DF-1: an ACRR separate effects experiment on severe fuel damage
Description
A series of in-pile experiments addressing LWR severe fuel damage phenomena is being conducted in the ACRR reactor at Sandia National Laboratories. The ACRR Damaged Fuel Relocation (DFR) experiments are separate effects tests which provide a data base for the development and verification of models for LWR severe core damage accidents. The first experiment in this series, DF-1, has been completed and the results and analysis to date are discussed in this paper. DF-1 examined the effect of low initial clad oxidation conditions on fuel damage and relocation processes. Visual observation showed early clad relocation and partial blockage formation at the grid spacer location with significant aerosol production. Oxidation-driven heating rates of 250K/s and peak temperatures in excess of 25250K were observed
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as DE84017421.
Files
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Additional details
Publishing Information
- Imprint Pagination
- 12 p.
- Report number
- SAND--84-0419C
Conference
- Title
- International meeting on thermal nuclear reactor safety.
- Dates
- 10-14 Sep 1984.
- Place
- Karlsruhe (Germany, F.R.).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16031435
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACPR REACTOR; AEROSOLS; FAILURES; FLOW BLOCKAGE; FUEL CANS; FUEL ELEMENTS; HEATING; NUCLEAR FUELS; OXIDATION; REACTOR ACCIDENTS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; CHEMICAL REACTIONS; COLLOIDS; DISPERSIONS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MATERIALS; MIXED SPECTRUM REACTORS; PULSED REACTORS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SOLID HOMOGENEOUS REACTORS; SOLS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-840914--15.