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Results 1 to 25 of 185065

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PREPARATION AND SINTERNING OF OXIDE REDUCED AND ARC MELTED URANIUM-PLUTONIUM CARBIDES.ZOPE BD.1978; TRANS. INDIAN CERAM. SOC.; IND; DA. 1978; VOL. 37; NO 1; PP. 1-7; BIBL. 4 REF.Article

CREEP BEHAVIOR OF URANIUM CARBIDE-BASED ALLOYSSELTZER MS; WRIGHT TR; MOAK DP et al.1975; J. AMER. CERAM. SOC.; U.S.A.; DA. 1975; VOL. 58; NO 3-4; PP. 138-142; BIBL. 20 REF.Article

FRACTURE-SURFACE ENERGY AND FRACTURE TOUGHNESS OF (U, PU) C AND (U, PU) (C, O) = ENERGIE SUPERFICIELLE DE RUPTURE ET RESISTANCE A LA RUPTURE DE (U, PU) (C, O)MATZKE HJ; MEYRITZ V; ROUTBORT JL et al.1983; JOURNAL OF THE AMERICAN CERAMIC SOCIETY; ISSN 0002-7820; USA; DA. 1983; VOL. 66; NO 3; PP. 183-188; BIBL. 28 REF.Article

GRUNDLEGENDE UNTERSUCHUNGEN ZUM REAKTIONSSINTERN VON URAN-PLUTONIUM-KARBID = RECHERCHES FONDAMENTALES POUR LE FRITTAGE REACTIONNEL DU CARBURE D'URANIUM ET DE PLUTONIUMKRAUTH A; MULLER N; NEUMANN G et al.1972; J. MATER. NUCL.; PAYS-BAS; DA. 1972; VOL. 45; NO 2; PP. 163-170; ABS. ANGL., FR.; BIBL. 7 REF.Serial Issue

RADIATION DAMAGE IN CRYSTALLINE INSULATORS, OXIDES AND CERAMIC NUCLEAR FUELSMATZKE H.1982; RADIAT. EFF.; ISSN 0033-7579; GBR; DA. 1982; VOL. 64; NO 1-4; PP. 3-33; BIBL. 181 REF.Conference Paper

CONTRIBUTION A L'ETUDE DU DEGAGEMENT DES GAZ DE FISSION ET DU GONFLEMENT DES COMBUSTIBLES NUCLEAIRES DE TYPE CARBURE UC ET (U0,8),PU0,2))CGROFF A.1976; RAPP. C.E.A.; FR.; DA. 1976; NO 4742; PP. 1-79; H.T. 17; ABS. ANGL.; BIBL. 5 P.Serial Issue

THE PLASTIC DEFORMATION BEHAVIOUR OF CERAMIC NUCLEAR FUELS AT STRESS CHANGESMUELLER LYDA I.1980; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1980; VOL. 88; NO 1; PP. 161-167; BIBL. 10 REF.Article

CERAMIC UTILIZATION IN THE NUCLEAR INDUSTRY. II: CUSSENT STATUS AND FUTURE TRENDSROBERTS JTA.1979; POWDER METALLURGY INTERNATION.; DEU; DA. 1979; VOL. 11; NO 2; PP. 72-80; ABS. GER/FREArticle

SWELLING ANALYSIS OF HIGHLY-RATED MX-TYPE LMFBR FUELS. II. MICROSCOPIC SWELLING BEHAVIOURRONCHI C; RAY ILF; THIELE H et al.1978; J. MATER. NUCL.; NLD; DA. 1978; VOL. 74; NO 2; PP. 193-211; ABS. FRE/GER; BIBL. 16 REF.Article

FABRICATION OF ADVANCED LMFBR FUELS AT BARCCANGULY C; ROY PR.1982; FAST REACTOR FUEL CYCLES. INTERNATIONAL CONFERENCE/1981-11-09/LONDON; GBR; LONDON: BRITISH NUCLEAR ENERGY SOCIETY; DA. 1982; PP. 181-188; BIBL. 8 REF.Conference Paper

DAMAGE ENERGY FUNCTIONS IN POLYATOMIC MATERIALSCOULTER CA; PARKIN DM.1980; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1980; VOL. 88; NO 2-3; PP. 249-260; BIBL. 20 REF.Article

LMFBR DESIGN FOR SAFETY AND PROLIFERATION RESISTANCE, WITH EXCELLENT PERFORMANCEFISCHER GJ; KOUTS HJC; CERBONE RJ et al.1982; FAST REACTOR FUEL CYCLES. INTERNATIONAL CONFERENCE/1981-11-09/LONDON; GBR; LONDON: BRITISH NUCLEAR ENERGY SOCIETY; DA. 1982; PP. 213-217; BIBL. 7 REF.Conference Paper

THE INITIAL STAGES OF SINTERING AND HOT-PRESSING IN VIBRO-COMPACTED FUELSMATTHEWS JR.1979; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1979; VOL. 87; NO 2-3; PP. 356-366; BIBL. 22 REF.Article

IRRADIATION INDUCED CREEP OF CERAMIC NUCLEAR FUELS.DIENST W.1977; J. MATER. NUCL.; PAYS-BAS; DA. 1977; VOL. 65; NO 1; PP. 1-8; ABS. FR. ALLEM.; BIBL. 32 REF.; (MEAS. IRRADIAT. ENHANCED CREEP NUCL. MATER. INT. CONF. PROC.; PETTEN, NETH.; 1976)Conference Paper

MATERIAL TRANSPORT IN THE TEMPERATURE GRADIENT OF FAST REACTOR FUELSBOBER M; SCHUMACHER G.1973; ADV. NUCL. SCI. TECHNOL.; U.S.A.; DA. 1973; VOL. 7; PP. 121-179; BIBL. 72 REF.Serial Issue

Carbon species in the crystal structures of uranium-transition-element carbides, UMC2JONES, D. W; MCCOLM, I. J; YERKESS, J et al.Journal of solid state chemistry (Print). 1988, Vol 74, Num 2, pp 304-313, issn 0022-4596Article

THE RATIO OF GRAIN BOUNDARY ENERGY TO SURFACE ENERGY OF NUCLEAR CERAMICS AS DETERMINED FROM PORE GEOMETRIESHODKIN EN.1980; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1980; VOL. 88; NO 1; PP. 7-14; BIBL. 17 REF.Article

PREPARATION AND THERMOCHEMICAL STABILITY OF URANIUM-ZIRCONIUM-CARBONITRIDES.KOUHSEN C; NAOUMIDIS A; NICKEL H et al.1976; J. MATER. NUCL.; PAYS-BAS; DA. 1976; VOL. 61; NO 1; PP. 88-98; ABS. FR. ALLEM.; BIBL. 34 REF.Article

EQUATION OF STATE STUDIES OF FAST BREEDER OXIDE AND CARBIDE FUELS BY DYNAMIC PULSE HEATING TECHNIQUES, AND PREDICTION OF THEIR CRITICAL POINT DATA BY VARIOUS THEORETICAL MODELSOHSE RW; BABELOT JF; FREZZOTTI A et al.1981; HIGH TEMP. SCI.; ISSN 0018-1536; USA; DA. 1981; VOL. 13; NO 1-4; PP. 35-78; BIBL. 195 REF.Article

OPTIMISATION OF FUEL PIN DIAMETER FOR OXIDE AND CARBIDE FUELS FOR A MEDIUM SIZED FAST BREEDEL REACTORBIR SINGH; BHOJE SB; JOHN TM et al.1982; FAST REACTOR FUEL CYCLES. INTERNATIONAL CONFERENCE/1981-11-09/LONDON; GBR; LONDON: BRITISH NUCLEAR ENERGY SOCIETY; DA. 1982; PP. 233-236; BIBL. 5 REF.Conference Paper

FORMATION DE MONOCARBURES MIXTES D'URANIUM ET DE TA LORS DE LA REDUCTION SIMULTANEE DE LEURS OXYDES PAR LE CARBONEKISELEV VA; VLASOV VG; BUKIN VE et al.1972; ZH. PRIKL. KHIM.; S.S.S.R.; DA. 1972; VOL. 45; NO 8; PP. 1657-1660; BIBL. 21 REF.Serial Issue

KERNEL MIGRATION FOR HTGR FUELS FROM THE SYSTEM TH-U-PU-C-O-N.LINDEMER TB; PEARSON RL.1977; J. AMER. CERAM. SOC.; U.S.A.; DA. 1977; VOL. 60; NO 1-2; PP. 5-14; BIBL. 49 REF.Article

FABRICATION OF URANIUM-PLUTONIUM MIXED CARBIDE PELLETSSUZUKI Y; SASAYAMA T; ARAI Y et al.1981; J. NUCL. SCI. TECHNOL.; ISSN 0022-3131; JPN; DA. 1981; VOL. 18; NO 1; PP. 61-70; BIBL. 14 REF.Article

EIN MODELL ZUR SPANNUNGSANALYSE IN COATED PARTICLES, SEINE MOEGLICHKEITEN UND SEINE PROBLEMATIK = MODELE POUR L'ANALYSE DES CONTRAINTES DANS LES PARTICULES DE COMBUSTIBLE ENROBEES, SES POSSIBILITES ET SES PROBLEMESBONGARTZ K.1972; BER. STUD.-GESELLSCH. FOERDER. KERNENERGIEVERWERT. SCHIFFBAU SCHIFFAHRT HAMBURG; DTSCH.; DA. 1972; NO 22; PP. 1-13; BIBL. 3 REF.Serial Issue

TECHNOLOGICAL ASPECTS OF FUEL PRODUCTION FOR DIFFERENT POWER REACTORSRESHETNIKOV FG; KOTEL'NIKOV RB; KUSHAKOVSKIJ VI et al.1977; IN: NUCL. POWER FUEL CYCLE. INT. CONF. PROC.; SALZBURG; 1977; VIENNA; INT. AT. ENERGY AGENCY; DA. 1977; PP. 477-491; ABS. ANGL. FR. ESP.; BIBL. 4 REF.Conference Paper

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