Fabrication of Powder from Ductile U-Mo Alloys for Use as Nuclear Dispersion

Michelangelo Durazzo; Cláudio José da Rocha; José Mestnik-Filho; Ricardo Mendes Leal Neto

doi:10.4028/www.scientific.net/MSF.727-728.362

Paper Titles

Covering with Carbon Black and Thermal Treatment by a CO₂ Laser Surfaces of Aisi 4340 Steel
p.340

Coated Steel Surfaces with WC by Lasers Action
p.345

Application of Sintered Steel for Synchronizer Rings Used in Mechanical Transmissions
p.349

Recycling of Zircaloy Machining Chips by VAR Remelting and Powder Metallurgy Techniques
p.356

Fabrication of Powder from Ductile U-Mo Alloys for Use as Nuclear Dispersion
p.362

Study of Sol-Gel/Powder Metallurgy Technique for Processing Titanium Parts
p.368

Quantitative Evaluation of Interstitial Elements in the Processing of Ti-6Al-4V Alloy by Powder Metallurgy
p.374

The Possibility of Production of Cemented Carbide under High Pressure and High Temperature
p.380

Effect of the Impurities on the Phosphoric Acid Process
p.386

HomeMaterials Science ForumMaterials Science Forum Vols. 727-728Fabrication of Powder from Ductile U-Mo Alloys for...

Fabrication of Powder from Ductile U-Mo Alloys for Use as Nuclear Dispersion

Abstract:

For the last 30 years high uranium density dispersion fuels have been developed in order to accomplish the low enrichment goals of the Reduced Enrichment for Research and Test Reactors (RERTR) Program. Gamma U-Mo alloys, particularly with 7 to 10 wt% Mo, as a fuel phase dispersed in aluminum matrix, have shown good results concerning its performance under irradiation tests. Thats why this fissile phase is considered to be used in the nuclear fuel of the Brazilian Multipurpose Research Reactor (RMB), currently being designed. Powder production from these ductile alloys has been attained by atomization, mechanical (machining, grinding, cryogenic milling) and chemical (hydriding-dehydriding) methods. This work is a part of the efforts presently under way at IPEN to investigate the feasibility of these methods. Results on alloy fabrication by induction melting and γ-stabilization of U-10Mo alloys are presented. Some results on powder production and characterization are also discussed.

You might also be interested in these eBooks

View Preview

Info:

Periodical:

Materials Science Forum (Volumes 727-728)

Pages:

362-367

DOI:

https://doi.org/10.4028/www.scientific.net/MSF.727-728.362

Citation:

Cite this paper

Online since:

August 2012

Authors:

Michelangelo Durazzo, Cláudio José da Rocha, José Mestnik-Filho, Ricardo Mendes Leal Neto

Keywords:

Dispersion Fuel, Nuclear Fuel, Powder Fabrication, U-Mo Alloy, UMo-Al Dispersion

Export:

RIS, BibTeX

Price:

Permissions CCC:

Request Permissions

Permissions PLS:

Request Permissions

Сopyright:

Citation:

References

[1] J.L. Snelgrove, M. K Meyer, C. L Trybus and T. C Wiencek: Nuclear Engineering and Design Vol. 179 (1997), p.119.

Google Scholar

[2] G.L. Hofman, J.L. Snelgrove, S.L. Hayes and M.K. Meyer, in: 6th International Topical Meeting on Research Reactor Fuel Management. Ghent, March 17 to 20, 2002. Proceeding.. Ghent (2002), p.50 (Belgium).

Google Scholar

[3] K.H. Kim, D.B. Lee, C.K. Kim, G.E. Hofman and K.W. Paik: J. Nuclear Materials Vol. 245 (1997), p.179.

Google Scholar

[4] C.R. Clark, B. Muntifering, J. Jue, M. Chapple, in: 29th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Prague, September 23-27, 2007. Proceeding.. Prague 2007. (Czech Republic).

Google Scholar

[5] C.R. Clark, M.K. Meyer and J.T. Strauss, in: 21st International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). São Paulo, October 18-23, 1998. Proceeding.. São Paulo 1998. (Brazil).

Google Scholar

[6] H. Vacelet, P. Sacristan, A. Languille, Y. Lavastre and M. Grasse, in: 22nd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Budapest, October 3-8, 1999. Proceeding.. Budapest 1999. (Hungary).

Google Scholar

[7] S. Balart, P. Bruzzoni, M. Granovsky, L. Gribaudo, J. Hermida, J. Ovejero, G . Rubiolo and E. Vicente, in: 23rd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Las Vegas, October 1-6, 2000. Proceeding.. Las Vegas 2000. (Nevada, USA).

Google Scholar

[8] M.I. Solonin, A.V. Vatulin, Y.A. Stetsky, Y.I. Trifonov and B.D. Rogozkin, in: 23rd International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Las Vegas, October 1-6, 2000. Proceeding.. Las Vegas 2000. (Nevada, USA).

Google Scholar

[9] F.B.V. Oliveira, M. Durazzo, E. Carvalho, A. Saliba-Silva and H. Riella, in: 29th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Prague, September 23-27, 2007. Proceeding.. Prague 2007. (Czech Republic).

Google Scholar

[10] L. Olivares, J. Marin, J. Lisboa and H. Pesenti, in: 30th RERTR 2008 International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Washington October 5-9, 2008. Proceeding.. Washington 2008. (USA).

Google Scholar

[11] E.E. Pasqualini, M. López, L.J. Helzel García, P. Echenique and P. Adelfang in: 24th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). San Carlos de Bariloche, November 3-8, 2002. Proceeding.. San Carlos de Bariloche 2002. (Argentina).

DOI: 10.22179/revmacn.6.68

Google Scholar

[12] G.L. Powell, J.W. Koger, R.K. Bennett, A.L. Willamson and V.C. Hemperly: Corrosion Vol. 32 (1976), p.442.

Google Scholar

[13] M. Durazzo, A. Silva, J. Souza, E. Carvalho and H. Riella, in: 29th International Meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Prague, September 23-27, 2007. Proceeding.. Prague 2007. (Czech Republic).

Google Scholar

[14] R.J. Van Thyne and D.J. McPherson: Transactions of the ASM Vol. 49 (1957), p.598.

Google Scholar