kw.\*:("Combustible nucléaire")
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Stowing of packages containing radioactive materials on conveyances in normal and accidental conditionsDRAULANS, J; CHEVALIER, G; GILLES, P et al.Revue énergie primaire. 1985, Vol 19, Num 3-4, pp 29-36, issn 0556-7734Article
Fields of application of the third party nuclear liability of the Paris ConventionMEES, M; CHRISTIAENS, L.Revue énergie primaire. 1985, Vol 19, Num 3-4, pp 37-44, issn 0556-7734Article
Reaction layer growth and reaction heat of U-Mo/Al dispersion fuels using centrifugally atomized powdersHO JIN RYU; YOUNG SOO HAN; JONG MAN PARK et al.Journal of nuclear materials. 2003, Vol 321, Num 2-3, pp 210-220, issn 0022-3115, 11 p.Article
Effect of reducing fuel enrichment on the Void reactivity. II: Analytical studySENDA, Y; SHIROYA, S; HAYASHI, M et al.Nuclear technology. 1985, Vol 70, Num 3, pp 318-334, issn 0029-5450Article
Le transport des matières radioactives dans le cycle du combustibleFRADIN, J.Revue énergie primaire. 1985, Vol 19, Num 3-4, pp 4-20, issn 0556-7734Article
Plentiful energy supplies for 21st century = Des approvisionnements d'énergie abondants au 21ème sièclePetroleum review (London. 1968). 1999, Vol 53, Num 626, pp 35-37, issn 0020-3076Article
S.G.N.: une bonne progression = SGN: a good increaseÉnergie magazine. 1986, Num 83-84, pp 34-36, issn 0755-5202Article
L'enrichissement au Tricastin: les raisons d'une bonne santé = Enrichment at Tricastin: the reasons for successÉnergie magazine. 1986, Num 83-84, pp 32-33, issn 0755-5202Article
A THEORETICAL MODEL WITH VARIABLE MASSES FOR THE MOLTEN FUEL-SODIUM THERMAL INTERACTION IN A NUCLEAR FAST REACTOR. = UN MODELE THEORIQUE A MASSES VARIABLES POUR L'INTERACTION THERMIQUE COMBUSTIBLE FONDU-SODIUM DANS UN REACTEUR NUCLEAIRE RAPIDECALDAROLA L.1975; NUCL. ENGNG DESIGN; NETHERL.; DA. 1975; VOL. 34; NO 2; PP. 181-201; BIBL. 9 REF.Article
A thermodynamic study of the uranium-americium oxide U0,5Am0,5 O2±xBARTSCHER, W; SARI, C.Journal of nuclear materials. 1983, Vol 118, Num 2-3, pp 220-223, issn 0022-3115Article
PROBLEME DES WAERMEUEBERGANGES IN BRENNSTAEBEN IN DER REAKTORDYNAMIK. = PROBLEMS OF FUEL ROD HEAT TRANSFER IN REACTOR DYNAMICS = PROBLEMES DU TRANSFERT DE CHALEUR DANS LES BARRES COMBUSTIBLES DANS LA DYNAMIQUE DES REACTEURSBROSCHE D.1975; ATOMWIRTSCH. ATOMTECH.; DTSCH.; DA. 1975; VOL. 20; NO 10; PP. 513-514; BIBL. 5 REF.Article
Development and fabrication of 70% PuC-30% UC fuel for the fast breeder test reactor in IndiaCHAITANYAMOY GANGULY; PARAMESHWAR VENKAPPA HEGDE; GYAN CHAND JAIN et al.Nuclear technology. 1986, Vol 72, Num 1, pp 59-69, issn 0029-5450Article
Thermal oxide reprocessing at SellafieldBENNETT, B.Chemical engineer (London). 1985, Num 415, pp 35-38, issn 0302-0797Article
Retraitement des combustibles «rapides». TOR bientôt en service = Reprocessing «rapid» fuels. TOR soon operatingRevue générale nucléaire. 1985, Vol 3, pp 259-260, issn 0335-5004Article
Expérience in the international transport of irradiated fuelCURTIS, H. W.Revue énergie primaire. 1985, Vol 19, Num 3-4, pp 21-27, issn 0556-7734Article
A strategy for fueling large prototype fast reactorsBRAUN, C; GOLAN, S.Atomkernenergie, Kerntechnik. 1984, Vol 45, Num 1, pp 29-30, issn 0171-5747Article
Alimentation électrique de l'usine Eurodif du Tricastin = Power supply of Eurodif plant at TricastinDE SARRAZIN, B.Énergie magazine. 1984, Num 74, pp 43-46, issn 0755-5202Article
Carbothermic synthesis of uranium-plutonium mixed carbideSUZUKI, Y; ARAI, Y; SASAYAMA, T et al.Journal of Nuclear Science and Technology. 1983, Vol 20, Num 7, pp 603-610, issn 0022-3131Article
Nuclear fuel cyclesOLDS, F. C.Power engineering (Barrington, IL.). 1983, Vol 87, Num 10, pp 42-50, issn 0032-5961Article
Oxygen potential and lattice parameter measurements in (U, Ce)O2-xNORRIS, D. I. R; KAY, P.Journal of nuclear materials. 1983, Vol 116, Num 2-3, pp 184-194, issn 0022-3115Article
Recueil des communications/Journée retraitement des combustibles irradiés, Paris, 8 novembre 1983 = Proceedings/Meeting on used fuel reprocessing, Paris, 8th November 1983Journée retraitement des combustibles irradiés. 1983, 107 p.Conference Proceedings
Les technologies du retraitement = The reprocessing technologiesCHAMBON, M.Journée retraitement des combustibles irradiés. 1983, pp 24-34Conference Paper
Gamma Decomposition and Powder Formation of γ-UBMo Nuclear Fuel Alloys via a Hydration―Dehydration ProcessBRANCO VAZ DE OLIVEIRA, Fabio; BERNARDIN, Adriano Michael; RIELLA, Humberto Gracher et al.Industrial & engineering chemistry research. 2012, Vol 51, Num 24, pp 8237-8245, issn 0888-5885, 9 p.Article
Nuclear Fuel Cycle : Environmental ImpactEWING, Rodney C.MRS bulletin. 2008, Vol 33, Num 4, pp 338-340, issn 0883-7694, 3 p.Article
Enrichissement de l'uranium par ultracentrifugation : Cycle du combustible : Recherches et réalisations = Fuel cycle : Research and achievements = Uranium enrichment by ultracentrifugationSOUBBARAMAYER, M.Revue générale nucléaire. 1996, Num 2, issn 0335-5004, p. 17Article