STRESS ANALYSIS FOR LONG CYLINDRICAL OXIDE FUEL RODS IN NUCLEAR REACTORSCHI KANG CHENG.1979; NUCL. SCI. J.; TWN; DA. 1979; VOL. 16; NO 2; PP. 105-111; ABS. CHI; BIBL. 4 REF.Article

AUMENTO DI TEMPERATURA PROVOCATO DA UNA MACCHIA CALDA IN UNA BARRETTA DI COMBUSTIBILE NUCLEARE = TEMPERATURE INCREASE IN A HOT SPOT OF A NUCLEAR FUEL ROD = AUGMENTATION DE TEMPERATURE PROVOQUEE PAR UN POINT CHAUD DANS UNE BARRE COMBUSTIBLE NUCLEAIRELORENZINI E; SPIGA M.1978; TERMOTECNICA; ITA; DA. 1978; VOL. 32; NO 10; PP. 544-551; ABS. ENG; BIBL. 9 REF.Article

BREVET 2.347.621 (A1) (76 34669). - 17 NOVEMBRE 1976. PROCEDE POUR ALLUMER UNIFORMEMENT UNE MASSE INFLAMMABLE ALLONGEE ET BARRE COMBUSTIBLE SERVANT A L'EXECUTION DU PROCEDE.sdPatent

BASIC PROBLEMS OF USED ROD REPROCESSINGFOMIN VV; SHEVCHENKO VB; ZEMLYANUKHIN VI et al.1977; ATOM. ENERG.; S.S.S.R.; DA. 1977; VOL. 43; NO 6; PP. 481-486; BIBL. 27 REF.Article

BREVET 2.311.262 (A1) (76 13326). - 5 MAI 1976. SECHAGE DE CORPS ENCAPSULES, NOTAMMENT BARRES DE COMBUSTIBLE NUCLEAIRE PAR PHASES SUCCESSIVES DE MISE SOUS VIDE, REMPLISSAGE DE DESHYDRATANT, MISE SOUS VIDE ET REMPLISSAGE DE GAZ INERTE.sdPatent

CAN ENCAPSULATION TO MAKE SPENT FUEL HANDLING EASIER1980; NUCL. ENGNG INTERNATION.; GBR; DA. 1980; VOL. 25; NO 296; PP. 46-47Article

AN EVALUATION OF THE THERMAL-HYDRAULIC AND FUEL ROD THERMAL AND MECHANICAL DEFORMATION BEHAVIOR DURING THE FIRST POWER BURST FACILITY NUCLEAR BLOWDOWN TESTSMACDONALD PE; BROUGHTON JM; SPORE JW et al.1979; NUCL. TECHNOL.; USA; DA. 1979; VOL. 44; NO 3; PP. 401-410; BIBL. 7 REF.Article

CALCUL NUMERIQUE DE PHENOMENES THERMIQUES TRANSITOIRES DANS DES ELEMENTS COMBUSTIBLES DE REACTEURS NUCLEAIRES PAR LA TECHNIQUE DES ELEMENTS FINIS = NUMERICAL CALCULATION OF TRANSIENT THERMAL PHENOMENA IN NUCLEAR REACTOR FUEL ELEMENTS USING FINITE ELEMENT TECHNIQUEMATHIEU P; DE WERGIFOSSE C.1978; UNIV. LIEGE, FAC. SCI. APPL., COLLECT. PUBL.; BEL; DA. 1978; NO 71; PP. 90-116; ABS. ENG/GER; BIBL. 12 REF.Article

THERMOGRAPHIC IMAGING OF NUCLEAR FUEL RODS.OLDBERG S JR; HONEY RC; FALCONER DG et al.1977; NUCL. TECHNOL.; U.S.A.; DA. 1977; VOL. 33; NO 2; PP. 231-234; BIBL. 2 REF.Article

ESTUDIOS EXPERIMENTALES EN TERMOFLUIDODINAMICA DE REACTORES. 5. SIMULACION DE BARRAS COMBUSTIBLES = EXPERIMENTAL STUDIES OF NUCLEAR REACTOR HYDRODYNAMICS AND THERMODYNAMICS. 5. MODELLING OF FUEL RODS = ETUDES EXPERIMENTALES D'HYDRODYNAMIQUE ET DE THERMODYNAMIQUE DE REACTEURS. 5. SIMULATION DE BARRES COMBUSTIBLESPONCE DE LEON MM.1976; ENERG. NUCL.; ESP.; DA. 1976; VOL. 20; NO 104; PP. 521-533; BIBL. 1 P.Article

HERSTELLUNG UND PRUEFUNG VON BRENNSTABELEMENTPROBEN MIT NATRIUMBINDUNG = MANUFACTURING AND TESTING SODIUM-BONDED FUEL ROD SAMPLES = FABRICATION ET ESSAI D'ECHANTILLONS DE BARRES COMBUSTIBLES A LIAISON AU SODIUMHIMPEL G; BARKLEIT G.1981; KERNENERGIE; ISSN 0023-0642; DDR; DA. 1981; VOL. 24; NO 9; PP. 357-360; ABS. ENG/RUS; BIBL. 6 REF.Article

POTENTIAL CAUSES OF FAILURES ASSOCIATED WITH POWER CHANGES IN LWR'SBOUFFIOUX P; VAN VLIET J; DERAMAIX P et al.1979; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1979; VOL. 87; NO 2-3; PP. 251-258; BIBL. 22 REF.Article

GAS CHROMATOGRAPHY IN NUCLEAR FUEL ROD FABRICATIONEECKHOUT F; MASSA C; VANHELLEMONT G et al.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 127-139; BIBL. 4 REF.Conference Paper

USE OF FUEL THERMOCOUPLE TRANSIENT RESPONSE FOR DATA VERIFICATION AND FUEL ROD MODELINGLANNING DD; BARNES BO; SCHEFFLER WA et al.1980; NUCL. TECHNOL.; USA; DA. 1980; VOL. 50; NO 1; PP. 95-107; BIBL. 7 REF.Article

EXPERIENCE WITH IAEA SAFEGUARDS AT A JAPANESE LEU FUEL FABRICATION FACILITYOSABE T.1979; NUCL. MATER. MANAG.; USA; DA. 1979; VOL. 8; NO 1; PP. 51-62Article

EFFECTS OF THE PARAMETERS OF A FUEL ELEMENT AND OF ITS DEFECT ON TEMPERATURE FIELDSMINASHIN VE; GORELOV IN; RUMYANTSEV VN et al.1979; INZHENER.-FIZ. ZH.; BYS; DA. 1979; VOL. 36; NO 4; PP. 737-741; ABS. ENG; BIBL. 5 REF.Article

A DIGITAL TRANSFER MATRIX FOR FUEL PIN HEAT TRANSFER.GREEN MD; KORNFILT J.1978; NUCL. SCI. ENGNG; U.S.A.; DA. 1978; VOL. 65; NO 2; PP. 385-393Article

POST IRRADIATION EXAMINATION OF THE THE FUEL DISCHARGED FROM THE TRINO VERCELLESE REACTOR AFTER THE 2ND IRRADIATION CYCLE.BARBERO P; BIDOGLIO G; BRESESTI M et al.1977; EUR-5605E; LUXEMBOURG; DA. 1977; PP. 1-90; BIBL. 10 REF.Report

HIGH SPEED MULTI-CHANNEL NUCLEAR FUEL SCANNER.MILLER H; SHEPARD SH.1976; NUCL. MATER. MANAG.; U.S.A.; DA. 1976; VOL. 5; NO 3; PP. 149-155Article

MIXED-OXIDE FUELS.1976; IN: SAFEGUARDING NUCL. MATER. PROC. SYMP.; VIENNA; 1975; VIENNA; INT. AT. ENERGY AGENCY; DA. 1976; VOL. 2; PP. 539-610; BIBL. DISSEM.Conference Paper

HUELLTEMPERATURMESSUNG MIT THERMOELEMENTEN AN VORBESTRAHLTEN LWR-BRENNSTAB-PRUEFLINGEN = CLODDING TEMPERATURE MEASUREMENT BY THERMOCOUPLES ON PRE-IRRADIATED LWR FUEL ROD SAMPLES = MESURE DE LA TEMPERATURE DE GAINES A L'AIDE DE THERMOELEMENTS SUR DES ECHANTILLONS DE BARRES COMBUSTIBLES DE REACTEUR A EAU LEGERE PREIRRADIESLEILING W.1981; KERNFORSCHUNGSZENT. KARLSR.; ISSN 0303-4003; DEU; DA. 1981; NO 3100; 117 P.; ABS. ENG; BIBL. 37 REF.Serial Issue

BETRIEBSVERHALTEN DER ERSTEN DREI NACHLADUNGEN (125 STANDARD-BRENNELEMENTE) UND 29 SONDER-BRENNELEMENTE IM SIEDEWASSERREAKTOR DODEWAARD = OPERATIONAL BEHAVIOUR OF THE FIRST THREE RELOADING (125 STANDARD FUEL ELEMENTS) AND OF 29 SPECIAL FUEL ELEMENTS IN DODEWAARD'S BWR = COMPORTEMENT EN SERVICE DES TROIS PREMIERES RECHARGES (125 ELEMENTS COMBUSTIBLES STANDARDS) ET DE 29 ELEMENTS COMBUSTIBLES SPECIAUX DANS LE REACTEUR A EAU BOUILLANTE DE DODEWAARDMAJOOR EBM.1980; VGB KRAFWERKSTECH.; DEU; DA. 1980; VOL. 60; NO 7; PP. 523-526Article

BREVET. DISPOSITIF D'EMMAGASINAGE DE COMBUSTIBLE EPUISE SUR LE SITE D'UN REACTEUR NUCLEAIRE1980; ; FRA; DA. 1980-01-18; FR/A1/2.426.315; DEP.79-12209/1979-05-14; PR. US/905.671/1978-05-15Patent

ZUM WAERMEDURCHGANG IM BEREICH ZWISCHEN HUELLE UND BRENNSTOFF EINES BRENNSTABES = HEAT TRANSFER BETWEEN FUEL AND CLADDING IN A FUEL ROD = TRANSFERT DE CHALEUR ENTRE LA GAINE ET LE COMBUSTIBLE D'UNE BARRE COMBUSTIBLELASSMANN K.1979; WAERME- U. STOFFUEBERTRAG.; DEU; DA. 1979; VOL. 12; NO 3-4; PP. 185-202; ABS. ENG; BIBL. 42 REF.Article

MODELING OF THE TRANSIENT HEAT TRANSFER IN A NUCLEAR REACTOR FUEL ROD USING A VARIATIONAL PROCEDURELEBON G; MATHIEU P; VAN VLIET J et al.1978; NUCL. ENGNG DESIGN; NLD; DA. 1978-1979; VOL. 51; NO 2; PP. 133-142; BIBL. 13 REF.Article