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INDENTIFICATION AND PRODUCTION OF PLUTONIUM MONO-OXIDERESHETNIKOV, F. G.Atomic energy (New York, N.Y.). 2007, Vol 103, Num 5, pp 911-913, issn 1063-4258, 3 p.Article

DISTRIBUTION OF INHALED 239PUO2 IN RAT HAMSTER LUNGRHOADS K; MAHAFFEY JA; SANDERS CL et al.1982; HEALTH PHYS.; ISSN 0017-9078; USA; DA. 1982; VOL. 42; NO 5; PP. 645-656; BIBL. 2 P.Article

A MORPHOMETRIC STUDY OF RAT AND HAMSTER LUNG FOLLOWING INHALATION OF 239PUO2RHOADS K; MAHAFFEY JA; SANDERS CL et al.1981; RADIAT. RES.; ISSN 0033-7587; USA; DA. 1981; VOL. 88; NO 2; PP. 266-279; BIBL. 39 REF.Article

An alternative structure of Pu4O9 (PuO2.25) incorporating interstitial hydroxyl rather than oxidePENNEMAN, R. A; PAFFETT, M. T.Journal of solid state chemistry (Print). 2005, Vol 178, Num 2, pp 563-566, issn 0022-4596, 4 p.Article

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

Dissolution of PuO2 in hydrochloric acid medium: effect of reducing agentsSHAKILA ABDUL MAJEED; THANDANGORAI GANAPATAI SRINIVASAN; KANWAL NAIN SABHARWAL et al.Nuclear technology. 1989, Vol 88, Num 3, pp 290-293, issn 0029-5450Article

Progressive development of PuO2 packagesNUTTALL, P. A; ROBERTSON, R. I.International conference on nuclear fuel reprocessing and waste management. 1987, pp 857-866Conference 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

Oxidation and pulverization of UO2 and mox pelletsSEEHARS, D; HOCHRAINER, D.Journal of nuclear materials. 1989, Vol 166, Num 1-2, pp 214-217, issn 0022-3115, 0Conference Paper

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