Alternative fuel cycle PWR models for the ORIGEN computer code
Technical Report
·
OSTI ID:5627539
Reactor physics calculations have led to the development of four PWR models for the ORIGEN computer code. The PWRs operate on the following fuel cycles: (1) denatured /sup 233/U-thorium oxide; (2) plutonium-thorium oxide; (3) low-enrichment uranium oxide with an extended burnup; and (4) thorium oxide enriched with self-generated, denatured /sup 233/U and denatured /sup 235/U. The reactor models are based on cross sections taken directly from the reactor physics codes. Descriptions of the reactor models, as well as values for the ORIGEN flux parameters THERM, RES, and FAST, are given.
- Research Organization:
- Oak Ridge National Lab., TN (USA)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 5627539
- Report Number(s):
- ORNL/TM-7005
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BURNUP
COMPUTER CALCULATIONS
CROSS SECTIONS
DENATURED FUEL
ENERGY SOURCES
FUEL CYCLE
FUELS
KINETICS
MATERIALS
NUCLEAR FUELS
PWR TYPE REACTORS
REACTOR KINETICS
REACTOR MATERIALS
REACTORS
THORIUM CYCLE
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BURNUP
COMPUTER CALCULATIONS
CROSS SECTIONS
DENATURED FUEL
ENERGY SOURCES
FUEL CYCLE
FUELS
KINETICS
MATERIALS
NUCLEAR FUELS
PWR TYPE REACTORS
REACTOR KINETICS
REACTOR MATERIALS
REACTORS
THORIUM CYCLE
WATER COOLED REACTORS
WATER MODERATED REACTORS