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

Abstract

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.

Authors:
; ; ;
Publication Date:
Research Org.:
Oak Ridge National Lab., TN (USA)
Sponsoring Org.:
USDOE
OSTI Identifier:
6787757
Report Number(s):
ORNL/TM-6051
TRN: 79-002795
DOE Contract Number:  
W-7405-ENG-26
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BWR TYPE REACTORS; FUEL CYCLE; REACTOR KINETICS; COMPUTER CALCULATIONS; PWR TYPE REACTORS; COMPUTER CODES; MATHEMATICAL MODELS; NUCLEAR REACTION YIELD; O CODES; PLUTONIUM RECYCLE; KINETICS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; YIELDS; 210100* - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Croff, A. G., Bjerke, M. A., Morrison, G. W., and Petrie, L. M. Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code. United States: N. p., 1978. Web. doi:10.2172/6787757.
Croff, A. G., Bjerke, M. A., Morrison, G. W., & Petrie, L. M. Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code. United States. doi:10.2172/6787757.
Croff, A. G., Bjerke, M. A., Morrison, G. W., and Petrie, L. M. Fri . "Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code". United States. doi:10.2172/6787757. https://www.osti.gov/servlets/purl/6787757.
@article{osti_6787757,
title = {Revised uranium--plutonium cycle PWR and BWR models for the ORIGEN computer code},
author = {Croff, A. G. and Bjerke, M. A. and Morrison, G. W. and Petrie, L. M.},
abstractNote = {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.},
doi = {10.2172/6787757},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1978},
month = {9}
}