IFR safety tests M2 and M3 in TREAT [electronic resource] : data and analysis.
TREAT tests M2 and M3 were performed to obtain information on the characteristics of metal-alloy reactor fuel under slow transient overpower accident conditions, in particular, the margin to cladding breach and the axial self-extrusion of fuel within intact cladding. The tests used U-5Fs fuel pins i...
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Online Access (via OSTI) |
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Corporate Author: | |
Format: | Government Document Electronic eBook |
Language: | English |
Published: |
Washington, D.C. : Oak Ridge, Tenn. :
United States. Department of Energy. ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1985.
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Subjects: |
Summary: | TREAT tests M2 and M3 were performed to obtain information on the characteristics of metal-alloy reactor fuel under slow transient overpower accident conditions, in particular, the margin to cladding breach and the axial self-extrusion of fuel within intact cladding. The tests used U-5Fs fuel pins irradiated to burnup levels of 0.3 at. %, 4.5 at. % and 7.9 at. %. Each pin was located in a separte flowtube and cooled by flowing sodium. In one test, a pin of each burnup was heated to incipient cladding breach. In the other, pins of the medium and high burnup levels wer heated to slightly beyond breach. Pre- and post-failure fuel motions were monitored by the fast-neutron hodoscope. The time and axial location of cladding breach were determined from the test-loop instrumentation. Computations of fuel extrusion and cladding failure are desribed. The models used in the computations include effects of retained fission gas expansion, vaporization of the sodium-bond annulus in low burnup fuel, and cladding-wall thinning by eutectic formation. |
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Item Description: | Published through SciTech Connect. 06/01/1985. "anl-ifr--18" "TI85028591" Robinson, W R; Lo, R K; Bauer, T H; Froehle, P H; Helenberg, H W; Morman, J A; Stanford, G S; Wright, A E. |
Physical Description: | 173 p. : digital, PDF file. |