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kw.\*:("Liquid metal reactor")

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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

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

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

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

Numerical simulation of non-premixed diffusion flame and reaction product aerosol behavior in liquid metal pool combustionYAMAGUCHI, Akira; TAJIMA, Yuji.Journal of Nuclear Science and Technology. 2003, Vol 40, Num 2, pp 93-103, issn 0022-3131, 11 p.Article

Cleaning cesium radionuclides from BN-350 primary sodiumROMANENKO, O. G; ALLEN, K. J; TIKHOMIROV, L et al.Nuclear technology. 2005, Vol 150, Num 1, pp 79-99, issn 0029-5450, 21 p.Article

BREVET. CHAUDIERE NUCLEAIRE A NEUTRONS RAPIDES A METAL LIQUIDE CALPORTEUR1980; ; FRA; DA. 1980-02-22; FR/A1/2.429.477; DEP.7818821/1978-06-23Patent

ERFAHRUNGEN ZUR NATRIUMTECHNOLOGIE AN DEN SCHNELLEN REAKTOREN DER UDSSR = EXPERIENCES WITH SODIUM TECHNOLOGY IN USSR FAST BREEDER = EXPERIENCES ACQUISES DANS LA TECHNOLOGIE DU SODIUM DES SURREGENERATEURS RAPIDES EN URSSKARPOV AV; ARCHIPOV VM; ARCHANGEL'SKIJ VV et al.1978; KERNENERGIE; DEU; DA. 1978; VOL. 21; NO 10; PP. 322-326; ABS. ENG/RUS; BIBL. 11 REF.Article

BREVET 2.288.285 (A1) (7527369). - 5 SEPTEMBRE 1975. ECHANGEUR DE CHALEUR METAL LIQUIDE-EAU AVEC FAISCEAUX TUBULAIRES INTERCHANGEABLES.sdPatent

BREVET. CHAUDIERE NUCLEAIRE A NEUTRONS RAPIDES A METAL LIQUIDE CALOPORTEUR1980; ; FRA; DA. 1980-02-22; FR/A1/2.429.479; DEP.7818823/1978-06-23Patent

METHOD FOR DETERMINATION OF SATURATED TEMPERATURE WITH AUTOMATIC PLUGGING INDICATORYAMAMOTO H; SUMIDA I; IZUMI S et al.1979; J. NUCL. SCI. TECHNOL.; ISSN 0022-3131; JPN; DA. 1979; VOL. 16; NO 6; PP. 383-389; BIBL. 8 REF.Article

THE VALUE OF PROTOTYPE TESTING IN THE DEVELOPMENT OF THE IN-VESSEL HANDLING MACHINE FOR FFTFSHARBAUGH JE.1979; J. ENG. POWER; ISSN 0022-0825; USA; DA. 1979; VOL. 101; NO 4; PP. 651-654Article

FAST REACTOR SAFETYSMITH RD.1981; NUCL. ENERGY (1978); ISSN 0140-4067; GBR; DA. 1981; VOL. 20; NO 1; PP. 49-54Article

INHERENT SAFETY IN THE DESIGN OF FUTURE NUCLEAR PLANTSLANTZ E.1980; NUCL. TECHNOL.; ISSN 0029-5450; USA; DA. 1980; VOL. 50; NO 2; PP. 136-147; BIBL. 13 REF.Article

VERIFICATION OF A DYNAMICS MODEL OF A SODIUM HEATED STEAM GENERATORIZUME A; KUBOTA J.1980; BOILER DYNAMICS AND CONTROL IN NUCLEAR POWER STATIONS. 2 INTERNATIONAL SYMPOSIUM. 2/1979/BOURNEMOUTH; GBR; LONDON: BRITISH NUCLEAR ENERGY SOCIETY; DA. 1980; PP. 61-129; 13 P.; BIBL. 3 REF.Conference Paper

EXPERIENCE DE CINQ ANNEES DE FONCTIONNEMENT DE PHENIX = FOUR YEARS OPERATING EXPERIENCE WITH PHENIXCONTE F.1980; TECH. DE L'ENERG.; FRA; DA. 1980; NO 38; PP. 53-56; ABS. ENGArticle

SUPERPHENIX, UNE REALISATION QUI FERA DATE DANS LES ANNALES DU XXEME SIECLE = SUPERPHENIX: A KEY PROJECT OF THE XXTH CENTURY1980; TECH. DE L'ENERG.; FRA; DA. 1980; NO 38; PP. 57-61; ABS. ENG; BIBL. 2 REF.Article

AUFGABEN UND METHODEN ZUR KONTROLLE DER VERUNREINIGUNGEN IN NATRIUMKREISLAEUFEN. = TASKS AND METHODS FOR IMPURITY CONTROL IN SODIUM LOOPS = EXIGENCES ET METHODOLOGIE POUR LE CONTROLE DE LA PURITE DANS LES CIRCUITS A SODIUM LIQUIDEULLMANN H.1977; KERNENERGIE; DTSCH.; DA. 1977; VOL. 20; NO 9; PP. 269-274; ABS. ANGL. RUSSE; BIBL. 34 REF.Article

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