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LOSS-OF-COOLANT ACCIDENT IN THE FLUIDIZED BED NUCLEAR POWER REACTORSEFIDVASH F.1983; ATOMKERNENERGIE. KERNTECHNIK; ISSN 0171-5747; DEU; DA. 1983; VOL. 42; NO 2; PP. 125-126; BIBL. 5 REF.Article

EXPERIMENTAL STUDY OF SYSTEM BEHAVIOR DURING REFLOOD PHASE OF PWR-LOCA USING CCTFMURAO Y; AKIMOTO H; SUDOH T et al.1982; JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY; ISSN 0022-3131; JPN; DA. 1982; VOL. 19; NO 9; PP. 705-719; BIBL. 8 REF.Article

A web-based nuclear simulator using RELAP5 and labVIEWKIM, K. D; RIZWAN-UDDIN.Nuclear engineering and design. 2007, Vol 237, Num 11, pp 1185-1194, issn 0029-5493, 10 p.Article

The vent-to-vent desynchronization effects on LOCA steam condensation loads in BWR pressure suppression poolKUKITA, Y; NAMATAME, K.Nuclear engineering and design. 1985, Vol 85, Num 2, pp 141-150, issn 0029-5493Article

Système de localisation des incidents sur les groupes à réacteur PBMK-1000TURETSKIJ, L. I; KELLER, V. D; KOZLOVA, N. A et al.Teploenergetika (Moskva, 1954). 1984, Num 2, pp 14-19, issn 0040-3636Article

CORE SUPPORT COLUMNS IN THE UPPER PLENUM OF A PRESSURIZED WATER REACTOR UNDER BLOWDOWN LOADING. I: TWO-DIMENSIONAL ANALYSIS, ASSESSMENT OF ESSENTIAL SIMPLIFICATIONS. II: THREE-DIMENSIONAL ANALYSIS, CALCULATION OF DEFORMATIONS AND STRESSESKRIEG R; DOLENSKY B; EBERLE F et al.1982; NUCLEAR ENGINEERING AND DESIGN; ISSN 0029-5493; NLD; DA. 1982; VOL. 73; NO 1; PP. 23-44; BIBL. 16 REF.Article

PROVING COMMERCIAL REACTOR SAFETY IN THE LOFT FACILITYOLDS FC.1982; POWER ENGINEERING (BARRINGTON, ILL.); ISSN 0032-5961; USA; DA. 1982; VOL. 86; NO 7; PP. 70-73Article

BEITRAEGE: ANALYSE VON KUEHLMITTELVERLUSTSTOERFAELLEN HEUTE, DIE LOFT (LOSS OF FLUID TEST)-VERSUCHE UND IHRE KONSEQUENZEN/3. GESELLSCHAFT FUER REAKTORSICHERHEIT-FACHGESPRAECH, MUENCHEN, 29-30 NOVEMBER 1979 = ANALYSIS OF LOFT ACCIDENT. RESEARCH AND CONSEQUENCES. 3. GRS FACHGESPRAECH MUNICH 29-30 DEC. 1979 = ANALYSE DES ACCIDENTS DE PERTE DE FLUIDE DE REFROIDISSEMENT AUJOURD'HUI (LOFT). RECHERCHES ET CONSEQUENCES. 3. GESELLSCHAFT FUER REAKTORSICHERHEIT-FACHGESPRAECH, MUNICH, 29-30 DEC. 1979SCHULZ W ED.sdANALYSE VON KUEHLMITTELVERLUSTSTOERFAELLEN HEUTE. GESELLSCHAFT FUER REAKTORSICHERHEIT-FACHGESPRAECH. 3/1979-11-29/MUENCHEN; DEU; KOELN: GRS; DA. S.D.; 73 P.; 30 CM; GRS-BERICHT; 16Conference Proceedings

SIMULATION DES KUEHLMITTELVERLUSTSTOERFALLS FUER EINEN DRUCK-WASSEREAKTOR VOM TYP WWER-440 IM MILLISEKUNDENBEREICH = SIMULATION OF LOSS-OF-COOLANT ACCIDENT IN A WWER-440 TYPE PRESSURIZED WATER REACTOR IN THE MILLISECOND RANGE = SIMULATION D'UN ACCIDENT DE PERTE DE REFRIGERANT D'UN REACTEUR A EAU PRESSURISEE DU TYPE WWER-440 DANS LE DOMAINE DE LA MILLISECONDEPERNECZKY L.1982; KERNENERGIE; ISSN 0023-0642; DDR; DA. 1982; VOL. 25; NO 2; PP. 64-66; ABS. ENG/RUS; BIBL. 6 REF.Article

CONFERENCE PAPERS/SMALL BREAK LOSS-OF-COOLANT ACCIDENT ANALYSES IN LWRS, SPECIALISTS MEETING, MONTEREY CA, AUGUST 25-27, 1981BAILEY PG ED.1981; SMALL BREAK LOSS-OF-COOLANT ACCIDENT ANALYSES IN LWRS. SPECIALISTS MEETING/1981-08-25/MONTEREY CA; USA; PALO ALTO: EPRI; DA. 1981; PAG. MULT.; 28 CMConference Proceedings

Thermohydraulics aspects of nuclear safety research in AustraliaBEATTIR, D. R. H; FORD, G. W. K; GREEN, W. J et al.Heat and fluid flow in nuclear and process plant safety. Conference. 1983, pp 111-120Conference Paper

Probalistic risk assessment insights from new Westinghouse pressurized water reactor designs studied in 1932-1987SANKACTAR, S; VAN DE VENNE, T.Nuclear technology. 1990, Vol 91, Num 1, pp 112-117, issn 0029-5450, 6 p.Article

ARIES-AT safety design and analysisPETTI, D. A; MERRILL, B. J; MOORE, R. L et al.Fusion engineering and design. 2005, Vol 80, Num 1-4, pp 111-137, issn 0920-3796, 27 p.Article

Applying sneak analysis to the identification of human errors of commissionHAHN, H. A; BLACKMAN, H. S; GERTMAN, D. I et al.Reliability engineering & systems safety. 1991, Vol 33, Num 2, pp 289-300, issn 0951-8320, 12 p.Article

Passive BWR integral LOCA testing at the Karlstein test facility INKADRESCHER, Robert; WAGNER, Thomas; LEYER, Stephan et al.VGB powertech. 2014, Num 5, pp 33-37, issn 1435-3199, 5 p.Article

Extending the application range of a fuel performance code from normal operating to design basis accident conditionsVAN UFFELEN, P; GYÖRI, C; SCHUBERT, A et al.Journal of nuclear materials. 2008, Vol 383, Num 1-2, pp 137-143, issn 0022-3115, 7 p.Conference Paper

Core to surge-line energy transport in a severe accident scenarioDI MARZO, M; ALMENAS, K; GOPALNARAYANAN, S et al.Nuclear engineering and design. 1995, Vol 154, Num 2, pp 119-132, issn 0029-5493Article

An on-line pressurizer surveillance system design to prevent small-break loss-of-coolant accidents through power-operated relief valves using a microcomputerJONG HO LEE; SOON HEUNG CHANG.Nuclear technology. 1987, Vol 76, Num 1, pp 27-40, issn 0029-5450Article

Reflooding with steady and oscillatory coolant injection. II: Quench front and liquid carryover behaviorOH, S; BANERJEE, S; YADIGAROGLU, G et al.Journal of heat transfer. 1986, Vol 108, Num 2, pp 448-456, issn 0022-1481Article

Einfluss der Durchströmungsrichtung im Reaktorkern auf die Hüllrohrverformung während eines Kühlmittelverluststörfolles = Influence du sens d'écoulement dans le cœur du réacteur sur la déformation des gaines des éléments combustibles lors d'un incident provoquant la perte du fluide de refroidissement = Influence of reactor core flow direction on fuel element cans deformation during a LOCA accidentWIEHR, K; ERBACHER, F.VGB Kraftwerkstechnik. 1984, Vol 64, Num 11, pp 978-981, issn 0372-5715Article

A diagnostic system for identifying accident conditions in a nuclear reactorSANTHOSH, T. V; KUMAR, M; LELE, H. G et al.Nuclear engineering and design. 2011, Vol 241, Num 1, pp 177-184, issn 0029-5493, 8 p.Article

Simulation of the IAEA's fourth standard problem exercise small-break loss-of-coolant accident using RELAP5/MOD3.1CEBULL, P. P; HASSAN, Y. A.Nuclear technology. 1995, Vol 109, Num 3, pp 327-337, issn 0029-5450Article

A survey of expert opinion and its probabilistic evaluation for specific aspects of the SNR-300 risk studyHOFER, E; JAVERI, V; LOFFLER, H et al.Nuclear technology. 1985, Vol 68, Num 2, pp 180-225, issn 0029-5450Article

Test results of jet discharge from a 4 inch pipe under BWR LOCA conditionsISOZAKI, T; YANO, T; MIYAZAKI, N et al.Nuclear engineering and design. 1984, Vol 79, Num 1, pp 81-92, issn 0029-5493Article

Experimental studies of 4-inch pipe whip test under BWR loca conditionsKURIHARA, R; UEDA, S; ISOZAKI, T et al.Nuclear engineering and design. 1983, Vol 76, Num 1, pp 23-33, issn 0029-5493Article

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