Review of the PBF program as a source of data for qualification of fuel behavior codes. Final report. [PWR; BWR].
- Author
- Johnson, R. L.
- Published
- United States : [publisher not identified], 1979.
Springfield, Va. : National Technical Information Service, [approximately 1979] - Physical Description
- microfiche : negative ; 11 x 15 cm
- Additional Creators
- Johnson, R. T. and Johnson, S. O.
- Summary
- The US NRC's Power Burst Facility (PBF) test program is reviewed for usefulness in qualification of fuel behavior codes used in the licensing of nuclear power plants. Fuel performance parameter ranges from selected design basis events are compared with experimental conditions to evaluate the PBF program. Data adequacy is considered in terms of both completeness and required accuracy for use in transient fuel behavior code assessment.
- Report Numbers
- EPRI-NP-1202
- Other Subject(s)
- 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
- 22 general studies of nuclear reactors
- 220900 - nuclear reactor technology- reactor safety
- Accidents
- Bwr type reactors
- Design basis accidents
- Fuel elements
- Fuel rods
- Performance testing
- Pressure gradients
- Pwr type reactors
- Reactor accidents
- Reactor components
- Reactors
- Stresses
- Test facilities
- Testing
- Thermal stresses
- Water cooled reactors
- Water moderated reactors
- Collection
- NTIS collection.
- Note
- OSTI Identifier 5576971
Research organization: Intermountain Technologies, Inc., Idaho Falls, ID (USA).
View MARC record | catkey: 45334002