ORIGEN2 model and results for the Clinch River Breeder Reactor

Technical Report · Tue Jun 01 04:00:00 EDT 1982

DOI:https://doi.org/10.2172/5340980· OSTI ID:5340980

Croff, A G; Bjerke, M A

Reactor physics calculations and literature information acquisition have led to the development of a Clinch River Breeder Reactor (CRBR) model for the ORIGEN2 computer code. The model is based on cross sections taken directly from physics codes. Details are presented concerning the physical description of the fuel assemblies, the fuel management scheme, irradiation parameters, and initial material compositions. The ORIGEN2 model for the CRBR has been implemented, resulting in the production of graphical and tabular characteristics (radioactivity, thermal power, and toxicity) of CRBR spent fuel, high-level waste, and fuel-assembly structural material waste as a function of decay time. Characteristics for pressurized water reactors (PWRs), commercial liquid-metal fast breeder reactors (LMFBRs), and the Fast Flux Test Facility (FFTF) have also been included in this report for comparison with the CRBR data.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 5340980
• Report Number(s): NUREG/CR-2762; ORNL-5884; ON: DE82017138
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
AFTER-HEAT
BREEDER REACTORS
CLINCH RIVER BREEDER REACTOR
COMPUTER CODES
D CODES
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
FISSION PRODUCTS
FUEL MANAGEMENT
ISOTOPES
KINETICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
MATERIALS
NEUTRON FLUX
POWER REACTORS
RADIATION FLUX
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR KINETICS
REACTORS
SODIUM COOLED REACTORS
WASTES