Published April 1992 | Version v1
Report Metadata-only

Release of fission products from irradiated aluminide fuel at high temperatures

Creators

  • 1. Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.
  • 2. Oak Ridge National Lab., TN (United States)
  • 3. Argonne National Lab., IL (United States)

Description

Irradiated uranium-aluminide fuel plates of 40% 235U enrichment were heated for the determination of the amounts of fission products released at temperatures up to and higher than the melting point of the fuel cladding material. The release of fission products from the fuel plate at temperatures below 500 deg. C was negligible. Three stages of fission product releases were observed. The first rapid release was observed at ∼561 deg. C along with blistering of the plates. The next release, which occurred at 585 deg. C, might have been caused by melting of the Type 6061 aluminum alloy. The last release of fission product gases occurred at 650 deg. C, which probably corresponds to the eutectic temperature of the uranium-aluminum alloy. The released material was mostly xenon, and small amounts of iodine and cesium were observed. (author). Abstract only

Part of:
Research reactor core conversion guidebook. V. 4: Fuels (Appendices I-K)

Additional details

Publishing Information

Imprint Title
Research reactor core conversion guidebook. V. 4: Fuels (Appendices I-K)
Imprint Pagination
594 p.
Journal Page Range
p. 419.
ISSN
1011-4289
Report number
IAEA-TECDOC--643(v.4)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
23087414
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Descriptors DEI
ALUMINIUM; CLADDING; FISSION PRODUCT RELEASE; FUEL PLATES; HEATING; MELTING POINTS; MODERATELY ENRICHED URANIUM; RARE GASES; RESEARCH REACTORS; TEMPERATURE RANGE 0400-1000 K
Descriptors DEC
ACTINIDES; DEPOSITION; ELEMENTS; ENRICHED URANIUM; FUEL ELEMENTS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NONMETALS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SURFACE COATING; TEMPERATURE RANGE; THERMODYNAMIC PROPERTIES; TRANSITION TEMPERATURE; URANIUM

Optional Information

Notes
The full text of this paper was published in Nuclear Science and Engineering, 87, 405-417 (1984).