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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

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

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 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

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

QUANTIFYING PHENOMENOLOGICAL IMPORTANCE IN BEST-ESTIMATE PLUS UNCERTAINTY ANALYSESMARTIN, Robert P.Nuclear technology. 2011, Vol 175, Num 3, pp 652-662, issn 0029-5450, 11 p.Article

AREVA's realistic large break LOCA analysis methodologyMARTIN, Robert P; O'DELL, Larry D.Nuclear engineering and design. 2005, Vol 235, Num 16, pp 1713-1725, issn 0029-5493, 13 p.Article

Study on post-blowdown of hot leg large break loss-of-coolant-accident in the view of mass and energy release analysisSOON JOON HONG; GOON CHERL PARK.Nuclear engineering and design. 2002, Vol 213, Num 1, pp 43-58, issn 0029-5493Article

Development of severe accident analysis code SAMPSON in IMPACT projectUJITA, H; SATOH, N; NAITOH, M et al.Journal of Nuclear Science and Technology. 1999, Vol 36, Num 11, pp 1076-1088, issn 0022-3131Article

Modeling of radiation heat transport in complex ladder-like structures placed in rectangular enclosuresUNAL, C; BOHL, W. R; PASAMEHMETOGLU, K. O et al.Nuclear engineering and design. 1999, Vol 193, Num 1-2, pp 173-183, issn 0029-5493Article

Modification of the reflood model in RELAP5/MOD3.1HAE YONG JEONG; HEE CHEON NO.Nuclear technology. 1998, Vol 124, Num 1, pp 52-64, issn 0029-5450Article

Safety approach for plasma anomaly events in fusion reactor : Code development and assessmentsHONDA, T; BARTELS, H.-W; UCKAN, N. A et al.Fusion engineering and design. 1998, Vol 42, Num 1-4, pp 103-108, issn 0920-3796Conference Paper

Implementation of a courant violating scheme for mixture drift-flux equationsKYUNGDOO KIM; DOSTER, J. M.Nuclear science and engineering. 1995, Vol 119, Num 1, pp 18-33, issn 0029-5639Article

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