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kw.\*:("Assemblage combustible")

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FUEL BED FOR A COATED PARTICLE FUEL ASSEMBLYYELLOWLEES JM; VAN ASBROECK PB.1972; BLG-462; BELG.; DA. 1972; PP. (45 P.); ABS. FR.; BIBL. 66 REF.; (E.N.E.A. FUEL SPEC. MEET.; HARWELL; 1971)Conference Proceedings

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

EPR : conception du coeur et combustibleCORNILUS, Pierre-Louis; FRANCILLON, Eric; KIEHLMANN, Horst Dieter et al.Revue générale nucléaire. 2004, Num 6, pp 55-60, issn 0335-5004, 6 p.Conference Paper

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

EIN PROGRAMM ZUR BERECHNUNG DER WAERMEUEBERGANGSVERHAELTNISSE IM ENGGEPACKTEN GITTER = UN PROGRAMME POUR LE CALCUL DES CONDITIONS DE TRANSFERT THERMIQUE DANS UN RESEAU COMPACTSCHRAEWER R.1972; ATOMWIRTSCH. ATOMTECH.; DTSCH.; DA. 1972; VOL. 17; NO 11; PP. 559-560; BIBL. 3 REF.Serial Issue

NUKLEARE BRENNSTOFFE-ERFAHRUNGEN UND ERWARTUNGEN DER ELEKTRIZITAETSPRODUZENTEN = COMBUSTIBLES NUCLEAIRES. EXPERIENCES ET DESIRS DES PRODUCTEURS D'ELECTRICITEVOLCKER H.1972; KERNTECHNIK; DTSCH.; DA. 1972; VOL. 14; NO 10; PP. 448-451; BIBL. 8 REF.; MEME ART. ANGLSerial 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

RESPONSE OF A FAST REACTOR SUBASSEMBLY WRAPPER TO INTERNAL PRESSURES GENERATED IN AN ACCIDENTJUDD AM.1973; J. BRIT. NUCL. ENERGY SOC.; G.B.; DA. 1973; VOL. 12; NO 2; PP. 159-166; BIBL. 16 REF.Serial Issue

COMPARISON OF SINGLE AND MULTICELL HEAT TRANSFER ANALYSIS NEAR NUCLEAR REACTOR ASSEMBLY WALLSFRANCE DM; GINSBERG T.1972; NUCL. ENGNG DESIGN; NETHERL.; DA. 1972; VOL. 23; NO 2; PP. 141-146; BIBL. 6 REF.Serial Issue

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

Statistical ignition of high density D-T fuelCARUSO, A; STRANGIO, C.Laser and particle beams (Print). 1998, Vol 16, Num 1, pp 83-90, issn 0263-0346Conference Paper

Conception et performances des combustibles PWR du programme nucléaire français = Design and performance of PWR fuel developed under the French nuclear power programmeDEHON, C; LECLERCQ, J; TRACCUCCI, R et al.Nuclear power experience. International conference. 1983, pp 597-609Conference 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

A quasi-isotropic reflecting boundary condition for the TIBERE heterogeneous leakage modelPETROVIC, I; BENOIST, P; MARLEAU, G et al.Nuclear science and engineering. 1996, Vol 122, Num 2, pp 151-166, issn 0029-5639Article

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