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Increasing the power of the high temperature reactor moduleVAN HEEK, A. I.Nuclear engineering and design. 1994, Vol 150, Num 1, pp 183-189, issn 0029-5493Article

CEGB review of safety aspects of Magnox reactorsCLARKE, A. W; MATTHEWS, R. R.Nuclear energy (1978). 1986, Vol 25, Num 3, pp 169-175, issn 0140-4067Article

Loading of tubular filters in AGRBERGER, F. P; IJAZ, A.Nuclear engineering and design. 1994, Vol 152, Num 1-3, pp 91-101, issn 0029-5493Article

Der Hochtemperatur-Reaktor: Ergebnisbericht, Stand der Technik, Entwicklungspotential, Realisierung = High temperature reactor : results, state of the art, development potential, realization (Retrofitting, EPR, SWR 1000)KUGELER, K; BONNENBERG, H.VDI-Berichte. 1999, pp 147-169, issn 0083-5560, isbn 3-18-091493-9Conference Paper

The gas turbine-modular helium reactor (GT-MHR) for electricity generation and plutonium consumptionGORELOV, I. N; KIRYUSHIN, A. I; KODOCHIGOV, N. G et al.Atomic energy (New York, N.Y.). 1997, Vol 83, Num 6, pp 877-881, issn 1063-4258Article

Hunterston B advanced gas-cooled reactor : development of electrical auxiliary system with station lifeLOGIE, J. H; ROYSTON, D. E.Nuclear energy (1978). 1995, Vol 34, Num 6, pp 361-368, issn 0140-4067Conference Paper

Evaluation of local power distribution with fine-mesh core model for high temperature engineering test reactor (HTTR)MURATA, I; YAMASHITA, K; MARUYAMA, S et al.Journal of Nuclear Science and Technology. 1994, Vol 31, Num 1, pp 62-72, issn 0022-3131Article

Quantified risk assessment: a nuclear industry viewpointTHOMSON, J. R.Journal of loss prevention in the process industries. 1994, Vol 7, Num 5, pp 419-424, issn 0950-4230Article

Core safety characteristics of high flux safe reactor (HFSR)PENG HONG LIEM; SEKIMOTO, H.Journal of Nuclear Science and Technology. 1993, Vol 30, Num 7, pp 648-663, issn 0022-3131Article

Aseismic study of high temperature gas-cooled reactor core with block-type fuel. III: Effect of excitation directions and core support stiffnessIKUSHIMA, T; HONMA, T.Bulletin of the JSME. 1985, Vol 28, Num 246, pp 2986-2993, issn 0021-3764Article

Automatic X-ray inspection for escaped coated particles in spherical fuel elements of high temperature gas-cooled reactorMIN YANG; QI LIU; HONGSHENG ZHAO et al.Energy (Oxford). 2014, Vol 68, pp 385-398, issn 0360-5442, 14 p.Article

Deformation and fracture of irradiated polygranular pile grade A reactor core graphiteHEARD, P. J; WOOTTON, M. R; MOSKOVIC, R et al.Journal of nuclear materials. 2011, Vol 418, Num 1-3, pp 223-232, issn 0022-3115, 10 p.Article

Indirect helium cooled fast breeder reactor of enhanced safety with helium turbine system for electricity generation and freshwater production unitMORI, Y.JSME international journal. Series B, fluids and thermal engineering. 1999, Vol 42, Num 2, pp 300-309, issn 1340-8054Article

Fabrication & testing of the TN-FSV transport caskGUERRA, G. V.International conference on the packaging and transportation of radioactive materials. 1998, pp 1037-1044, 4VolConference Paper

Chemical processes in the oxidation and degradation of AGR oxide fuel : Chemistry of the nuclear fuel cycleBRADFORD, M. R.Nuclear energy (1978). 1996, Vol 35, Num 5, pp 321-330, issn 0140-4067Conference Paper

Utilisation de paliers à gaz dans le circulateur d'hélium d'un réacteur nucléaire à haute température refroidi par gazTANIGUCHI, S.Junkatsu. 1988, Vol 33, Num 5, pp 398-399, issn 0449-4156Article

Nuclear tribology: a personal perspectiveCHIVERS, T. C.Tribology international. 1986, Vol 19, Num 5, pp 225-233, issn 0301-679XArticle

Assessment of irradiation temperature stability of the first irradiation test rig in the HTTRSHIBATA, Taiju; KIKUCHI, Takayuki; MIYAMOTO, Satoshi et al.Nuclear engineering and design. 2003, Vol 223, Num 2, pp 133-143, issn 0029-5493, 11 p.Article

Dynamic analysis of AGR fuel assembliesNG, H. W.Computers & structures. 1995, Vol 54, Num 2, pp 339-350, issn 0045-7949Article

Coupling a gas turbine with a helium-cooled nuclear reactorPower. 1993, Vol 137, Num 12, pp 62-65, issn 0032-5929, 3 p.Article

Impact fracture toughness of a nuclear graphite measured by the one-point-bending methodTAKAHASHI, S; AOKI, S; MIYAHARA, N et al.Carbon (New York, NY). 1993, Vol 31, Num 2, pp 315-323, issn 0008-6223Article

Torness fuel route completionTHOMSON, J. R; TOTTMAN-TRAYNOR, E; BURNS, W. K et al.Nuclear energy (1978). 1993, Vol 32, Num 6, pp 349-354, issn 0140-4067Article

The safety of modular high temperature gas-cooled reactors : Safety and licensing issuesKASTEN, P. R.Nuclear engineering and design. 1992, Vol 137, Num 2, pp 171-180, issn 0029-5493Article

Specific power bound of a finite-time closed Brayton cycleCHIH WU.International journal of ambient energy. 1990, Vol 11, Num 2, pp 77-82, issn 0143-0750, 6 p.Article

The Leidenfrost reactor: a new general purpose direct-cooled reactor and its use for low temperature polymerizationsZSUGA, M; KENNEDY, J. P; KELEN, T et al.Polymer bulletin (Berlin. Print). 1988, Vol 19, Num 2, pp 201-207, issn 0170-0839Article

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