presented in this paper along with a discussion of some recent validation/verification efforts.

Research Organization:
Oak Ridge National Lab., TN (United States)
Sponsoring Organization:
DOE; USDOE, Washington, DC (United States)
DOE Contract Number:
AC05-84OR21400
OSTI ID:
5989657
Report Number(s):
CONF-9109217-1; ON: DE92005106
Country of Publication:
United States
Language:
English

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Related Subjects

050800* -- Nuclear Fuels-- Spent Fuels Reprocessing
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
BURNUP
BWR TYPE REACTORS
COMPUTER CODES
CROSS SECTIONS
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUELS
ISOTOPES
MATERIALS
NUCLEAR FUELS
POWER REACTORS
PWR TYPE REACTORS
RADIATION SOURCES
RADIATION TRANSPORT
RADIOISOTOPES
REACTOR MATERIALS
REACTORS
S CODES
SPENT FUELS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS