PLUTONIUM-ENRICHED THERMAL FUEL PRODUCTION EXPERIENCE IN BELGIUMLEBLANC JM.1983; NUCLEAR TECHNOLOGY; ISSN 0029-5450; USA; DA. 1983; VOL. 61; NO 3; PP. 416-422; BIBL. 8 REF.Article

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INFLUENCE OF THE PROCESS PARAMETERS ON THE FABRICATION OF UO₂-PUO₂ PELLETS USING THE GRANULATION TECHNIQUEVOLLATH D; WEDEMEYER H; HANUS H et al.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 191-197; BIBL. 10 REF.Conference Paper

OXYGEN POTENTIALS OF (TH, U)O_2+X SOLID SOLUTIONSUGAJIN M.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 110; NO 2-3; PP. 140-146; BIBL. 15 REF.Article

ZUSAMMENHAENGE ZWISCHEN DEM BETRIEBSVERHALTEN VON SBR-BRENNSTOFF UND ANFORDERUNGEN AN DIE PRODUKTQUALITAET = RELATIONSHIPS BETWEEN THE OPERATING BEHAVIOUR OF RBR FUEL AND ITS QUALITY REQUIREMENTS = CORRELATIONS ENTRE LE COMPORTEMENT EN SERVICE DU COMBUSTIBLE DE SURREGENERATEUR ET LES CONDITIONS REQUISES CONCERNANT SA QUALITEDUENNER P.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 291-299; BIBL. 14 REF.Conference Paper

DEVELOPMENT OF A PROCESS FOR THE CO-CONVERSION OF PU-U NITRATE MIXED SOLUTIONS TO MIXED-OXIDE POWDER USING A MICROWAVE HEATING METHODKOIZUMI M; OHTSUKA K; ISAGAWA H et al.1983; NUCLEAR TECHNOLOGY; ISSN 0029-5450; USA; DA. 1983; VOL. 61; NO 1; PP. 55-70; BIBL. 9 REF.Article

FAST REACTOR FUEL FABRICATION AND WASTE MANAGEMENTWILKINSON WL.1982; FAST REACTOR FUEL CYCLES. INTERNATIONAL CONFERENCE/1981-11-09/LONDON; GBR; LONDON: BRITISH NUCLEAR ENERGY SOCIETY; DA. 1982; PP. 171-180; BIBL. 5 REF.Conference Paper

FABRICATION OF PLUTONIUM-ENRICHED FUEL AT BELGONUCLEAIREBEMDEN EV.1981; NUCL. TECHNOL.; ISSN 0029-5450; USA; DA. 1981; VOL. 53; NO 2; PP. 186-195; BIBL. 5 REF.Article

EVALUATION DE L'EMISSION DE MATIERES RADIOACTIVES DANS DES CONDITIONS ACCIDENTELLES POUR UNE USINE DE FABRICATION DE COMBUSTIBLES. (RAPPORT FINAL) = ASSESSMENT OF RADIOACTIVE MATERIAL EMISSION IN ACCIDENT CONDITIONS FOR A FUEL MANUFACTURING PLANT (FINAL REPORT)1981; ; LUX; LUXEMBOURG: OFFICE DES PUBLICATIONS OFFICIELLES DES COMMUNAUTES EUROPEENNES; DA. 1981; EUR/7364; 189 P.; 30 CM; BIBL. 31 REF.; SCIENCES ET TECHNIQUES NUCLEAIRESReport

COMPARISON OF PHYSICAL CHEMICAL PROPERTIES OF POWDERS AND RESPIRABLE AEROSOLS OF INDUSTRIAL MIXED URANIUM AND PLUTONIUM OXIDE FUELSEIDSON AF.1982; HEALTH PHYS.; ISSN 0017-9078; USA; DA. 1982; VOL. 42; NO 4; PP. 531-536; BIBL. 19 REF.Article

DEVELOPMENT OF THE STRUCTURE DURING REDUCTION SINTERING OF UO₂-PUO₂ PELLETS FROM GRANULATED POWDERSVOLLATH D; ELBEL H; WEDEMEYER H et al.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 181-189; BIBL. 6 REF.Conference Paper

FAST BREEDER FUEL FABRICATION WITHIN THE GERMAN PROGRAMSTOLL W.1982; FAST REACTOR FUEL CYCLES. INTERNATIONAL CONFERENCE/1981-11-09/LONDON; GBR; LONDON: BRITISH NUCLEAR ENERGY SOCIETY; DA. 1982; PP. 189-193Conference Paper

INTERDIFFUSION AND CHEMICAL DIFFUSION IN THE UO₂-(U,PU)O₂ SYSTEMGLASSER LEME D; MATZKE HJ.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 211-220; BIBL. 27 REF.Conference Paper

AUSWIRKUNGEN VON BRENNSTOFFTOLERANZEN AUF DIE BETRIEBSDATEN EINES SCHNELLEN REAKTORS = EFFECTS OF FUEL TOLERANCES ON THE OPERATING DATA OF A RAPID REACTOR = INFLUENCES DES TOLERANCES DU COMBUSTIBLE SUR LES DONNEES D'EXPLOITATION D'UN REACTEUR RAPIDECOORS D; WEBER W; SPENKE H et al.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 253-259; BIBL. 1 REF.Conference Paper

U.K. DEVELOPMENT TOWARD REMOTE FABRICATION OF BREEDER REACTOR FUELNELSON RL; PARKINSON N; KENT WCL et al.1981; NUCL. TECHNOL.; ISSN 0029-5450; USA; DA. 1981; VOL. 53; NO 2; PP. 196-203; BIBL. 11 REF.Article

Experience with the ammonium uranyl plutonyl carbonate coconversion process for mixed-oxide fuel fabricationROEPENACK, H; SCHNEIDER, V. W; DRUCKENBRODT, W. G et al.American Ceramic Society bulletin. 1984, Vol 63, Num 8, pp 1051-1061, issn 0002-7812Article

The chemical state of the fission products in oxide fuelsKLEYKAMP, H.Journal of nuclear materials. 1985, Vol 131, Num 2-3, pp 221-246, issn 0022-3115Article

Study of homogeneisation and cation interdiffusion in mixed UO₂-PuO₂ compacts by X-ray diffractionVERMA, R.Journal of nuclear materials. 1984, Vol 120, Num 1, pp 65-73, issn 0022-3115Article

Oxygen potential measurements in irradiated mixed oxide fuelEWART, F; LASSMANN, K; MATZKE, H et al.Journal of nuclear materials. 1984, Vol 124, pp 44-55, issn 0022-3115Article

Development of a process for co-conversion of Pu-U nitrate mixed solutions to mixed oxide powder using microwave heating methodKOIZUMI, M; OHTSUKA, K; OHSHIMA, H et al.Journal of Nuclear Science and Technology. 1983, Vol 20, Num 7, pp 529-536, issn 0022-3131Article

Roll compaction and granulation system for nuclear fuel materialGOLDMANN, L. H. JR; HOLLEY, C. C.Institute for briquetting and agglomeration. Biennial conference. 17. 1982, pp 333-345Conference Paper

DETERMINATION OF PU/U+PU RATIO IN FBR FUEL PELLETS BY X-RAY FLUORESCENCE ANALYSISDIELS P; LECOCQ R.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 115-120; BIBL. 5 REF.Conference Paper

DAS BERTRAHLUNGSEXPERIMENT MOL-7B = MOL-7B IRRADIATION EXPERIMENT = L'EXPERIENCE D'IRRADIATION MOL-7BKUMMERER K; WEIMAR P.1982; KERNFORSCHUNGSZENT. KARLSR.; ISSN 0303-4003; DEU; DA. 1982; NO 3256; PAG. MULT.; ABS. ENG; BIBL. 17 REF.Serial Issue

DIE GADOLINIUMBESTIMMUNG IN KERNBRENNSTOFFEN-EIN METHODENVERGLEICH = DETERMINATION OF GADOLINIUM IN NUCLEAR FUELS. A COMPARISON OF METHODSCOERDT W; CRUBELLATI R; MAINKA E et al.1982; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1982; VOL. 106; NO 1-3; PP. 109-113; BIBL. 16 REF.Conference Paper

BERECHNUNG DES SAUERSTOFFPOTENTIALS VON (U,PU)O_{2 +OU- X} MITTELS DEFEKTMODELLEN UND GEMESSENER DATEN IM TEMPERATURBEREICH VON 1000 BIS 1700 K. = CALCUL DU POTENTIEL DE L'OXYGENE DE (U,PU)O_{2 +OU- X} PAR MODELE DU DEFAUT ET RESULTATS DE MESURES DANS LE DOMAINE DES TEMPERATURES DE 1000 A 1700 KBREITUNG W.1976; KERNFORSCH.-ZENTR. KARLSRUHE, K.F.K.; DTSCH.; DA. 1976; NO 2363; PP. 1-27; ABS. ANGL.; BIBL. 20 REF.Serial Issue