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ZUM RADIALEN UND AXIALEN WAERMETRANSPORT IN REAKTORBRENNSTAEBEN = RADIAL AND AXIAL HEAT TRANSFER IN REACTOR FUEL RODS = TRANSFERT DE CHALEUR RADIAL ET AXIAL DANS DES BARRES COMBUSTIBLES DE REACTEURSWEST G.1981; WAERME-STOFFUEBERTRAG; ISSN 0042-9929; DEU; DA. 1981; VOL. 15; NO 1; PP. 1-8; ABS. ENG; BIBL. 7 REF.Article

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

DAS BESTRAHLUNGSVERHALTEN ALTEN VON BRENNSTAEBEN IN LEITUNGSREAKTOREN. = IRRADIATION BEHAVIOUR OF FUEL RODS IN POWER NUCLEAR REACTORS = COMPORTEMENT A L'IRRADIATION DES BARRES COMBUSTIBLES DANS LES REACTEURS DE PUISSANCEGEITHOFF D.1976; CHEMIKER-ZTG; DTSCH.; DA. 1976; VOL. 100; NO 11; PP. 483-495; ABS. ANGL.; BIBL. 41 REF.Article

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

DIE BEDEUTUNG DER BRENNSTOFF-VERUNEINIGUNGEN FUER DAS BRENNSTABSVERHALTEN = THE SIGNIFICANCE OF FUEL IMPURITIES FOR THE FUEL ROD BEHAVIOUR = IMPORTANCE DES IMPURETES DU COMBUSTIBLE POUR LE COMPORTEMENT DES BARRES COMBUSTIBLESGOETZMANN O.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 301-308; ABS. ENG; BIBL. 12 REF.Conference Paper

SUPERCONDUCTING MAGNETOMETER FOR QUALITY CONTROL OF NUCLEAR FUEL RODS = MAGNETOMETRE SUPRACONDUCTEUR POUR UN CONTROLE DE QUALITE DE BARRES DE COMBUSTIBLE NUCLEAIRELANDRY JD; SCHOENIG FC; GROSSMAN LN et al.1982; JOURNAL OF APPLIED PHYSICS; ISSN 0021-8979; USA; DA. 1982; VOL. 53; NO 11; PART. 2; PP. 8260-8262; BIBL. 3 REF.Conference Paper

DISSOLUTION AND STORAGE EXPERIMENT WITH 4.75-WT%-235 U-ENRICHED UO2 RADSMANARANCHE JC; MANGIN D; MAUBERT L et al.1980; NUCL. TECHNOL.; ISSN 0029-5450; USA; DA. 1980; VOL. 50; NO 2; PP. 148-157; BIBL. 11 REF.Article

ZUR WAERMEFREISETZUNG AUS BRENNSTAEBEN BEI SCHNELLENN LASTWECHSEL = HEAT RELEASE FROM FUEL RODS FOR FAST LOAD TRANSIENTS = DEGAGEMENT DE CHALEUR DE BARRES COMBUSTIBLES POUR DES VARIATIONS RAPIDES DE LA CHARGEWEST G.1980; WAERME- U. STOFFUEBERTRAG; DEU; DA. 1980; VOL. 14; NO 2; PP. 75-80; ABS. ENG; BIBL. 8 REF.Article

URANUS. A COMPUTER PROGRAMME FOR THE THERMAL AND MECHANICAL ANALYSIS OF THE FUEL RODS IN A NUCLEAR REACTOR.LASSMANN K.1978; NUCL. ENGNG DESIGN; NETHERL.; DA. 1978; VOL. 45; NO 2; PP. 325-342; BIBL. 16 REF.Article

EXPERIENCE IN FABRICATING PLUTONIUM RECYCLE FUEL.STOLL W.1977; IN: TOP. MEET. PLUTONIUM FUEL CYCLE. PROC.; BAL HARBOUR, FLA.; 1977; HINSDALE, ILL.; AM. NUCL. SOC.; DA. 1977; PP. (8P.)Conference Paper

LANGJAEHRIGE BETRIEBSERFAHRUNGEN MIT URAN- UND PLUTONIUM-BRENN-ELEMENTEN IM KERNKRAFTWERK GUNDREMMINGEN. = EXPERIENCE GAINED FOR SEVERAL YEARS WITH THE GUNDREMMUNGEN NUCLEAR POWER PLANT URANIUM AND PLUTONIUM FUEL ELEMENTS = EXPERIENCE ACQUISE DEPUIS PLUSIEURS ANNEES PAR LA CENTRALE NUCLEAIRE DE GUNDREMMINGEN AVEC LES ELEMENTS COMBUSTIBLES D'URANIUM ET DE PLUTONIUMEICKELPASCH N; SEEPOLT R.1977; ENERGIE; DTSCH.; DA. 1977; VOL. 29; NO 10; PP. 326-329Article

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

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