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kw.\*:("Réacteur métal liquide")

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Hydrodynamic characteristics of liquid-metal blankets of thermonuclear-power plantsKOREN', V. M; SALTYKOVSKY, A. V; FIRSOVA, E. V et al.Inženerno-fizičeskij žurnal. 1990, Vol 58, Num 2, pp 229-235, issn 0021-0285, 7 p.Article

Design of a complementary scram system for liquid metal cooled nuclear reactorsVANMAERCKE, S; VAN DEN EYNDE, G; TIJSKENS, E et al.Nuclear engineering and design. 2012, Vol 243, pp 87-94, issn 0029-5493, 8 p.Article

Seismic analysis of heavy-liquid-metal-cooled reactor vesselsBUONGIORNO, J; HAWKES, B. D.Nuclear engineering and design. 2004, Vol 228, Num 1-3, pp 305-317, issn 0029-5493, 13 p.Conference Paper

The modular reactor plantBLUMBERG, B.Proceedings of the American Power Conference. 1984, Vol 46, pp 694-695, issn 0097-2126Conference Paper

Innovative design of a low-cost breederDIFRANSICO, T. W; STADER, J. E.Power engineering (Barrington, IL.). 1985, Vol 82, Num 2, pp 53-56, issn 0032-5961Article

Le contrôle de la puissance thermique du réacteur BN-600 de la centrale nucléaire de BieloiarskSHEJNKMAN, A. G; KARPENKO, A. I; LYZHIN, A. A et al.Teploenergetika (Moskva, 1954). 1984, Num 2, pp 6-8, issn 0040-3636Article

Tribological coatings for liquid metal and irradiation environments = Revêtements tribologiques pour environnements de métal liquide et d'irradiationJOHNSON, R. N.Journal of materials for energy systems. 1986, Vol 8, Num 1, pp 27-37, issn 0162-9719Article

Investigation of a commercially available chemical power for extinguishing liquid metal pool firesRAJU, C; KALE, R. D.Nuclear engineering and design. 1984, Vol 77, Num 1, pp 109-113, issn 0029-5493Article

A low cost liquid metal reactor designHOWARD ARNOLD, W; ANDSERSON, C. A; MANGUS, J. D et al.Proceedings of the American Power Conference. 1984, Vol 46, pp 688-693, issn 0097-2126Conference Paper

Cost-competitive, inherently safe LMFBR pool plantMCDONALD, J. S; BRUNINGS, J. E; CHANG, Y. I et al.Proceedings of the American Power Conference. 1984, Vol 46, pp 696-700, issn 0097-2126Conference Paper

Temperature dependent attenuation of ex-vessel flux measurements at the Hanford fast flux test facilityMCLANE, F. E; WOOD, M. R; RATHBUN, J. L et al.Power plant dynamics. Control and testing symposium. 5. 1983, pp 43.01-43.11Conference Paper

HYDRAULIC PERFORMANCE OF TILTING-DISK CHECK VALVES. = PERFORMANCE HYDRAULIQUE DE VANNES DE CONTROLE A DISQUE BASCULANTKANE RS; CHO SM.1976; PROC. AMER. SOC. CIV. ENGRS, J. HYDRAUL. DIV.; U.S.A.; DA. 1976; VOL. 102; NO 1; PP. 57-72; BIBL. 10 REF.Article

PROGRESS TOWARD THE COMMERCIAL LMFBRMURRAY P; DYOS MW.1974; COMBUSTION; U.S.A.; DA. 1974; VOL. 45; NO 12; PP. 26-29; BIBL. 1 REF.Article

BEITRAG ZUR ENTWICKLUNG VON DAMPFERZEUGERN FUER NATRIUMGEKUEHLTE SBR-KERNKRAFTWERKE = CONTRIBUTION A LA MISE AU POINT DE GENERATEURS DE VAPEUR DESTINES AUX CENTRALES NUCLEAIRES REFROIDIES PAR SODIUMKRIZEK V; DUBSEK F.1973; ENERGIETECHNIK; DTSCH.; DA. 1973; VOL. 23; NO 3; PP. 134-135; BIBL. 6 REF.Serial Issue

BREVET 2.112.044 (B) (7028940). A 5 AOUT 1970. REACTEUR NUCLEAIRE REFROIDI PAR CIRCULATION DE METAL FONDUsdPatent

BREVET 2.228.194 (B) (7405276). A 15 FEVRIER 1974. GENERATEUR DE VAPEURsdPatent

IMPLICATIONS OF SMALL WATER LEAK REACTIONS ON SODIUM HEATED STEAM GENERATOR DESIGN. = IMPLICATIONS DES REACTIONS DE PETITES FUITES D'EAU SUR LA CONCEPTION DE GENERATEURS DE VAPEUR CHAUFFES AU SODIUMSMEDLEY JA.1976; J. BRIT. NUCL. ENERGY SOC.; G.B.; DA. 1976; VOL. 15; NO 2; PP. 153-156Article

ON SCHEMES OF SODIUM-STEAM GENERATORSKIRILLOV PL; POPLAVSKIJ VM.1976; ATOM. ENERG.; S.S.S.R.; DA. 1976; VOL. 40; NO 4; PP. 286-288Article

INSTRUMENTATION FOR CORE AND COOLANT MONITORING IN LIQUID-METAL FAST BREEDERS REACTORS (LMFBR) = INSTRUMENTATION POUR LA COMMANDE DU COEUR ET DU REFRIGERANT DANS LES SURREGENERATEURS RAPIDES REFROIDIS PAR METAL LIQUIDE (LMFBR)HESS B; RUPPERT E.1975; REV. ENERG. ATOM.; AUTR.; DA. 1975; VOL. 13; NO 1; PP. 81-144; BIBL. 6 P.Article

DOUNREAY FAST REACTOR OUTPUT BUILDS UP TO 40 MW1974; ELECTR. TIMES; G.B.; DA. 1974; NO 4305; PP. 22-23Article

Multiple recycling of light water reactor waste plutonium in a fast spectrum coreSEGEV, M; MISULOVIN, A; GALPERIN, A et al.Nuclear science and engineering. 1997, Vol 127, Num 2, pp 238-244, issn 0029-5639Article

PLANNING FOR THE SECOND LMFBR DEMONSTRATION PLANT: A 1000-MW COMMERCIAL TYPE = PLANIFICATION DE LA SECONDE CENTRALE DE DEMONSTRATION A REACTEUR LMFBR: UN TYPE COMMERCIAL DE 1000 MWNOYES RC; VITTI JA; PENFIELD SR et al.1974; COMBUSTION; U.S.A.; DA. 1974; VOL. 46; NO 3; PP. 5-11; BIBL. 7 REF.Article

Numerical investigation of multi-dimensional characteristics in sodium combustionTAKATA, Takashi; YAMAGUCHI, Akira; MAEKAWA, Isamu et al.Nuclear engineering and design. 2003, Vol 220, Num 1, pp 37-50, issn 0029-5493, 14 p.Article

Stability analysis of a liquid-metal reactor and its primary heat transport systemDEPIANTE, E. V.Nuclear engineering and design. 1994, Vol 152, Num 1-3, pp 361-377, issn 0029-5493Article

Key asset-inherent safety of LMFBR pool plantMARCHATERRE, J. F; SEVY, R. H; LANCET, R. T et al.Proceedings of the American Power Conference. 1984, Vol 46, pp 701-704, issn 0097-2126Conference Paper

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