Thermal group contribution to the fuel-temperature coefficient revisited
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6025137
- Paul Scherrer Institute, Villigen PSI (Switzerland)
A project at the Paul Scherrer Institute (PSI) involves the development of simulation models for the transient analysis of the reactors in Switzerland (STARS) (Ref. 1). This project, funded in part by the Swiss Federal Nuclear Safety Inspectorate, also involves the calculation and evaluation of certain transients for Swiss light water reactors. To generate the nuclear data for these analyses, we have employed various codes, including the cell/assembly codes BOXER (Refs. 2 and 3) and CASMO-3 (Ref. 4). For certain reactivity insertion accidents, the fuel-temperature coefficient (FTC) determines the major component of the feedback reactivity, which limits the peak fuel enthalpy during the transient. The FTC has a component due to the temperature dependence of the oxygen scattering in the fuel that causes changes in the thermal group cross sections. However, this and other sources of a thermal group contribution to the FTC (TFTC) are sometimes ignored. In this paper, we present some results of investigations of contributions to the TFTC.
- OSTI ID:
- 6025137
- Report Number(s):
- CONF-930601--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 68
- Country of Publication:
- United States
- Language:
- English
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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
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
FUEL ELEMENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SIMULATION
TEMPERATURE GRADIENTS
TESTING
THREE-DIMENSIONAL CALCULATIONS
VALIDATION
WATER COOLED REACTORS
210100* -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
COMPUTER CODES
COMPUTERIZED SIMULATION
CROSS SECTIONS
FUEL ELEMENTS
REACTOR COMPONENTS
REACTOR CORES
REACTORS
SIMULATION
TEMPERATURE GRADIENTS
TESTING
THREE-DIMENSIONAL CALCULATIONS
VALIDATION
WATER COOLED REACTORS