Comportement vibratoire des assemblages combustibles d'un réacteur: un modèle simplifié = Vibration behaviour of reactor fuel assemblies: a simplified modelPLANCHARD, J.Bulletin de la Direction des études et recherches - Electricité de France. Série C, mathématiques, informatique. 1984, Num 1, pp 5-15, issn 0013-4511Article

DIE AUSLEGUNG DES REAKTORKERNES UND DER BRENNELEMENTE DES KERNKRAFTWERKES TULLNERFELD = LA CONCEPTION DU COEUR DU REACTEUR ET DES ELEMENTS COMBUSTIBLES DE LA CENTRALE NUCLEAIRE DE TULLNERFELDREICHL A; ROTH E.1972; OSTERR. INGR-Z.; OSTERR.; DA. 1972; VOL. 15; NO 11; PP. 336-337Serial Issue

RESISTANCE HYDRAULIQUE LORS DE L'ECOULEMENT LONGITUDINAL AUTOUR DE FAISCEAUX DE BARRES LISSES ET A AILETTESSUBBOTIN VI; GABRIANOVICH BN; SHEJNINA AV et al.1972; ATOM. ENERG.; S.S.S.R.; DA. 1972; VOL. 33; NO 5; PP. 889-892; ABS. ANGL.; BIBL. 6 REF.Serial Issue

INVESTIGATION OF FLOW PARAMETERS FOR A SERIES OF CONCENTRIC ROUGH PIN AND SMOOTH CHANNEL ASSEMBLIESLEE CJ.1972; CEGB-RD-B-N 2404; G.B.; DA. 1972; PP. (26 P.); BIBL. 9 REF.Report

TWO-PHASE FLOW MIXING IN ROD BUNDLE SUBCHANNELSGONZALEZ SANTALO JM; GRIFFITH P.1972; IN: AM. SOC. MECH. ENG. WINTER ANNU. MEET.; NEW YORK, N.Y.; 1972; S.L.; A.S.M.E.; DA. 1972; VOL. NE-19; PP. 1-13Conference Paper

ETUDES EXPERIMENTALES DES CARACTERISTIQUES MOYENNES D'UN ECOULEMENT TURBULENT DANS DES CELLULES DE FAISCEAUX DE BARRESLEVCHENKO YU D; SUBBOTIN VI; USHAKOV PA et al.1972; ATOM. ENERG.; S.S.S.R.; DA. 1972; VOL. 33; NO 5; PP. 893-899; ABS. ANGL.; BIBL. 15 REF.Serial Issue

THERMOHYDRAULICS OF NUCLEAR FUEL ASSEMBLIES AND RELATED PROBLEMSMICHEL A; DE HEERING D; MESTREE J et al.1972; IMA-NT-31-1972; BELG.; DA. 1972; PP. (84 P.)Report

Numerical modeling of the shearing of irradiated fuel assembliesMESHCHERYAKOV, Yu. P.Journal of applied mechanics and technical physics. 2006, Vol 47, Num 3, pp 419-425, issn 0021-8944, 7 p.Article

The AFA 3G fuel assembly a proven design for high burnupsFORAT, C; FLORENTIN, F.TopFuel '99. International topical meetingSFEN /ENS conference. 1999, pp 73-82Conference Paper

Review and proposal for best fit of wire-wrapped fuel bundle friction factor and pressure drop predictions using various existing correlationsBUBELIS, E; SCHIKORR, M.Nuclear engineering and design. 2008, Vol 238, Num 12, pp 3299-3320, issn 0029-5493, 22 p.Article

Accurate Estimation of subcriticality using Indirect Bias Estimation method, (II) : ApplicationsSAKURAI, K; YAMAMOTO, T; ARAKAWA, T et al.Journal of Nuclear Science and Technology. 1997, Vol 34, Num 6, pp 544-550, issn 0022-3131Article

Automated fuel fabrication : A vision comes trueHEMANTHA RAO, G. V. S; PRAKASH, M. S; SETTY, C. R. P et al.Seminar on technological achievements. 1997, 4 p.Conference Paper

Nuclear analysis for the boraflex used in a typical spent-fuel storage assemblyINSOO JUN; MYUNG JAE SONG.Nuclear technology. 1995, Vol 109, Num 3, pp 357-365, issn 0029-5450Article

Comportement en exploitation du combustible = Operating behaviour of the fuelDEHON.Société française d'énergie nucléaire. Journée. 1984, 16 p.Conference Paper

Effects of a new blending agent on ethanol-gasoline fuelsKARAOSMANOGLU, F; ISIGIGÜR, A; AKSOY, H. A et al.Energy & fuels. 1996, Vol 10, Num 3, pp 816-820, issn 0887-0624Article

Flooding in a thin rectangular slit geometry representative of ATR fuel assembly side-plate flow channelsLARSON, T. K; OH, C. H; CHAPMAN, J. C et al.Nuclear engineering and design. 1994, Vol 152, Num 1-3, pp 277-285, issn 0029-5493Article

EINE GEOMETRIETRANSFORMATION ZUR ANALYTISCHEN BESTIMMUNG VON DRUCKVERLUST UND WAERMEUEBERGANG BEI STABBUENDEL-ELEMENTEN = UNE TRANSFORMATION GEOMETRIQUE POUR LA DETERMINATION ANALYTIQUE DE LA CHUTE DE PRESSION ET DU TRANSFERT THERMIQUE DANS DES FAISCEAUX DE BARRESMARKFORT D.1973; ATOMKERNENERGIE; DTSCH.; DA. 1973; VOL. 20; NO 4; PP. 286-290; ABS. ANGL.; BIBL. 6 REF.Serial Issue

CROSS FLOW RESISTANCE IN ROD BUNDLE CORESWEISMAN J.1972; NUCL. TECHNOL.; U.S.A.; DA. 1972; VOL. 15; NO 3; PP. 465-469; BIBL. 10 REF.Serial Issue

HEAT TRANSFER TO LIQUID METALS FLOWING TURBULENTLY AND LONGITUDINALLY THROUGH CLOSELY SPACED ROD BUNDLES. PART IDWYER OE; BERRY HC.1972; NUCL. ENGNG DESIGN; NETHERL.; DA. 1972; VOL. 23; NO 3; PP. 273-294; BIBL. 33 REF.Serial Issue

PRELIMINARY COOLANT TEMPERATURE OSCILLATION MEASUREMENTS AT THE FUEL-FAILURE MOCKUPFRY DN; KERLIN TW.1972; ORNL-TM-3761; U.S.A.; DA. 1972; PP. (23 P.); BIBL. 5 REF.; MICROFICHEReport

TURBULENT FLOW PRESSURE DROP MODEL FOR FUEL ROD ASSEMBLIES UTILIZING A HELICAL WIRE-WRAP SPACER SYSTEMNOVENDSTERN EH.1972; NUCL. ENGNG DESIGN; NETHERL.; DA. 1972; VOL. 22; NO 1; PP. 19-27; BIBL. 13 REF.Serial Issue

UNTERSUCHUNGEN ZUR BESTIMMUNG DER STROEMUNGSFORM IM TOTWASSER HINTER LOKALEN KUEHLKANALBLOCKADEN IN STABBUENDELN = ETUDE SUR LA DETERMINATION DE LA FORME DE L'ECOULEMENT DANS LA ZONE DE RECIRCULATION DESCENDANTE LORS D'UN BLOCAGE LOCAL DANS DES FAISCEAUX D'AIGUILLES COMBUSTIBLESBASMER P; KIRSCH D; SCHULTHEISS GF et al.1972; ATOMWIRTSCH. ATOMTECH.; DTSCH.; DA. 1972; VOL. 17; NO 8; PP. 416-417; BIBL. 4 REF.Serial Issue

ANALYSIS OF INERTIAL CONTRIBUTION OF THE FLUID IN A PLENUM TO A RAPID COOLANTEXPULSION PROCESS IN A LIQUID METAL FAST BREEDER REACTOR SINGLE-SUBASSEMBLY ACCIDENTCHAWLA TC.1972; NUCL. SCI. ENGNG; U.S.A.; DA. 1972; VOL. 48; NO 4; PP. 397-402; BIBL. 8 REF.Serial Issue

FORCED CONVECTION BURNOUT AND HYDRODYNAMIC INSTABILITY EXPERIMENTS FOR WATER AT HIGH PRESSURE. VIII. ANALYSIS OF BURNOUT EXPERIMENTS ON 3 X 3 ROD BUNDLES WITH UNIFORM AND NON-UNIFORM HEAT GENERATIONDI CAPUA E; RICCARDI R.1972; EUR-4875 E; LUXEMBOURG; DA. 1972; PP. 1-78; BIBL. 7 REF.Report

TRENDS IN FUEL ASSEMBLY DESIGN AND IMPACT ON FUEL CYCLE COSTKRAMER FW.sdJOURNEES INTERNATIONALES D'ETUDE DES CENTRALES ELECTRIQUES MODERNES. SESSION. 8/1981-10-26/LIEGE; BEL; LIEGE: IMPR. CLRO; DA. S.D.; PP. 15.1-15.14; ABS. GER/FRE/DUTConference Paper