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BREVET 2.256.088 (A1) (7443240). A 30 DECEMBRE 1974. TRANSPORTEUR POUR GAINES TUBULAIRES DE BARRES COMBUSTIBLES DE REACTEURSsdPatent

BREVET 2.237.280 (B) (7416583). A 14 MAI 1974. DISPOSITIF DE DECOUPAGE D'UNE ENVELOPPE D'ELEMENT COMBUSTIBLE DE REACTEUR NUCLEAIREsdPatent

Analysis on Lift-Off experiment in Halden reactor by FEMAXI-6 codeSUZUKI, M; KUSAGAYA, K; SAITOU, H et al.Journal of nuclear materials. 2004, Vol 335, Num 3, pp 417-424, issn 0022-3115, 8 p.Article

LEACHED HULL MONITOR FOR DETECTION OF UNDISSOLVED IRRADIATED NUCLEAR FUEL = CONTROLEUR D'ENVELOPPES LIXIVIEES POUR LA DETECTION DU COMBUSTIBLE NUCLEAIRE IRRADIE NON DISSOUTGOZANI T.1974; NUCL. MATER. MANAG.; U.S.A.; DA. 1974; VOL. 3; NO 3; PP. 203-216; BIBL. 6 REF.; (15TH ANNU. MEET. INST. MATER. MANAGE. PROC.; ATLANTA, GA.; 1974)Conference Paper

CORROSION DES MATERIAUX DANS LES REACTEURS NUCLEAIRESBRATESCU ID.1974; STUD. CERC. FIZ.; ROMAN.; DA. 1974; VOL. 26; NO 10; PP. 1049-1060; ABS. ANGL.; BIBL. 12 REF.Article

A DIFFRACTION METHOD TO MONITOR IN-PLANE STRAIN IN ZIRCALOY FUEL TUBES = UNE METHODE PAR DIFFRACTION POUR CONTROLER LA DEFORMATION PLANE DANS DES GAINES DE COMBUSTIBLE EN ZIRCALOYPRYOR TR; HAGENIERS OL; NORTH WPT et al.1974; MECH. RES. COMMUNIC.; G.B.; DA. 1974; VOL. 1; NO 5-6; PP. 321-324; BIBL. 2 REF.Article

COMPORTEMENT DE L'URANIUM METALLIQUE ET D'AUTRES ELEMENTS DU COMBUSTIBLE DE LA CENTRALE NUCLEAIRE A-1NOVAK J; SLANCAR F; SPLICHAL K et al.1975; JADER. ENERG.; CESKOSL.; DA. 1975; VOL. 21; NO 5; PP. 172-176; ABS. RUSSE ANGL.; BIBL. 15 REF.Article

UNIFORM ULTRASONIC INSPECTION OF FUEL SHEATH TUBINGCROSS BT; ABBOTT DJ.1974; A.S.T.M. SPEC. TECH. PUBL.; U.S.A.; DA. 1974; NO 551; PP. 31-38; (ZIRCONIUM NUCL. APPL. SYMP.; 1974 PORTLAND, OREG.; 1974)Conference Paper

EINE AUTOMATISCHE ROHRPRUEFANLAGE NACH DEM TAUCHTECHNIKVERFAHREN = UNE INSTALLATION AUTOMATIQUE D'ESSAI DES TUBES PAR LES PROCEDES DE LA TECHNIQUE D'IMMERSIONSCHUBERT K.1972; KERNTECHNICK; DTSCH.; DA. 1972; VOL. 14; NO 12; PP. 570-573; BIBL. 1 REF.; MEME ART. ANGLSerial Issue

NUCLEAR TUBES FOR FUEL CLADDING AND STEAM GENERATORS1972; NUCL. ENGNG INTERNATION.; G.B.; DA. 1972; VOL. 17; NO 199; PP. 1001-1017; BIBL. 11 REF.Serial Issue

CLADDING MATERIALS = MATERIAUX DE GAINAGE DE COMBUSTIBLE NUCLEAIRE1974; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1974; VOL. 19; PP. 143-150; BIBL. DISSEM.; (AM. NUCL. SOC. WINTER MEET.; WASHINGTON, D.C.; 1974)Conference Paper

FINITE ELEMENT FRACTURE MECHANICS ANALYSIS OF CREEP RUPTURE OF FUEL ELEMENT CLADDING = ANALYSE, PAR UNE TECHNIQUE DE MECANIQUE DE FRACTURE D'ELEMENTS FINIS, DE LA RUPTURE PAR FLUAGE DE LA GAINE D'ELEMENTS COMBUSTIBLES NUCLEAIRESCHOPRA PS.1974; NUCL. ENGNG DESIGN; NETHERL.; DA. 1974; VOL. 29; NO 1; PP. 7-21; BIBL. 15 REF.Article

REMOTIZED APPARATUS FOR DETERMINING OXYGEN IN IRRADIATED REACTOR FUELS AND CLADDING MATERIALSMACDOUGALL CS; SMITH ME; WATERBURY GR et al.1972; LA-DC-72-524, CONF-720903-8; U.S.A.; DA. 1972; PP. (18 P.); BIBL. 2 REF.; MICROFICHEReport

VANADIUM ALLOY CLADDING DEVELOPMENT. FINAL REPORTWHITLOW GA; NADLER RA; SVEDBERG RC et al.1970; WARD-3791-47; U.S.A.; DA. 1970; PP. (201 P.); BIBL. 19 REF.; MICROFICHEReport

LE CONTROLE DES TUBES PAR ULTRASONS SANS MISE EN ROTATIONPERDIJON J.1975; REV. METALLURG.; FR.; DA. 1975; VOL. 72; NO 1; PP. 73-81; ABS. ALLEM. ANGL. ESP.; BIBL. 11 REF.Article

A THERMAL ANALYSIS OF HOT SPOTS ON FAST-REACTOR FUEL CLADDING DUE TO DEPOSITION OF LOW - CONDUCTIVITY MATERIALS = ANALYSE THERMIQUE DES POINTS CHAUDS SUR DES GAINES DE COMBUSTIBLES DE REACTEURS RAPIDES, DUS AU DEPOT DE MATERIAUX DE FAIBLE CONDUCTIVITEISHII M; CHAWLA TC.1975; NUCL. SCI. ENGNG; U.S.A.; DA. 1975; VOL. 56; NO 2; PP. 188-195; BIBL. 11 REF.Article

AKTUELLE FRAGEN ZUM BRENNSTOFF-ZYKLUS. III. IST DIE HERSTELLUNG VON UO2-BRENNSTAEBEN MIT ZIRCALOY-HUELLEN INDUSTRIELL ETABLIERT = QUESTIONS ACTUELLES SUR LE CYCLE COMBUSTIBLE. III. LA FABRICATION DE BARRES COMBUSTIBLES EN UO2 AVEC GAINES DE ZIRCALOY EST-ELLE ETABLIE INDUSTRIELLEMENT.HAUSNER H.1973; ATOMWIRTSCH. ATOMTECH.; DTSCH.; DA. 1973; VOL. 18; NO 4; PP. 168-170; ABS. ANGL. FRSerial Issue

STRESS-RUPTURE BEHAVIOR OF AUSTENITIC STAINLESS STEEL TUBING. INFLUENCE OF COLD WORK AND EFFECT OF SURFACE DEFECTSLAURITZEN T.1972; GEAP-13897; U.S.A.; DA. 1972; PP. (32 P.); BIBL. 11 REF.; MICROFICHEReport

USER'S GUIDE FOR GAPCON: A COMPUTER PROGRAM TO PREDICT FUEL-TO-CLADDING HEAT TRANSFER COEFFICIENTS IN OXIDE FUEL PINSHORN GR; PANISKO FE.1972; UEDI-TME 72-128; U.S.A.; DA. 1972; PP. (75 P.); BIBL. 25 REF.; MICROFICHEReport

BREVET 2.276.896 (A1) (7423486). A 5 JUILLET 1974. INSTALLATION DE SOUDAGE PAR BOMBARDEMENT ELECTRONIQUEsdPatent

Mechanical design issues and resolutions of a dual cooled fuel for the OPR-1000KIM, Hyung-Kyu; KIM, Jae-Yong; YOON, Kyung-Ho et al.Nuclear engineering and design. 2011, Vol 241, Num 6, pp 2119-2127, issn 0029-5493, 9 p.Article

Chemical reactions of caesium, tellurium and oxygen with fast breeder reactor cladding alloys. VII: The kinetics of the corrosion od 12R72HV steel by Cs2Te at at constant O2 potential; comparison with rates for PE16 alloyPULHAM, R. J; RICHARDS, M. W.Journal of nuclear materials. 1995, Vol 223, Num 2, pp 180-185, issn 0022-3115Article

Accident scenarios of the TRIGA Mark II reactor in ViennaVILLA, Mario; HAYDN, Markus; STEINHAUSER, Georg et al.Nuclear engineering and design. 2010, Vol 240, Num 12, pp 4091-4095, issn 0029-5493, 5 p.Article

A new method to study hydriding processes from the inner surfaces of fuel claddingsSACEDON, J. L; DIAZ, M; MOYA, J. S et al.Journal of nuclear materials. 2004, Vol 327, Num 1, pp 11-18, issn 0022-3115, 8 p.Article

Development of the ultra-microhardness technique for post irradiation examination of fuel cladding tubesNAKATSUKA, M; NOMATA, T; UMEHARA, H et al.Journal of Nuclear Science and Technology. 1998, Vol 35, Num 5, pp 344-352, issn 0022-3131Article

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