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

Technical Report · Fri Dec 01 00:00:00 EST 1989

DOI:https://doi.org/10.2172/5229728· OSTI ID:5229728

Ludwig, S. B.; Renier, J. P.

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.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: DOE/RW
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5229728
• Report Number(s): ORNL/TM-11018; ON: DE90005020; TRN: 90-004350
• Country of Publication: United States
• Language: English

Related Subjects

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