kw.\*:("Plutonio Óxido")
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An estimate of the high temperature, metal rich phase boundary of plutonium sesquioxideSHELDON, Robert I.Journal of nuclear materials. 2001, Vol 297, Num 3, pp 358-360, issn 0022-3115Article
Self-excited plutonium X-ray emission in plutonium-bearing materialsFRAZZOLI, F. V; REMETTI, R; GUARDINI, S et al.Nuclear technology. 1999, Vol 126, Num 2, pp 205-214, issn 0029-5450Article
Alternative versions of inert matrix fuel for the use of civil and weapons-grade plutonium in reactorsVATULIN, A; LYSENKO, V; KOSTOMAROV, V et al.Journal of nuclear materials. 1999, Vol 274, Num 1-2, pp 135-138, issn 0022-3115Conference Paper
Possibility of using mixed dioxide fuel in the VK-300 reactorVIKULOV, V. K; ILYUKHIN, V. I; MITYAEV, Yu. I et al.Atomic energy (New York, N.Y.). 1998, Vol 85, Num 3, pp 635-641, issn 1063-4258Article
The advanced MIMAS processDUCROUX, R; COUTY, Y; LEROUX, J. C et al.International nuclear conference on recycling, conditioning and disposal. 1998, pp 955-959, 3VolConference Paper
Ultrasonic inspection of MOX rodsKAPLAN, P; GOUYAUD, F; WATANABE, K et al.International nuclear conference on recycling, conditioning and disposal. 1998, pp 261-265, 3VolConference Paper
The physical chemistry for regenerating spent uranium and plutonium oxide fuel by recrystallization from molybdate meltsUSTINOV, O. A.Atomic energy (New York, N.Y.). 1997, Vol 82, Num 2, pp 99-102, issn 1063-4258Article
Sintering study of hyperstoichiometric powder compacts of UO2+x-(6mol%)PuO2HUET, F; GAUDREAU, B; DEHAUDT, P et al.Key engineering materials. 1997, pp 932-935, issn 1013-9826, isbn 0-87849-761-7, 3VolConference Paper
Synthesis of plutonium trifluoride from weapons plutonium as a potential fuel for power reactorsGREBENKIN, K. F; ZUEV, Yu N; LOBANOV, V. I et al.Atomic energy (New York, N.Y.). 1997, Vol 83, Num 2, pp 614-621, issn 1063-4258Conference Paper
Determination of the modified conversion ratio of light-water-moderated uranium-plutonium mixed-oxide-fuel latticeNAKAJIMA, K; AKAI, M; SUZAKI, T et al.Nuclear science and engineering. 1995, Vol 119, Num 3, pp 175-181, issn 0029-5639Article
Thermal conductivity of (U, Pu)O2-x mixed oxide fuelPHILIPPONNEAU, Y.Journal of nuclear materials. 1992, Vol 188, pp 194-197, issn 0022-3115Conference Paper
NOUVELLES METHODES DE CO-CONVERSION PAR VOIE AQUEUSE DE L'URANIUM (IV) ET DU PLUTONIUM(IV) POUR PREPARER DES OXYDES MIXTES (U, PU)O2 EN VUE DE LA FABRICATION DE COMBUSTIBLES MOX = NEW METHODS FOR CO-CONVERSION OF URANIUM(IV) AND PLUTONIUM(IV) IN AQUEOUS MEDIUM TO PREPARE MIXTES OXIDES (U, PU)O2 FOR MOX FUELSMesmin, Claire; Madic, Charles.2000, 235 p.Thesis
Development of fresh fuel packaging for ATR demonstration reactorOUCHI, Y; YAMANAKA, R; KURAKAMI, J et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 1738-1743, 4VolConference Paper
Transport and storage of MOX fuels methodology for criticality assessment methodsGUILLOU, E; LEJEUNE, E; AGUIAR, L et al.International conference on the packaging and transportation of radioactive materials. 1998, pp 1829-1833, 4VolConference Paper
The development of BNFL's MOX fuel supply businessEDWARDS, J; BROWN, C; MARSHALL, S. J et al.International nuclear conference on recycling, conditioning and disposal. 1998, pp 182-190, 3VolConference Paper
Fabrication and study of the properties of PuO2-MgO fuel pelletsKURINA, I. S; MOSEEV, L. I.Atomic energy (New York, N.Y.). 1997, Vol 82, Num 5, pp 347-350, issn 1063-4258Article
Le combustible MOX et l'usine de fabrication Melox : Le plutonium = MOX fuel and the Melox plantFOURNIER, W; DALVERNY, G.Revue générale nucléaire. 1995, Num 1, pp 34-39, issn 0335-5004Article
Criticality data and validation studies of arrays of mixed-oxide fuel pins in aqueous and organic solutionsSMOLEN, G. R; BIERMAN, S. R; FUKUMURA, N et al.Nuclear technology. 1994, Vol 107, Num 3, pp 285-303, issn 0029-5450Article
MOX fuels recyclingGAY, A.International nuclear conference on recycling, conditioning and disposal. 1998, pp 198-205, 3VolConference Paper
Multiple recycling of plutonium in advanced PWRsKLOOSTERMAN, J. L.International nuclear conference on recycling, conditioning and disposal. 1998, pp 266-273, 3VolConference Paper
Volatile molecule PuO3 observed from subliming plutonium dioxideRONCHI, C; CAPONE, F; COLLE, J. Y et al.Journal of nuclear materials. 2000, Vol 280, Num 1, pp 111-115, issn 0022-3115Article
Melox : une usine clef pour le prochain siècle = Melox : A key plant for the next centuryTechnologies France (Strasbourg). 1998, Num 46, pp 6-7, issn 1257-2489, 4 p.Article
Effect of the boundary conditions in multigroup calculations of cells in reactors with mixed oxide fuelSULTANOV, N. V.Atomic energy (New York, N.Y.). 1998, Vol 85, Num 3, pp 608-615, issn 1063-4258Article
MX8 : The next generation high capacity system for land transport of MOX fuelISSARD, H; BRACHET, Y; PENOTY, M et al.International nuclear conference on recycling, conditioning and disposal. 1998, pp 947-951, 3VolConference Paper
MOX : Les réponses du fournisseur de combustible aux attentes de l'électricien = MOX : respense of fuel supplier to electrical engineer requirements1987-1997 : 10 ans de combustibles MOX en France. Colloque. 1997, pp 1-8Conference Paper