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PROPERTIES, BLENDING AND HOMOGENIZATION OF (U,TH)O2-UO2 POWDER. = PROPRIETES, MELANGE ET HOMOGENEISATION D'UNE POUDRE DE (U,TH)O2-UO2RADFORD KC; BRATTON RJ.1975; J. MATER. NUCL.; PAYS-BAS; DA. 1975; VOL. 57; NO 3; PP. 287-302; ABS. FR. ALLEM.; BIBL. 15 REF.Article

METALLIC AND DISPERSED FUEL BEHAVIOR. = COMPORTEMENT DU COMBUSTIBLE METALLIQUE ET DISPERSE1975; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1975; VOL. 22; PP. 188-195; BIBL. DISSEM.; (AM. NUCL. SOC. WINTER MEET. TRANS.; SAN FRANCISCO, CALIF.; 1975)Conference Paper

FUEL FABRICATION. = FABRICATION DU COMBUSTIBLE1975; IN: NUCL. ENERGY MATURITY. TRANS. 1ST CONF. EUR. NUCL. SOC.; PARIS; 1975; HINSDALE; AM. NUCL. SOC.; DA. 1975; PP. 591-620; BIBL. DISSEM.Conference Paper

FUEL FABRICATION = FABRICATION DU COMBUSTIBLE1975; TRANS. AMER. NUCL. SOC.; U.S.A.; DA. 1975; VOL. 20; PP. 591-620; BIBL. DISSEM.; (EUR. NUCL. CONF. NUCL. ENERGY MATURITY. TRANS. 1ST CONF. EUR. NUCL. SOC.; PARIS, FR.; 1975)Conference Paper

FUEL KERNEL MATERIALS FOR THE THORIUM CYCLE HTGR = MATERIAUX DE NOYAUX DE COMBUSTIBLE POUR REACTEUR A HAUTE TEMPERATURE A REFROIDISSEMENT PAR GAZ A CYCLE DU THORIUMSTANSFIELD OM; GULDEN TD; HARMON DP et al.1973; IN: NUCL. FUEL PERFORMANCE. INT. CONF. PROC.; LONDON; 1973; S.L.; BR. NUCL. ENERGY SOC.; DA. 1973; PP. (5 P.); BIBL. 12 REF.Conference Paper

BREVET PROCEDE POUR LA PREPARATION DE COEURS DE MATIERES FERTILES OU DE MATIERES FERTILES ET DE MATIERES COMBUSTIBLES DE REACTEURS NUCLEAIRES1979; ; FRA; DA. 1979-03-23; FR/A1/2.398.369; DEP.78-21488/1978-07-20; PR. DE/P 27 33 384.2/1977-07-23Patent

MEASUREMENT OF THERMAL PROPERTIES OF NUCLEAR MATERIALS BY LASER FLASH METHOD. = MESURE DES PROPRIETES THERMIQUES DE MATERIAUX NUCLEAIRES PAR UNE METHODE A ECLAIR DE LASERTAKAHASHI Y; MURABAYASHI M.1975; J. NUCL. SCI. TECHNOL.; JAP.; DA. 1975; VOL. 12; NO 3; PP. 133-144; BIBL. 1 P. 1/2Article

A NONAQUEOUS REPROCESSING METHOD FOR THORIUM-BASED FUELSBATES JK; JARDINE LJ; KRUMPELT M et al.1980; A.C.S. SYMP. SER.; USA; DA. 1980; NO 117; PP. 207-217; BIBL. 15 REF.Article

VERFAHRANSTECHNISCHE UND KERNTECHNISCHE ASPEKTE BEI AUSLEGUNG, FERTIGUNG UND MONTAGE VON KOMPONENTEN DES CHEMISCHEN PROZESSTEILS DER VERSUCHSANLAGE JUPITER = PROCESS ENGINEERING AND NUCLEAR ENGINEERING ASPECTS OF THE DESIGN, FABRICATION AND ASSEMBLY AT THE COMPONENTS OF THE CHEMICAL PROCESS PART OF JUPITER EXPERIMENTAL FACILITY = ASPECTS TECHNIQUES ET NUCLEAIRES DANS LA CONCEPTION, LA REALISATION ET LE MONTAGE DES ELEMENTS DE LA PARTIE TRAITEMENT CHIMIQUE DE L'INSTALLATION EXPERIMENTALE JUPITERKAISER G; WOLF J; AHLERS H et al.1978; KERNTECHNIK; DEU; DA. 1978; VOL. 20; NO 12; PP. 550-555; (3 P.); BIBL. 4 REF.; IDEM ENGArticle

LATTICE DEFECTS AND IRRADIATION DAMAGE IN THO2, UO2 AND (U, PU)O2. = DEFAUTS DU RESEAU ET DOMMAGE DU A L'IRRADIATION DANS THO2, UO2 ET U,PU)O2MATZKE H.1976; IN: PLUTONIUM 1975 OTHER ACTINIDES. INT. CONF. 5. PROC.; BADEN-BADEN; 1975; AMSTERDAM; NORTH-HOLLAND; DA. 1976; PP. 801-831; BIBL. 227 REF.Conference Paper

BILDUNG DER AKTINIDEN IN BESTRAHLTEN HTGR-BRENNELEMENTEN. = ACTINIDE FORMATION IN IRRADIATED HTGR FUEL ELEMENTS = FORMATION DES ACTINIDES DANS LES ELEMENTS COMBUSTIBLES IRRADIES DE REACTEUR HAUTE TEMPERATURE A REFROIDISSEMENT PAR GAZDOS SANTOS AM.1976; BER. KERNFORSCH.-ANLAGE JUELICH; DTSCH.; DA. 1976; NO 1284; PP. 1-73; ABS. ANGL. PORT. FR.; BIBL. 1 P. 1/2Serial Issue

BREVET 2.339.234 (A1) (77 01625). - 30 JANVIER 1977. PROCEDE POUR RETRAITER ET RECYCLER SANS PERTES DES DECHETS D'URANIUM ET DE THORIUM DANS LA PRODUCTION D'ELEMENTS COMBUSTIBLES EN URANIUM ET THORIUM.sdPatent

DETERMINATION OF COMPOSITION OF THO2 AND (TH,U)O2 FUEL KERNELS WITH AL2O3/SIO2 ADDITIVESFRANZ H; GOERGENYI T; JUNGEN W et al.1978; Z. (FRESENIUS') ANAL. CHEM.; DEU; DA. 1978; VOL. 292; NO 5; PP. 353-358; ABS. GER; BIBL. 17 REF.Article

WIEDERAUFARBEITUNG THORIUMHALTIGER KERNBRENNSTOFFE IM LICHTE PROLIFERATIONSSICHERER BRENNSTOFFKREISLAEUFE = REPROCESSING THORIUM-CONTAINING NUCLEAR FUELS WITH REGARD TO PROLIFERATION RESISTANT FUEL CYCLES = LE RETRAITEMENT DES COMBUSTIBLES NUCLEAIRES CONTENANT DU THORIUM A LA LUMIERE DES CYCLES DE COMBUSTIBLES A L'ABRI DE LA PROLIFERATIONMERZ E.1978; NATURWISSENSCHAFTEN; DEU; DA. 1978; VOL. 65; NO 8; PP. 424-431; ABS. ENG; BIBL. 12 REF.Article

CHEMICAL FORM OF THE SOLID FISSION PRODUCTS IN (TH,U)O2 SIMULATING HIGH BURNUPUGAJIN M; SHIRATORI T; SHIBA et al.1979; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1979; VOL. 84; NO 1-2; PP. 26-38; BIBL. 46 REF.Article

THERMODYNAMIC AND EXPERIMENTAL FEASIBILITY OF DECONTAMINATING THORIUM-URANIUM FUELS BY A VOLATILIZATION TECHNIQUECARLSON ON; CHIOTTI P; SHIERS L et al.1980; CHEM. SOC., SPEC. PUBL.; GBR; DA. 1980; NO 34; PP. 169-179; BIBL. 11 REF.Conference Paper

THERMODYNAMIC ASSESSMENT OF THE HTGR FUEL SYSTEM TH-U-C-OUGAJIN M; SHIBA K.1978; J. MATER. NUCL.; NLD; DA. 1978; VOL. 74; NO 2; PP. 354-357; BIBL. 28 REF.Article

CESIUM RELEASE DATA FOR BISO-COATED PARTICLES.STOVER D; HECKER R.1977; NUCL. TECHNOL.; U.S.A.; DA. 1977; VOL. 35; NO 2; PP. 465-474; BIBL. 18 REF.Article

ABBRAND BEDINGTES SCHWELLEN HOCHDICHTER OXIDISCHER HTR-BRENNSTOFFKERNE. = SWELLING OF HIGH-DENSITY OXIDE KERNELS OF HTR FUEL = GONFLEMENT DES NOYAUX OXYDES A DENSITE ELEVES DE COMBUSTIBLE POUR REACTEUR HAUTE TEMPERATUREPROKSCH E; KNOTIK K; STRIGL A et al.1977; J. MATER. MED.; PAYS-BAS; DA. 1977; VOL. 66; NO 3; PP. 263-272; ABS. ANGL. FR.; BIBL. 9 REF.Article

SOLVENT PERFORMANCE IN THTR NUCLEAR FUEL REPROCESSING. II. ON THE FORMATION OF DIBUTYL PHOSPHORIC ACID BY RADIOLYTIC AND HYDROLYTIC DEGRADATION OF THE TBP-N-PARAFFIN EXTRACTANT.BRODDA BG; HEINEN D.1977; NUCL. TECHNOL.; U.S.A.; DA. 1977; VOL. 34; NO 3; PP. 428-437; BIBL. 25 REF.Article

REPROCESSING TECHNOLOGY IN THE HTGR FUEL CYCLE.KAISER G; MERZ E; ZIMMER E et al.1977; IN: NUCL. POWER FUEL CYCLE. INT. CONF. PROC.; SALZBURG; 1977; VIENNA; INT. AT. ENERGY AGENCY; DA. 1977; PP. 661-671; ABS. FR. RUSSE ESP.; BIBL. 14 REF.Conference Paper

THE EXTERNAL GELATION OF THORIUM PROCESS FOR PREPARATION OF THO2 AND (TH, U)O2 FUEL KERNELSRINGEL HD; ZIMMER E.1979; NUCL. TECHNOL.; USA; DA. 1979; VOL. 45; NO 3; PP. 287-298; BIBL. 15 REF.Article

SOLVENT PERFORMANCE IN THTR NUCLEAR FUEL REPROCESSING. I. CALCULATION OF DOSES RECEIVED BY TBP-N-PARAFFIN EXTRACTANT IN REPROCESSING THTR FUELS APPLYING A THOREX FLOWSHEET.BRODDA BG; HEINEN D.1977; NUCL. TECHNOL.; U.S.A.; DA. 1977; VOL. 34; NO 3; PP. 420-427; BIBL. 14 REF.Article

SEPARATION OF LONG-LIVED ALPHA -EMITTERS FROM HIGHLY RADIOACTIVE SOLUTIONS IN THE THORIUM-URANIUM FUEL CYCLEWENZEL U; BRANQUINHO CL; HERZ D et al.1980; A.C.S. SYMP. SER.; USA; DA. 1980; NO 117; PP. 533-545; BIBL. 10 REF.Article

FABRICATION OF LARGE (TH, U)O2 MICROSPHERESMATTHEWS RB; SWANSON ML.1979; AMER. CERAM. SOC. BULL.; USA; DA. 1979; VOL. 58; NO 2; PP. 223-227; BIBL. 15 REF.Article

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