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Results 1 to 25 of 1684

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Hydraulische Belastungen von Kesselreaktoren = Charge hydraulique des réacteurs à cuve = Hydraulic loading of tank reactorsKIPKE, K. D.Chemieingenieurtechnik. 1984, Vol 56, Num 10, pp 733-739, issn 0009-286XArticle

Studies for the staggered pans core catcherFIEG, G; MÖSCHKE, M; WERLE, H et al.Nuclear technology. 1995, Vol 111, Num 3, pp 331-340, issn 0029-5450Article

Dynamic loads from reactor pressure vessel core melt-through under high primary system pressureJACOBS, G.Nuclear technology. 1995, Vol 111, Num 3, pp 351-357, issn 0029-5450Article

Etudes des incertitudes sur la fluence dans les cuves des REP. Ajustement des données de base = Uncertainty study of the PWR pressure vessel fluence. Adjustment of the nuclear data baseKodeli, Ivan; Nimal, Jean-Claude.1993, 138 p.Thesis

Schweissen in der Kerntecknik = Soudage dans le génie nucléaire = Welding in nuclear engineeringAtomkernenergie, Kerntechnik. 1983, Vol 43, Num 1, pp 1-29, issn 0171-5747Article

Die KTA-Regeln für den stählernen Reaktorsicherheitsbehälter = Le règlement KTA pour l'enceinte de sécurité en acier des réacteurs = The KTA code for the steel containment of LWR Power plantsSCHRÖTER, H.-J.Der Stahlbau. 1985, Vol 54, Num 2, pp 46-51, issn 0038-9145Article

Largest titanium reactor vessel barges to customerStainless steel world. 2000, Vol 12, Num 3, issn 1383-7184, p. 23Article

Visual examination for nuclear inservice inspectionHIGHT, V. H; GALLINO, D. A.Power engineering (Barrington, IL.). 1983, Vol 87, Num 9, pp 50-53, issn 0032-5961Article

Innendruck-Schwellversuche an einem Behälter in Zwischengrösse (ZB1) = Essais de pression interne et de gonflement d'une cuve de taille moyenne (ZB1)JAX, P; GILLOT, R; SPÖHRER, H.-J et al.VGB Kraftwerkstechnik. 1983, Vol 63, Num 11, pp 996-1002, issn 0372-5715Article

Development of boiler jacks for short term repairs to boilersDEAN, R.Nuclear energy (1978). 1984, Vol 23, Num 2, pp 97-104, issn 0140-4067Article

Study on underclad cracking in nuclear reactor vessel steelsHORIYA, T; TAKEDA, T; YAMATO, K et al.Journal of pressure vessel technology. 1985, Vol 107, Num 1, pp 30-35, issn 0094-9930Article

Debris interactions in reactor vessel lower plena during a severe accident. II. Integral analysisSUH, K. Y; HENRY, R. E.Nuclear engineering and design. 1996, Vol 166, Num 2, pp 165-178, issn 0029-5493Article

Failure strains and proposed limit strains for an reactor pressure vessel under severe accident conditionsKRIEG, R.Nuclear engineering and design. 2005, Vol 235, Num 2-4, pp 199-212, issn 0029-5493, 14 p.Conference Paper

Temperature evaluation of an instrumented capsule after material irradiation tests in HANAROCHOI, M. H; CHOO, K. N; KIM, H. R et al.Journal of nuclear materials. 2007, Vol 362, Num 1, pp 19-25, issn 0022-3115, 7 p.Article

CARINA ― A programme for experimental investigation of the irradiation behaviour of German reactor pressure vessel materialsHEIN, Hieronymus; KEIM, Elisabeth; BECHLER, Eduard et al.VGB powertech. 2013, Num 5, issn 1435-3199, 6-7, 43-49 [9 p.]Article

Debris interactions in reactor vessel lower plena during a severe accident. I. Predictive modelSUH, K. Y; HENRY, R. E.Nuclear engineering and design. 1996, Vol 166, Num 2, pp 147-163, issn 0029-5493Article

Statement on the operation of ferritic steel nuclear reactor pressure vessels. Health and safety executive, nuclear installations inspectorateBARR, W; DUNN, J. W; FORMBY, C. L et al.International journal of pressure vessels and piping. 1995, Vol 64, Num 3, pp 307-310, issn 0308-0161Conference Paper

Nondestructive testing of the point beach replacement reactor vessel closure headJENSEN, William A.Materials evaluation. 2006, Vol 64, Num 11, pp 1059-1063, issn 0025-5327, 5 p.Article

The impact of NDE unreliability on pressure vessel fracture predictionsSIMONEN, F. A.Journal of pressure vessel technology. 1985, Vol 107, Num 1, pp 18-24, issn 0094-9930Article

Résistance aux transitoires thermiques des cuves de réacteur à eau sous-pression = Resistance to thermal transients of pressurized water reactor vesselsHUTIN, J.-P.Revue générale de thermique. 1985, Vol 24, Num 282-283, pp 619-623, issn 0035-3159Article

A parametric study of the steady-state operational characteristics of the Ohio State university natural circulation, indirect-cycle, inherently safe boiling water reactorAYBAR, H. S; ALDEMIR, T; CHRISTENSEN, R. N et al.Nuclear technology. 1995, Vol 111, Num 1, pp 1-22, issn 0029-5450Article

Düsen für die Tank- und Behälterreinigung = Buses pour le nettoyage de cuves et réservoirs = Nozzles for cleaning of tanks and reservoirsBÜCHELE, W.SÖFW. Seifen, Öle, Fette, Wachse. 1989, Vol 115, Num 9, pp 315-318, issn 0173-5500Article

Zur Bestimmung von Temperatur und Druck bei der Wasserdruckprüfung des Reaktordruckgefässes von Kernkraftwerken = La détermination de températures et de pressions lors des essais de pression hydraulique de la cuve de réacteurs de centrales nucléairesBERGEMANN, W.Energietechnik. 1985, Vol 35, Num 1, pp 13-17, issn 0013-7421Article

Adequacy of estimates and variability of fracture related properties for reactor pressure vessel materialsRICHARDSON, A. R; SERVER, W. L; REUTER, W. G et al.International journal of pressure vessels and piping. 1985, Vol 19, Num 4, pp 299-315, issn 0308-0161Article

Reduction in reactor vessel irradiation through fuel managementBAGNAL, C. W. JR; CAVANAUGH, G. P; HARRIS, R. P et al.Nuclear technology. 1985, Vol 68, Num 1, pp 7-17, issn 0029-5450Article

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