Swelling behavior of U-Pu-Zr fuel

Hofman, G.L.; Pahl, R.; Lahm, C.E.; Porter, David

doi:10.1007/bf02671924

Cited by 125 publications

(39 citation statements)

References 1 publication

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Diametric swelling of the fuel slug was calculated as 4 ADID, % TEMPERATURE, OC Fig.3. Experimental (above, [ 1,2]) and VACS-calculated (below) diametric swelling at 0.9 at.% burnup under EBR-I1 conditions. 3D/D=AV/V, taking into account an average radial fuel temperature gradient of 13U' C.…”

Section: Modeling Of U-1ozr Swelling Behavior By a Vacancy Mechanismmentioning

confidence: 99%

Analysis of the swelling behavior of U-alloys

Rest¹,

Hofman²,

Coffey³

et al. 1997

View full text Add to dashboard Cite

The submitud manuscrip1 has been authored by a contractor AbstractAvailable data on two alloys from the EBR-II driver fuel development program have been utilized in the construction and validation of mechanistic models aimed at elucidating swelling mechanisms in high density uranium alloys. Swelling predictions are made under ATR conditions for U-1OMo fuels, currently under irradiation in the ATR, and for U-1OZr.

show abstract

Section: Modeling Of U-1ozr Swelling Behavior By a Vacancy Mechanismmentioning

confidence: 99%

Analysis of the swelling behavior of U-alloys

Rest¹,

Hofman²,

Coffey³

et al. 1997

View full text Add to dashboard Cite

show abstract

“…As shown in Fig. 9, the axial swelling of the METAPHIX fuels is within the predicted range, considering the uncertainties of the experimental data (AE1{2% [21][22][23] in EBR-II test fuels).…”

Section: Axial Swelling Of Fuel Alloymentioning

confidence: 59%

Development of Fast Reactor Metal Fuels Containing Minor Actinides

Ohta

Ogata

Dimitrios

et al. 2011

Journal of Nuclear Science and Technology

View full text Add to dashboard Cite

Fast reactor metal fuels containing minor actinides (MAs) Np, Am, and Cm and rare earths (REs) Y, Nd, Ce, and Gd are being developed by the Central Research Institute of Electric Power Industry (CRIEPI) in collaboration with the Institute for Transuranium Elements (ITU) in the METAPHIX project. The basic properties of U-Pu-Zr alloys containing MA (and RE) were characterized by performing ex-reactor experiments. On the basis of the results, test fuel pins including U-Pu-Zr-MA(-RE) alloy ingots in parts of the fuel stack were fabricated and irradiated up to a maximum burnup of $10 at% in the Phénix fast reactor (France). Nondestructive postirradiation tests confirmed that no significant damage to the fuel pins occurred. At present, detailed destructive postirradiation examinations are being carried out at ITU.

show abstract

“…10(c)). The grains of this type in U-Pu-Zr alloys have been reported to be zirconium with impurities (O, N and C) in previous studies [6,7]. At a fast cooling rate of 10°C/min, the massive Zr(O) grains, which were found at the slow cooling rate of 2°C/min, were not observed, and the lath-type a-Zr precipitates were finely distributed throughout the matrix (Fig.…”

Section: Resultsmentioning

confidence: 79%