FRAPCON-2 assessment: power reactor fuel performance data and code evaluation status
Creators
Description
The Nuclear Regulatory Commission's Division of Accident Evaluation (DAE) is sponsoring a fuel behavior research program entitled ''Evaluation of Power Reactor Fuel Performance Analysis Capabilities''. The main program objective is to evaluate the performance and accuracy of DAE-sponsored fuel rod material behavior codes for application to commercial fuel design and operational conditions. Program emphasis to data has been on the steady state fuel rod model, FRAPCON-2. During each of 2 FRAPCON activity phases, available high burnup results from EPRI and DOE sponsored power reactor fuel surveillance programs have been acquired, reviewed, and analyzed to provide the basic code input and fuel performance data. This data is then applied to the generation of FRAPCON predictions, the systematic comparison of key predicted and measured fuel performance parameters, and the interpretation of results to identify code capabilities and outstanding model development requirements. The program activities are documented in the form of Data and Code Evaluation Reports
Additional details
Publishing Information
- Imprint Title
- Twelfth water reactor safety research information meeting: proceedings. Volume 3
- Journal Page Range
- p. 512-535.
- Report number
- NUREG/CP--0058-Vol.3
Conference
- Title
- 12. water reactor safety research information meeting.
- Dates
- 23-26 Oct 1984.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16085928
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; COMPUTER CODES; DATA ACQUISITION; DEFORMATION; FISSION PRODUCT RELEASE; FISSION PRODUCTS; FUEL RODS; PERFORMANCE; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY; SPECIFICATIONS; US NRC
- Descriptors DEC
- ACCIDENTS; ENRICHED URANIUM REACTORS; FUEL ELEMENTS; ISOTOPES; MATERIALS; NATIONAL ORGANIZATIONS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS