Results of the four PBF severe fuel damage tests
Description
Four in-pile severe fuel damage tests have been conducted in the Power Burst Facility as part of the US Nuclear Regulatory Commission's (USNRC) Severe Accident and Source Term Research Program. The tests included 1-m long bundles of PWR fuel pins and simulated the thermal-hydraulic and fuel damage conditions of a severe core damage accident. Tests were run with both low and high burnup fuel, low and high coolant flow and with slow and rapid cooldown. One test included Ag-In-Cd control rods. The various types of fuel damage that occurred in the four tests are presented and the measured hydrogen generation, fission product release, and aerosol behavior are described. The principal benefits of the test program have been to improve the USNRC's severe accident analysis capability. Some of the computer models affected by the test results are discussed in the paper
Additional details
Additional titles
- Augmented title (English)
- Power Burst Facility
Publishing Information
- Imprint Title
- Proceedings of the US Nuclear Regulatory Commission fifteenth water reactor safety information meeting: Volume 4, Separate effects/experiments and analyses, Source term uncertainty analysis, Integral systems testing, 2D/3D research
- Journal Page Range
- p. 299-323.
- Report number
- NUREG/CP--0091-Vol.4
Conference
- Title
- 15. water reactor safety information meeting.
- Dates
- 26-30 Oct 1987.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 20019263
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COOLANTS; COOLING; CORIUM; CRACKS; FLOW RATE; FLUID FLOW; FUEL COOLING TIME; FUEL ELEMENTS; HYDROGEN; PHOTOGRAPHY; PWR TYPE REACTORS; RADIOACTIVE AEROSOLS; RADIOACTIVITY TRANSPORT; RADIONUCLIDE MIGRATION; REACTOR ACCIDENTS; REACTOR SAFETY; RESEARCH PROGRAMS; SOURCE TERMS; SYNTHESIS; TEST FACILITIES; US NRC
- Descriptors DEC
- ACCIDENTS; AEROSOLS; COLLOIDS; DISPERSIONS; ELEMENTS; ENRICHED URANIUM REACTORS; ENVIRONMENTAL TRANSPORT; MASS TRANSFER; NATIONAL ORGANIZATIONS; NONMETALS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SOLS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS