DETERMINATION OF OXYGEN IN IRRADIATED REACTOR FUELS AND CLADDING MATERIALSMACDOUGALL CS; SMITH ME; WATERBURY GR et al.1972; LA-4971; U.S.A.; DA. 1972; PP. (8 P.); BIBL. 6 REF.; MICROFICHEReport

THE EFFECT OF IRRADIATION LEVEL ON THE RUPTURE TEMPERATURE OF ZIRCALOY-2 CLAD URANIUM FUEL TUBESREID DL; HESSON GM.1971; BNWL-1576; U.S.A.; DA. 1971; PP. (40 P.); BIBL. 5 REF.; MICROFICHEReport

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

Study on underclad cracking in nuclear reactor vessel steelsHORIYA, T; TAKEDA, T; YAMATO, K et al.Journal of pressure vessel technology. 1985, Vol 107, Num 1, pp 30-35, issn 0094-9930Article

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

MASS TRANSFER IN THE PLUTONIA-IRIDIUM SYSTEM = TRANSFERT DE MASSE DANS LE SYSTEME PLUTONIUM DIOXYDE-IRIDIUMGOLDENBERG N; ALEXANDER CA; KENT RA et al.1975; IN: THERMODYN. NUCL. MATER. 1974. PROC. SYMP. THERMODYN. NUCL. MATER. I.; VIENNA; 1974; VIENNA; IAEA; DA. 1975; PP. 123-131; BIBL. 2 REF.Conference Paper

ULTRASONIC TESTING OF IRRADIATED FUEL SHEATHINGPATEL HB; DITSCHUN A; HUNTON AE et al.1975; MATER. EVALUAT.; U.S.A.; DA. 1975; VOL. 33; NO 3; PP. 49-55; BIBL. 15 REF.Article

CALCULATIONAL PROCEDURE FOR DETERMINING CREEP COLLAPSE OF LWR FUELS RODS = PROCEDURE DE CALCUL POUR LA DETERMINATION DE L'ECRASEMENT PAR FLUAGE DES BARRES DE COMBUSTIBLES DE REACTEURS A EAU LEGEREMERCKX KR.1974; NUCL. ENGNG DESIGN; NETHERL.; DA. 1974; VOL. 31; NO 1; PP. 95-101; BIBL. 11 REF.Article

FABRICATION OF (U,ZR) C-FUELED/TUNGSTEN-CLAD SPECIMENS FOR IRRADIATION IN THE PLUM BROOK REACTOR FACILITY1972; N72-30598, NASA-CR-120945, GULF-GA-A-12121; U.S.A.; DA. 1972; PP. (39 P.); BIBL. 6 REF.; MICROFICHEReport

THEORETISCHE UNTERSUCHUNGEN ZUR WANDTEMPERATURMESSUNG AN SIMULIERTEN BRENNSTAEBEN FUER THERMODYNAMISCHE EXPERIMENTE IN NATRIUM = ETUDES THEORIQUES POUR LA MESURE DES TEMPERATURES DE PAROI SUR DES COMBUSTIBLES SIMULES AU COURS D'EXPERIENCES THERMODYNAMIQUES DANS LE SODIUMMOLLER R; TSCHOKE H.1972; KFK-1555; DTSCH.; DA. 1972; PP. (40 P.); ABS. ANGL.; BIBL. 8 REF.Report

ARTIFICIAL DEFECTS USED AT RISO AS CALIBRATION STANDARDS FOR ULTRASONIC INSPECTION OF THIN-WALLED TUBINGDOMANUS J; NIELSEN N.1972; RISO REPORT NO 273; U.S.A.; DA. 1972; PP. (24 P.)Report

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

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