Assessing progress in the development of safety cultureROTARU, Ioan; GHITA, Sorin.International symposium on nuclear energy. 1999, pp 151-156, 2VolConference Paper

Nuclear safety assessment for Cernavoda NPP unit 1 in the case of loss of class IV power supply with primary liquid relief unavailableANGHELESCU, Mihnea; DINCA, Elena.International symposium on nuclear energy. 1999, pp 157-160, 2VolConference Paper

A comprehensive assessment of round tube CHF prediction models for square-latticed rod bundlesHWANG, Dae-Hyun; ZEE, Sung-Quun; CHANG, Moon-Hee et al.International heat transfer conference. 2002, pp 309-314, isbn 2-84299-308-X, 6 p.Conference Paper

Pin power factor decrease and fuel economy during LEU refueling of 14 MW triga coreIORGULIS, C; PREDA, M; CIOCANESCU, M et al.International symposium on nuclear energy. 1999, pp 385-389, 2VolConference Paper

ILK-Stellungnahme: Praxis des Sicherheitsmanagements in den Kernkraftwerken in Deutschland = ILK statement practice of safety management in German nuclear power plantsAtw. Internationale Zeitschrift für Kernenergie. 2002, Vol 47, Num 10, issn 1431-5254, 599, 631 [2 p.]Article

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

Quel taux de disponibilité pour un nouveau réacteur rapide sodium ?GUIDEZ, Joël.Revue générale nucléaire (Paris). 2009, Num 5, pp 54-58, issn 0335-5004, 5 p.Article

Fluid-to-fluid modeling of natural circulation boiling loops for stability analysisMARCEL, C. P; ROHDE, M; VAN DER HAGEN, T. H. J. J et al.International journal of heat and mass transfer. 2008, Vol 51, Num 3-4, pp 566-575, issn 0017-9310, 10 p.Article

APPLICATION OF THE PROBABILITY METHOD FOR ANALYSIS OF DISRUPTIONS IN THE OPERATION OF RESEARCH NUCLEAR FACILITIESMEL'NIKOV, V. N; PEPELYSHEV, Yu. N; CHISTOZVONOV, A. S et al.Atomic energy (New York, N.Y.). 2007, Vol 103, Num 5, pp 917-920, issn 1063-4258, 4 p.Article

Chinese sign up for four AP1000sModern power systems. 2007, Num SEP, pp 19-20, issn 0260-7840, 2 p.Article

IS A RUSSIAN REACTOR SIMULATION PROJECT NECESSARY?ZIZIN, M. N.Atomic energy (New York, N.Y.). 2007, Vol 103, Num 4, pp 776-779, issn 1063-4258, 4 p.Article

PROSPECTS FOR THE DEVELOPMENT OF PROPULSION NUCLEAR POWER SYSTEMSKHLOPKIN, N. S.Atomic energy (New York, N.Y.). 2007, Vol 103, Num 4, pp 747-752, issn 1063-4258, 6 p.Article

Durée de vie des enceintes de confinement : La durée de vie des réacteurs, ses enjeux, les problèmatiques et les réalisations associées = Durability of reactor containment confinements : Durability of reactors, their stakes, problems and associated accomplishmentsGALLITRE, Etienne; LABBE, Pierre; PASTOR, Guy et al.Revue générale nucléaire. 2007, Num 2, pp 43-47, issn 0335-5004, 5 p.Conference Paper

Characteristic features of emergency heat removal in reactors with lead-bismuth and lead coolantsBEZNOSOV, A. V; BOKOVA, T. A; MOLODTSOV, A. A et al.Atomic energy (New York, N.Y.). 2006, Vol 101, Num 6, pp 908-910, issn 1063-4258, 3 p.Article

Thermohydraulic characteristics of an experimental fuel assembly for a water-graphite reactorDMITRIEV, A. M; GAVRILOV, P. M; TSYGANOV, A. A et al.Atomic energy (New York, N.Y.). 2006, Vol 101, Num 3, pp 669-674, issn 1063-4258, 6 p.Article

The Process-Oriented Simulation (POS) model for common cause failures : recent progressBERG, H.-P; GÖRTZ, R; SCHIMETSCHKA, E et al.Kerntechnik (1987). 2006, Vol 71, Num 1-2, pp 54-59, issn 0932-3902, 6 p.Article

Methodology for reference accidents definition for ITERPINNA, T; RABOIN, S; UZAN-ELBEZ, J et al.Fusion engineering and design. 2005, Vol 75-79, pp 1103-1107, issn 0920-3796, 5 p.Conference Paper

ILK-Empfehlung zur Vermeidung von gemeinsam verursachten Ausfällen bei digitalen Schutzsystemen = ILK recommendation on the avoidance of dependent failures of digital I&C protection systemsAtw. Internationale Zeitschrift für Kernenergie. 2003, Vol 48, Num 11, pp 698-700, issn 1431-5254, 3 p.Article

Experience in verifying the thermohydraulic program system BAGIRA on the integrated safety test bed for VVER reactorsKALINICHENKO, S. D; KROSHILIN, A. E; KROSHILIN, V. E et al.Thermal engineering. 2003, Vol 50, Num 11, pp 883-890, issn 0040-6015, 8 p.Article

Increasing the internal protection of a pulsed reactor against wrong or illegal actionsSNOPKOV, A. A; MARKOV, V. N; GORIN, N. V et al.Atomic energy (New York, N.Y.). 2003, Vol 94, Num 5, pp 350-354, issn 1063-4258, 5 p.Article

Alerting procedures for scenarios without warning timeBAGGENSTOS, M.Kerntechnik (1987). 2002, Vol 67, Num 2-3, pp 127-129, issn 0932-3902Article

General safety criteria for the Korean Next Generation Reactor : Advanced nuclear installation safetyLEE, Jae-Hun; KIM, Woong-Sik; YOUNG GILL YUNE et al.Nuclear technology. 2002, Vol 139, Num 1, pp 36-41, issn 0029-5450Article

Indikatoren für die Bewertung des Sicherheitsniveaus von Kernkraftwerken = Indicators for assessing the safety level of nuclear power plantsSEIDEL, E. R; STRAUB, G.Atw. Internationale Zeitschrift für Kernenergie. 2002, Vol 47, Num 12, issn 1431-5254, 744, 754-758 [6 p.]Article

Simulatorschulung: 25 Jahre Sicherheitstraining für Kernkraftwerke = Twenty-five years of simulator trainingAtw. Internationale Zeitschrift für Kernenergie. 2002, Vol 47, Num 12, issn 1431-5254, 745, 783-785 [4 p.]Article

Probabilistic service-life assessment for safety analysis for preparing a power-generating unit of a nuclear power plant for service-life extensionVEREZEMSKII, V. G.Atomic energy (New York, N.Y.). 2002, Vol 93, Num 4, pp 800-807, issn 1063-4258, 8 p.Article