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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| 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: |
MARC
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| 245 | 0 | 0 | |a IFR safety tests M2 and M3 in TREAT |h [electronic resource] : |b data and analysis. |
| 260 | |a Washington, D.C. : |b United States. Department of Energy. ; |a Oak Ridge, Tenn. : |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, |c 1985. | ||
| 300 | |a 173 p. : |b digital, PDF file. | ||
| 336 | |a text |b txt |2 rdacontent. | ||
| 337 | |a computer |b c |2 rdamedia. | ||
| 338 | |a online resource |b cr |2 rdacarrier. | ||
| 500 | |a Published through SciTech Connect. | ||
| 500 | |a 06/01/1985. | ||
| 500 | |a "anl-ifr--18" | ||
| 500 | |a "TI85028591" | ||
| 500 | |a Robinson, W R; Lo, R K; Bauer, T H; Froehle, P H; Helenberg, H W; Morman, J A; Stanford, G S; Wright, A E. | ||
| 520 | 3 | |a 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. | |
| 536 | |b W-31-109-ENG-38. | ||
| 650 | 7 | |a Treat Reactor. |2 local. | |
| 650 | 7 | |a Ifr Reactor. |2 local. | |
| 650 | 7 | |a Transient Overpower Accidents. |2 local. | |
| 650 | 7 | |a Ebr-2 Reactor. |2 local. | |
| 650 | 7 | |a Fuel Pins. |2 local. | |
| 650 | 7 | |a Fuel Element Failure. |2 local. | |
| 650 | 7 | |a General Studies Of Nuclear Reactors. |2 edbsc. | |
| 710 | 2 | |a Argonne National Laboratory. |4 res. | |
| 710 | 1 | |a United States. |b Department of Energy. |4 spn. | |
| 710 | 1 | |a United States. |b Department of Energy. |b Office of Scientific and Technical Information. |4 dst. | |
| 856 | 4 | 0 | |u http://www.osti.gov/scitech/biblio/712225 |z Online Access (via OSTI) |
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| 952 | f | f | |p Can circulate |a University of Colorado Boulder |b Online |c Online |d Online |e E 1.99:anl-ifr--18 |h Superintendent of Documents classification |i web |n 1 |