Release and deposition of volatile fission products during in-pile severe fuel damage tests
Conference
·
· Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5534858
Four in-pile severe fuel damage (SFD) tests have been conducted in the Power Burst Facility (PBF) at the Idaho National Engineering Lab. (INEL). These tests are part of the Severe Fuel Damage Source Term Research Program sponsored by the US Nuclear Regulatory Commission (NRC) and its international partners. The overall objectives of the SFD tests are to obtain the data necessary to understand fuel behavior, fission product behavior, and hydrogen generation during severe accidents. The four SFD tests were designed SFD-ST, SFD 1-1, SFD 1-3, and SFD 1-4. The fuel rods in each test were typical of 17 x 17 pressurized water reactor fuel elements, except 1 m in length. The results presented in this summary indicate that the overall volatile fission product releases were lower then expected, considering the extreme conditions of the tests. Deposition on surfaces was significant, and all but tellurium was easily removed by water flushing. Tellurium was not released from the fuel bundles in large quantities except in Test SFD-ST, where significant cladding oxidation occurred. The preliminary results suggest that the effect of control rod materials on volatile fission product release from the fuel may be important. However, in the SFD 1-4 test, the greater aerosol source due to the present of control rod materials transported the volatile fission products farther downstream.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls
- OSTI ID:
- 5534858
- Report Number(s):
- CONF-870601-
- Conference Information:
- Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 54
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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220900* -- Nuclear Reactor Technology-- Reactor Safety
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Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
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ACCIDENTS
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ISOTOPES
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PWR TYPE REACTORS
RADIOACTIVE MATERIALS
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TEST FACILITIES
VOLATILITY
WATER COOLED REACTORS
WATER MODERATED REACTORS