Annual Progress Report on Reactor Fuels and Materials Development for Fy 1964

Graber, M.J.; Zelezny, W.F.; Gibson, G. W.

doi:10.2172/4609980

Cited by 6 publications

(2 citation statements)

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“…We understand, however, that concerns about problems presented by uranium silicide fuels in the back end of the fuel cycle have prompted some consideration of the use of UN as a substitute for U3Si2. We have found only one reference to irradiation of UN-AI fuel [12]. The swelling of UN-A1 fuel at about 14 vol.% loading was found to be greater than that of U308-AI fuel at a similar volume loading.…”

Section: Unmentioning

confidence: 88%

Development of very-high-density low-enriched-uranium fuels

Snelgrove

Hofman

Meyer

et al. 1997

Nuclear Engineering and Design

251

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Section: Unmentioning

confidence: 88%

Development of very-high-density low-enriched-uranium fuels

Snelgrove

Hofman

Meyer

et al. 1997

Nuclear Engineering and Design

251

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“…Studies on aluminides [110] showed that UAl 2 reacts rapidly, and UA13 reacts slowly, with aluminum to form the stable compound UA14, which undergoes no further reaction with Al. A mixture of aluminides, designated UAlx but compositionally close to UA1 3 , will therefore react with aluminum in the reactor, but at a slow rate.…”

Section: Stability Of Aluminide Fuelsmentioning

confidence: 99%

Fuels for research and test reactors, status review: July 1982

Stahl¹

1982

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U0 2 U0 2 U0 2 9.Microstructures of U 3 SiAl (U + 3.5 wt% Si + 1.5 wt% Al). Curves A-D show heat-flow data for fuels with x -1.58, 1.65, 1.7, and 1.8, respectively. Lines UL, LL, and MP indicate the upper limit, lower limit, and most probable value, respectively, for the thermal conductivity of fuel with x -1.6. Line A shows pulse-heating data for fuel with x -1.6, which do not agree with curve MP. ABSTRACTA thorough review is provided on nuclear fuels for steady-state thermal research and test reactors.The review was conducted to provide a documented data base in support of recent advances in research and test reactor fuel development, manufacture, and demonstration in response to current U.S. policy on availability of enriched uranium. The review covers current fabrication practice, fabrication development efforts, irradiation performance, and properties affecting fuel utilization, including thermal conductivity, specific heat, density, thermal expansion, corrosion, phase stability, mechanical properties, and fission-product release. The emphasis is on U.S. activities, but major work in Europe and elsewhere is included. The standard fuel types discussed are the U-Al alloy and the UAl -Al and U 3 0 8 -Al dispersion plate fuels, and the U-Al alloy, UZrHx, and U0 2 rod fuels. Among new fuels, those given major emphasis include U 3 Si-Al dispersion and b0 2 caramel plate fuels.

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Dispersion Fuels

Snelgrove

Hofman

2006

Materials Science and Technology

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Annual Progress Report on Reactor Fuels and Materials Development for Fy 1964

Cited by 6 publications

References 0 publications

Development of very-high-density low-enriched-uranium fuels

Development of very-high-density low-enriched-uranium fuels

Fuels for research and test reactors, status review: July 1982

Dispersion Fuels

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