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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

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

LOCAS USER GROUP FORMEDABBOTT W.1978; VINE; GBR; DA. 1978; NO 25; PP. 8-9Article

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

Consequence calculations for PPCS bounding accidentsHAN, W. E.Fusion engineering and design. 2005, Vol 75-79, pp 1205-1209, issn 0920-3796, 5 p.Conference Paper

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

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

Oxidation of uranium in steamHAYWARD, P. J; EVANS, D. G; TAYLOR, L et al.Journal of nuclear materials. 1994, Vol 217, Num 1-2, pp 82-92, issn 0022-3115Article

A review on the clad failure studiesALAM, Tanweer; KALEEM KHAN, Mohd; PATHAK, Manabendra et al.Nuclear engineering and design. 2011, Vol 241, Num 9, pp 3658-3677, issn 0029-5493, 20 p.Article

Perspectives on the application of order-statistics in best-estimate plus uncertainty nuclear safety analysisMARTIN, Robert P; NUTT, William T.Nuclear engineering and design. 2011, Vol 241, Num 1, pp 274-284, issn 0029-5493, 11 p.Article

Analysis for loss of coolant accident in a fusion reactorHINO, T; HIROHATA, Y; YAMASHINA, T et al.Fusion engineering and design. 1996, Vol 31, Num 3, pp 259-263, issn 0920-3796Article

Small-break loss-of-coolant accident analysis for pressurized water reactors with an advanced drift-flux model in ATHLETKIRMSE, R; POINTNER, W; SONNENBURG, H. G et al.Nuclear engineering and design. 1995, Vol 154, Num 1, pp 23-25, issn 0029-5493Article

Some challenges to the thermal-hydraulic codesYIH-YUN HSU.Nuclear engineering and design. 1994, Vol 151, Num 1, pp 103-111, issn 0029-5493Article

Nuclear safety assessment for Cernavoda NPP unit 1 in the case of loss of feedwater flow accidentDINCA, Elena; ANGHELESCU, Mihnea.International symposium on nuclear energy. 1999, pp 161-165, 2VolConference Paper

Heat transfer from a high temperature safety rod placed in a perforated guide tube and surrounded by an array of cold tubesPASAMEHMETOGLU, K. O; UNAL, C.Nuclear engineering and design. 1994, Vol 148, Num 2-3, pp 293-304, issn 0029-5493Article

Application of fractional scaling analysis (FSA) to loss of coolant accidents (LOCA) Methodology developmentZUBER, Novak; ROHATGI, Upendra S; WULFF, Wolfgang et al.Nuclear engineering and design. 2007, Vol 237, Num 15-17, pp 1593-1607, issn 0029-5493, 15 p.Conference Paper

Short-term hydrogen production issues for ITERGAETA, M. J; MERRILL, B. J; BARTELS, H.-W et al.Fusion technology. 1997, Vol 32, Num 1, pp 23-34, issn 0748-1896Article

THE U.K. LIBRARY NETWORKS AND THE CO-OPERATIVE AUTOMATION GROUPBAKEWELL KGB.1982; ASLIB PROC.; ISSN 0001-253X; GBR; DA. 1982; VOL. 34; NO 6-7; PP. 301-309; BIBL. 6 REF.Article

CUMBRIA: LOCAS SETTLED IN1979; VINE; GBR; DA. 1979; NO 31; PP. 44-46Article

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

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