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Title: Standard- and extended-burnup PWR (pressurized-water reactor) and BWR (boiling-water reactor) reactor models for the ORIGEN2 computer code

Abstract

The purpose of this report is to describe an updated set of reactor models for pressurized-water reactors (PWRs) and boiling-water reactors (BWRs) operating on uranium fuel cycles and the methods used to generate the information for these models. Since new fuel cycle schemes and reactor core designs are introduced from time to time by reactor manufacturers and fuel vendors, an effort has been made to update these reactor models periodically and to expand the data bases used by the ORIGEN2 computer code. In addition, more sophisticated computational techniques than previously available were used to calculate the resulting reactor model cross-section libraries. The PWR models were based on a Westinghouse design, while the BWR models were based on a General Electric BWR/6 design. The specific reactor types considered in this report are as follows (see Glossary for the definition of these and other terms): (1) PWR-US, (2) PWR-UE, (3) BWR-US, (4) BWR-USO, and (5) BWR-UE. Each reactor model includes a unique data library that may be used to simulate the buildup and deletion of isotopes in nuclear materials using the ORIGEN2 computer code. 33 refs., 44 tabs.

Authors:
;
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
DOE/RW
OSTI Identifier:
5229728
Report Number(s):
ORNL/TM-11018
ON: DE90005020; TRN: 90-004350
DOE Contract Number:  
AC05-84OR21400
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE; BURNUP; O CODES; BWR TYPE REACTORS; PWR TYPE REACTORS; A CODES; B CODES; COMPARATIVE EVALUATIONS; COMPILED DATA; COMPUTERIZED SIMULATION; DATA PROCESSING; FUEL CYCLE; FUEL ELEMENTS; G CODES; HEAT TRANSFER; N CODES; POWER GENERATION; R CODES; REACTOR COOLING SYSTEMS; REACTOR CORES; S CODES; TECHNOLOGY ASSESSMENT; U CODES; X CODES; COMPUTER CODES; COOLING SYSTEMS; DATA; ENERGY SYSTEMS; ENERGY TRANSFER; INFORMATION; NUMERICAL DATA; PROCESSING; REACTOR COMPONENTS; REACTORS; SIMULATION; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210100* - Power Reactors, Nonbreeding, Light-Water Moderated, Boiling Water Cooled; 210200 - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled; 990200 - Mathematics & Computers

Citation Formats

Ludwig, S. B., and Renier, J. P. Standard- and extended-burnup PWR (pressurized-water reactor) and BWR (boiling-water reactor) reactor models for the ORIGEN2 computer code. United States: N. p., 1989. Web. doi:10.2172/5229728.
Ludwig, S. B., & Renier, J. P. Standard- and extended-burnup PWR (pressurized-water reactor) and BWR (boiling-water reactor) reactor models for the ORIGEN2 computer code. United States. https://doi.org/10.2172/5229728
Ludwig, S. B., and Renier, J. P. 1989. "Standard- and extended-burnup PWR (pressurized-water reactor) and BWR (boiling-water reactor) reactor models for the ORIGEN2 computer code". United States. https://doi.org/10.2172/5229728. https://www.osti.gov/servlets/purl/5229728.
@article{osti_5229728,
title = {Standard- and extended-burnup PWR (pressurized-water reactor) and BWR (boiling-water reactor) reactor models for the ORIGEN2 computer code},
author = {Ludwig, S. B. and Renier, J. P.},
abstractNote = {The purpose of this report is to describe an updated set of reactor models for pressurized-water reactors (PWRs) and boiling-water reactors (BWRs) operating on uranium fuel cycles and the methods used to generate the information for these models. Since new fuel cycle schemes and reactor core designs are introduced from time to time by reactor manufacturers and fuel vendors, an effort has been made to update these reactor models periodically and to expand the data bases used by the ORIGEN2 computer code. In addition, more sophisticated computational techniques than previously available were used to calculate the resulting reactor model cross-section libraries. The PWR models were based on a Westinghouse design, while the BWR models were based on a General Electric BWR/6 design. The specific reactor types considered in this report are as follows (see Glossary for the definition of these and other terms): (1) PWR-US, (2) PWR-UE, (3) BWR-US, (4) BWR-USO, and (5) BWR-UE. Each reactor model includes a unique data library that may be used to simulate the buildup and deletion of isotopes in nuclear materials using the ORIGEN2 computer code. 33 refs., 44 tabs.},
doi = {10.2172/5229728},
url = {https://www.osti.gov/biblio/5229728}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Dec 01 00:00:00 EST 1989},
month = {Fri Dec 01 00:00:00 EST 1989}
}