kw.\*:("REFROIDISSEMENT URGENCE")
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SPRAY COOLING TEST: A SEPARATE EFFECT TEST WITH ROSA-III, A BWR-LOCA SIMULATION FACILITYSOBAJIMA M.1981; J. NUCL. SCI. TECHNOL.; ISSN 0022-3131; JPN; DA. 1981; VOL. 18; NO 8; PP. 629-639; BIBL. 12 REF.Article
STUDY OF FAILURE CONDITIONS CONTROL OF LARGE NUCLEAR POWER PLANT TURBINESEKIMOVA MM; KUCHUMOVA EO; MYSHKIN NS et al.1978; TRUDY L.P.I., LENINGRAD; S.S.S.R.; DA. 1978; NO 358; PP. 79-84; BIBL. 9 REF.Article
A THREE REGIONS SEMI-ANALYTICAL REWETTING MODELSAWAN ME; TEMRAZ HM.1981; NUCL. ENG. DES.; ISSN 0029-5493; NLD; DA. 1981; VOL. 64; NO 3; PP. 319-327; BIBL. 11 REF.Article
AN ANALYSIS OF REWETTING PHENOMENA IN VERTICAL CHANNELSKIM A; LEE Y.1981; CANCAM 81. CONGRES CANADIEN DE MECANIQUE APPLIQUEE. 8/1981-06-07/MONCTON NB; CAN; YARMOUTH NS: IMPR. LESCARBOT; DA. 1981; PP. 733-734; BIBL. 2 REF.Conference Paper
INFLUENCE OF PARTIAL BLOCKAGE OF A BWR BUNDLE ON HEAT TRANSFER, CLADDING TEMPERATURE, AND QUENCHING DURING BOTTOM FLOODING OR TOP SPRAYING UNDER SIMULATED LOCA CONDITIONSBRAND B; GAUL HP; SARKAR J et al.1982; NUCL. TECHNOL.; ISSN 0029-5450; USA; DA. 1982; VOL. 56; NO 1; PP. 128-133; BIBL. 8 REF.Article
NORCOOL-I, A BEST-ESTIMATE MODEL FOR BWR EMERGENCY COOLING DURING REFLOOD. I. IIASTRUP P; MIETTINEN J.1982; NEWSL. NEA DATA BANK; ISSN 0253-2506; INT; DA. 1982; NO 28; PP. 5-72; BIBL. DISSEM.Article
DYNAMIC ANALYSIS CODE FOR HYDRAULIC NETWORK SYSTEMSTANJI J.1981; J. NUCL. SCI. TECHNOL.; ISSN 0022-3131; JPN; DA. 1981; VOL. 18; NO 12; PP. 969-971; BIBL. 3 REF.Article
ON THE ABILITY OF THE TRAC-P1A COMPUTER PROGRAM TO PREDICT BLOWDOWN, REFILL, AND REFLOOD PHENOMENA DURING SEMISCALE MOD-1 EXPERIMENTSDEMMIE PN.1981; AICHE SYMP. SER.; ISSN 0065-8812; USA; DA. 1981; VOL. 77; NO 203; PP. 290-300; BIBL. 3 REF.Conference Paper
SURETE DES REACTEURS A EAU ET EXPERIENCES EN SIMILITUDE THERMOHYDRAULIQUEMUND E; GIOT M.1979; REV. ENERG. PRIM.; BEL; DA. 1979; VOL. 14; NO 1; PP. 33-39; ABS. ENG/DUT/GER; BIBL. 6 REF.Article
HEAT TRANSFER MODEL FOR DISPERSED FLOW REGIME DURING REFLOODKAMINAGA F.1981; J. NUCL. SCI. TECHNOL.; ISSN 0022-3131; JPN; DA. 1981; VOL. 18; NO 1; PP. 6-14; BIBL. 12 REF.Article
A TRAC-PD2 ANALYSIS OF FLECHT EXPERIMENTSBOTT TF; MANDELL DA.1981; AICHE SYMP. SER.; ISSN 0065-8812; USA; DA. 1981; VOL. 77; NO 203; PP. 301Conference Paper
Post-accident heat removal research: a state of the art reviewMÜLLER, U; SCHULENBERG, T.Kernforschungszentrum Karlsruhe. 1983, Num 3601, issn 0303-4003, 125 p.Serial Issue
Perspective channel-type reactor with enhanced safetyADAMOV, E. O; GROZDOV, I. I; KUZNETSOV, S. P et al.Nuclear engineering and design. 1993, Vol 147, Num 1, pp 23-28, issn 0029-5493Article
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
HYDRODYNAMIQUE DES ECOULEMENTS EAU-VAPEUR DANS LA ZONE REMOUILLEE D'UN TUBE CHAUFFANT EN RENOYAGE = THE HYDRODYNAMICS OF WATER-STEAM FLOW IN THE REWETTED ZONE OF A REFLOODING HEATING TUBEFREITAS RL.1981; ; FRA; DA. 1981; 111 P.-PL.; 30 CM; BIBL. 8 P.; TH. DOCT.-ING./GRENOBLE 1-INPG/1981Thesis
EXPERIMENTAL AND COMPUTATIONAL THERMAL-HYDRAULIC RESULTS OF FLUID AND THERMAL MIXING TESTSHASSAN YA.1982; NUCLEAR ENGINEERING AND DESIGN; ISSN 0029-5493; NLD; DA. 1982; VOL. 74; NO 2; PP. 215-221; BIBL. 7 REF.Article
EINFLUSS VON ABSTANDSHALTERN AUF DEN WAERMEUEBERGANG WAEHREND DER FLUTPHASE EINES DWR-KUEHLNUTTELVERLUSTSTOERFALLE = EFFECT OF SPACER-GRIDS ON THE HEAT TRANSFER DURING THE FLOODING PHASE OF A PWR LOSS-OF-COOLANT ACCIDENT = INFLUENCE DES ESPACEURS SUR LE TRANSFERT DE CHALEUR AU COURS DE LA PHASE DE NOYAGE DANS UN ACCIDENT DE PERTE DE FLUIDE DE REFROIDISSEMENT D'UN REACTEUR A EAU PRESSURISEEIHLE P; RUST K.1981; KERNFORSCHUNGSZENT. KARLSR.; ISSN 0303-4003; DEU; DA. 1981; NO 3178; 12 P.; H.T. 20; ABS. ENG; BIBL. 8 REF.Article
A MODEL OF COUNTERCURRENT STEAM-WATER FLOW IN LARGE HORIZONTAL PIPESDALY BJ; HARLOW FH.1981; NUCL. SCI. ENG.; ISSN 0029-5639; USA; DA. 1981; VOL. 77; NO 3; PP. 273-284; BIBL. 27 REF.Article
EFFECT OF INTERFACIAL SHEAR AND ENTRAINMENT MODELS ON FLOODING PREDICTIONSPOPOV NK; ROHATGI US.1983; AICHE SYMPOSIUM SERIES; ISSN 0065-8812; USA; DA. 1983; VOL. 79; NO 225; PP. 190-199; BIBL. 24 REF.Conference Paper
TRANSITION BOILING HEAT TRANSFER IN THE SEMISCALE MOD-3 CORE DURING REFLOODLOOMIS GG; SHUMWAY RW.1982; NUCL. TECHNOL.; ISSN 0029-5450; USA; DA. 1982; VOL. 56; NO 3; PP. 426-433; BIBL. 11 REF.Article
MACHINE RECOGNITION OF VOID FRACTION IN TWO-PHASE FLOWSHAMILTON NJ; GONZALEZ RC.1981; IEEE TRANS. SYST. MAN CYBERN.; ISSN 0018-9472; USA; DA. 1981; VOL. 11; NO 11; PP. 766-777; BIBL. 10 REF.Article
ECHANGEURS DE CHALEUR POUR LES CENTRALES HHT = HEAT EXCHANGERS FOR HHT NUCLEAR POWER PLANTSNAEGELIN R; BIERI H; FISCHLI H et al.1979; ENTROPIE; FRA; DA. 1979; VOL. 15; NO 86; PP. 28-33; ABS. ENG/GER/SPA; BIBL. 1 REF.Article
NUCLEAR REACTOR SAFETY1980; TRANS. AM. NUCL. SOC.; ISSN 0003-018X; USA; DA. 1980; VOL. 35; PP. 297-403; BIBL. DISSEM.Article
AN ANALYSIS OF HEAT TRANSFER TO AXIAL DISPERSED FLOW BETWEEN ROD BUNDLES UNDER REACTOR EMERGENCY COOLING CONDITIONSWONG S; HOCHREITER LE.1980; J. HEAT TRANSFER; ISSN 0022-1481; USA; DA. 1980; VOL. 102; NO 3; PP. 508-512; BIBL. 4 REF.Article
The TOMAS Software System for Approximate Analysis of Emergency Situations at Nuclear Power StationsZHUKAVIN, A. P.Thermal engineering. 2009, Vol 56, Num 5, pp 390-397, issn 0040-6015, 8 p.Article