Pascal and Francis Bibliographic Databases

Help

Search results

Your search

kw.\*:("Réacteur métal liquide")

Document Type [dt]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Publication Year[py]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Discipline (document) [di]

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Language

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Author Country

A-Z Z-A Frequency ↓ Frequency ↑
Export in CSV

Results 1 to 25 of 444

  • Page / 18
Export

Selection :

  • and

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

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

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

Passive safety testing at the fast flux test facilityLUCOFF, D. M.Nuclear technology. 1989, Vol 88, Num 1, pp 21-29, issn 0029-5450Article

Damping in LMFBR pipe systemsANDERSON, M. J; BARTA, D. A; LINDQUIST, M. R et al.Journal of pressure vessel technology. 1985, Vol 107, Num 4, pp 366-372, issn 0094-9930Article

The fast reactor: perspective and prospectsHIRSCH, P.Nuclear energy (1978). 1983, Vol 22, Num 6, pp 401-415, issn 0140-4067Article

BACCHUS-3D/SP: a computer programme for the three-dimensional description of sodium single-phase flow in bundle geometryBOTTONI, M; DORR, B; HOMANN, C et al.Kernforschungszentrum Karlsruhe. 1983, Num 3376, issn 0303-4003, V-186 pSerial Issue

Simulation of molten metal freezing behavior on to a structureMIZANUR RAHMAN, M; EGE, Yoshiyuki; MORITA, Koji et al.Nuclear engineering and design. 2008, Vol 238, Num 10, pp 2706-2717, issn 0029-5493, 12 p.Article

Thermohydraulic optimization of liquid metal self-cooled breeding blanketsKIRILLOV, I. R; VITKOVSKY, I. V.SOFT : Symposium on fusion technology. 1998, 2Vol, Vol 2, 1175-1178Conference Paper

Basic concepts for the liquid-metal target loop of accelerator-controlled reactorsBEZONOSOV, A. V; VESHNYAKOV, K. B; SEROV, V. E et al.Atomic energy (New York, N.Y.). 1996, Vol 81, Num 3, pp 647-650, issn 1063-4258Article

Application of the vortex method analysis of coolant temperature fluctuationAMANO, K; ISHIDA, M.Nuclear technology. 1986, Vol 73, Num 2, pp 243-251, issn 0029-5450Article

The development of breeder reactors in the United StatesKOUTS, H.Annual review of energy. 1983, Vol 8, pp 385-413, issn 0362-1626Article

  • Page / 18