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Maintenance des chaudières nucléaires = Maintenance of nuclear boilersHUTIN, Jean-Pierre.Techniques de l'ingénieur. Génie nucléaire. 2001, Vol BN2, Num BN3295, pp BN3295.1-BN3295.26, issn 1762-875XArticle

Simulating ET: Simulation for Eddy Current Testing of Steam Generators in Nuclear Power PlantsNAIGUANG LEI; BARDEL, Charles; UDPA, Lalita et al.Materials evaluation. 2011, Vol 69, Num 12, pp 1354-1361, issn 0025-5327, 8 p.Article

Formation et entraînement du personnel : le CETIC : La formation dans le domaine nucléaire = Staff formation and training : the CETICRENARD, Pierre.Revue générale nucléaire. 2005, Num 5, pp 45-47, issn 0335-5004, 3 p.Article

Development of stabilizers for steam generator tube repairAU-YANG, M. K.Nuclear engineering and design. 1987, Vol 103, Num 2, pp 189-197, issn 0029-5493Article

Leak and burst testing practice on pulled-out steam generator tubesHERNALSTEEN, P; VAN ZEVEREN, F.Fontevraud. Colloque international. 1994, pp 425-433, 2VolConference Paper

Some aspects regarding the operation of the CANDU 6 NPP in normal modeMOCANASU, Matei.International symposium on nuclear energy. 1999, pp 458-462, 2VolConference Paper

Simulation of CNE primary heat transport behaviour for a postulated boiler dividing plate change in case of a perturbationGERSBERG, Sara.International symposium on nuclear energy. 1999, pp 451-454, 2VolConference Paper

Les moyens de Framatome : Outils et méthods d'évaluation = Framatome meansPY, J.-P.Revue générale nucléaire. 1998, Num 6, pp 74-78, issn 0335-5004Article

Two-phase flow in wire-packed bedARITOMI, M; MIZUSHIMA, T; YABUTA, H et al.Journal of Nuclear Science and Technology. 1994, Vol 31, Num 3, pp 204-212, issn 0022-3131Article

Analyses of deposits and underlying surfaces on the secondary side of pulled out tubes from a French plantCATTANT, F; DUPIN, M; SALA, B et al.Fontevraud. Colloque international. 1994, pp 469-480, 2VolConference Paper

Commissioning experience in pumps for stream-water system for fast breeder test reactor (FBTR)SURESH KUMAR, K. V; ALAGUDURAI, V; IYER, M. A. K et al.Pumping equipment in nuclear industry and thermal power plants. National symposium. 1994, pp IV.5.1-IV.5.6Conference Paper

Sound propagation in a steam generator: experimental and theoretical resultsFIRTH, D; HECKL, M. A; MCKNIGHT, J. A et al.Nuclear energy (1978). 1993, Vol 32, Num 6, pp 369-378, issn 0140-4067Article

Etude des générateurs de vapeur du bloc principal d'une centrale nucléaire avec réacteur modéré et refroidi à l'eauTARANKOV, G. A; TITOV, V. F; LOGVINOV, S. A et al.Ènergomašinostroenie. 1986, Num 5, pp 30-32, issn 0131-1336Article

Principales tendances d'étude et de développement de générateurs de vapeur du type horizontal pour centrales nucléaires avec réacteurs modérés et refroidis à l'eauTITOV, V. F; TARANKOV, G. A; LUKASEVICH, B. I et al.Ènergomašinostroenie. 1986, Num 5, pp 27-29, issn 0131-1336Article

Experience shows in steam generator replacementSMITH, J. C; ATHANASIU, L.Modern power systems. 1996, Vol 16, Num 10, pp 59-61, issn 0260-7840Article

Retour d'expérience des chaufferies nucléaires de propulsion navale = In service feedback from on-board nuclear reactorsGALL, P.Onde électrique. 1995, Vol 75, Num 2, pp 11-13, issn 0030-2430Article

Record breaking SG replacement at Gravelines 1GUINOT, M; CHAUMONT, J.-C.Modern power systems. 1994, Vol 14, Num 7, pp 43-45, issn 0260-7840, 2 p.Article

Study of chemical concentration behavior in tube support plate crevices within the steam generatorUENO, T; KAWANISHI, K.Kagaku kōgaku ronbunshū. 1994, Vol 20, Num 3, pp 321-329, issn 0386-216XArticle

Constant extension rate (CERT) testing of alloy 690 and 800 nuclear steam generator tubingSARVER, J. M; MIGLIN, B. P; MONTER, J. V et al.Fontevraud. Colloque international. 1994, pp 529-536, 2VolConference Paper

Effect of secondary cycle sulphuric acid injection on steam generator tubesGOMEZ BRICENO, D; GARCIA, M. S; HERNANDEZ, F et al.Fontevraud. Colloque international. 1994, pp 565-570, 2VolConference Paper

Is corrosion dependent on the duration of in-service cycle?STUBBE, J; HERNALSTEEN, P.Fontevraud. Colloque international. 1994, pp 365-373, 2VolConference Paper

Mechanism and effectiveness of inhibitors for IGA/SCCLUMSDEN, J. B; MIGLIN, B. P; PAINE, J. P. N et al.Fontevraud. Colloque international. 1994, pp 505-511, 2VolConference Paper

Résistance en milieu acide des matériaux alternatifs pour tubes de GV (alliages 690 et 800) = Acid resistance of materials of steam generators tubes (alloy 690 and 800)PIERSON, E; STUBBE, J; SOMVILLE, P et al.Fontevraud. Colloque international. 1994, pp 556-564, 2VolConference Paper

Comments on «failure probability of axially cracked steam generator tubes: a probabilistic fracture mechanics model». ReplyHOPENFELD, J; MAVKO, B; CIZELJ, L et al.Nuclear technology. 1993, Vol 102, Num 1, pp 143-144, issn 0029-5450Article

L'industrie nucléaire française en 1989. Les constructeurs d'équipements de l'îlot nucléaire = The french nuclear power industry in 1989. The manufacturers of nuclear island equipmentMEGNIN, J.-C.Revue générale nucléaire. 1989, Num 3, pp 219-224, issn 0335-5004Article

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