Fission product behavior during the in-pile Severe Fuel Damage Test SFD 1-4
Fission product behavior during Severe Fuel Damage (SFD) Test SFD 1-4 is discussed in this paper. The SFD 1-4 fuel bundle consisted of 26 previously irradiated (36000 MWd/tU) and 2 fresh pressurized-water-reactor fuel rods, and 4 stainless-steel clad Ag-In-Cd control rods. The 1-m bundle was heated to temperatures in excess of 2400 K during the test to reproduce temperature, fuel damage, fission product release, hydrogen generation, and control rod material behavior that are representative of a small break loss of coolant accident in a light-water-reactor. Samples of the effluent exiting the damaged fuel bundle consisting of superheated steam, fission products, aerosols, and noncondensable gases were collected and analyzed. Measurements of deposition on sample system surfaces were also made. The samples were analyzed using a variety of analytical techniques to provide an understanding of the release, transport and deposition of fission products. The results are presented in terms of release fractions, release rates and the distribution of fission products. The probable chemical forms of the predominant fission product species are inferred from the solubility, transport and deposition behavior of key isotopes. 9 refs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6565253
- Report Number(s):
- EGG-M-33587; CONF-8806143-8; ON: DE89005187
- Resource Relation:
- Conference: 2. nuclear reactor severe accident chemistry symposium, Toronto, Canada, 5 Jun 1988; Other Information: Portions of this document are illegible in microfiche products
- Country of Publication:
- United States
- Language:
- English
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LOSS OF COOLANT
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CESIUM 137
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EUROPIUM 154
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