Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code

Technical Report · Fri Sep 01 04:00:00 UTC 1978

DOI:https://doi.org/10.2172/6787757· OSTI ID:6787757

Croff, A. G.; Bjerke, M. A.; Morrison, G. W.; Petrie, L. M.

Reactor physics calculations and literature searches have been conducted, leading to the creation of revised enriched-uranium and enriched-uranium/mixed-oxide-fueled PWR and BWR reactor models for the ORIGEN computer code. These ORIGEN reactor models are based on cross sections that have been taken directly from the reactor physics codes and eliminate the need to make adjustments in uncorrected cross sections in order to obtain correct depletion results. Revised values of the ORIGEN flux parameters THERM, RES, and FAST were calculated along with new parameters related to the activation of fuel-assembly structural materials not located in the active fuel zone. Recommended fuel and structural material masses and compositions are presented. A summary of the new ORIGEN reactor models is given.

• Research Organization: Oak Ridge National Lab., TN (USA)
• Sponsoring Organization: USDOE
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6787757
• Report Number(s): ORNL/TM-6051
• Country of Publication: United States
• Language: English

Related Subjects

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
BWR TYPE REACTORS
COMPUTER CALCULATIONS
COMPUTER CODES
FUEL CYCLE
KINETICS
MATHEMATICAL MODELS
NUCLEAR REACTION YIELD
O CODES
PLUTONIUM RECYCLE
PWR TYPE REACTORS
REACTOR KINETICS
REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
YIELDS