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

IRRADIATION-INDUCED CREEP OF MECHANICALLY BLENDED POROUS UO₂-PUO₂ FUEL.DIENST W.1976; J. MATER. NUCL.; PAYS-BAS; DA. 1976; VOL. 61; NO 2; PP. 185-191; ABS. FR. ALLEM.; BIBL. 12 REF.Article

UO₂-PUO₂-BRENNSTAB-KAPSELBESTRAHLUNGEN DER VERSUCHSGRUPPE MOL 8B UND C AUSWERTUNG VON MESS- UND NACHUNTERSUCHUNGSERGEBNISSEN. = UO₂-PUO₂ FUEL PIN CAPSULE IRRADIATION MOL 8B AND C. EVALUATION OF MEASUREMENT AND POST-IRRADIATION EXAMINATION RESULTS = ESSAIS MOL B ET C D'IRRADIATION EN CAPSULES D'AIGUILLES A UO₂-PUO₂. EVALUATION DES RESULTATS DES MESURES ET DES OBSERVATIONS APRES IRRADIATIONDIENST W; ZIMMERMANN H.1976; KERNFORSCH.-ZENTR. KARLSRUHE, K.F.K.; DTSCH.; DA. 1976; NO 2355; PP. 1-42; ABS. ANGL.; BIBL. 9 REF.Serial Issue

BESTRAHLUNGSVERHALTEN VON UAL₃-AL UND UAL₂-AL-DISPERSIONSBRENNSTOFFPLATTEN. = IRRADIATION BEHAVIOUR OF UAL₃-AL AND UAL₂-AL DISPERSION FUEL PLATES = COMPORTEMENT SOUS IRRADIATION DES PLAQUES DE COMBUSTIBLE DISPERSE EN UAL₃-AL ET UAL₂-ALDIENST W; GAUSMANN G.1975; KERNFORSCH.-ZENTR. KARLSRUHE, K.F.K.; DTSCH.; DA. 1975; NO 2199; PP. 1-38; ABS. ANGL.; BIBL. 1 P.Serial Issue

Mechanical properties of neutron-irradiated ceramic materialsDIENST, W.Journal of nuclear materials. 1994, Vol 211, Num 3, pp 186-193, issn 0022-3115Article

Swelling, densification and creep of (U, Pu) C fuel under irradiationDIENST, W.Journal of nuclear materials. 1984, Vol 124, pp 153-158, issn 0022-3115Article

Swelling, densification and creep of (U, Pu)C fuel under irradiation = Schwellen, Verdichtung und Kriechen von (U, Pu)C-Kernbrennstoff unter BestrahlungDIENST, W.Journal of nuclear materials. 1984, Vol 124, pp 153-158, issn 0022-3115Article

CREEP AND DENSIFICATION OF UO₂ UNDER IRRADIATION = FLUAGE ET DENSIFICATION DE UO₂ SOUS IRRADIATIONBRUCKLACHER D; DIENST W.1973; IN: NUCL. FUEL PERFORMANCE. INT. CONF. PROC.; LONDON; 1973; S.L.; BR. NUCL. ENERGY SOC.; DA. 1973; PP. (3 P.); BIBL. 5 REF.Conference Paper

IRRADIATION BEHAVIOUR OF UAL₃-AL DISPERSION FUELS FOR THERMAL HIGH FLUX REACTORS.DIENST W; NAZARE S; THUEMMLER F et al.1977; J. MATER. NUCL.; PAYS-BAS; DA. 1977; VOL. 64; NO 1-2; PP. 1-13; ABS. FR. ALLEM.; BIBL. 13 REF.Article

ARBEITEN ZUR BRENNELEMENT-ENTWICKLUNG FUER DEN SCHNELLEN BRUTREAKTOR SNR-300 = TRAVAUX POUR LA MISE AU POINT D'ELEMENTS COMBUSTIBLES POUR LE REACTEUR SURREGENERATEUR RAPIDE SNR-300BOHM H; DIENST W; KUMMERER K et al.1974; KERNFORSCH.-ZENTR. KARLSRUHE, K.F.K.; DTSCH.; DA. 1974; NO 1999; PP. 1-345; ABS. ANGL.; BIBL. DISSEM.Article

UO₂-PUO₂-BRENNSTAB-KAPSELBESTRAHLUNGEN DER VERSUCHSGRUPPE FR2-5A. AUSWERTUNG VON NACHBESTRAHLUNGSUNTERSUCHUNGSERGEBNISSEN = IRRADIATIONS EN CAPSULE DE BARRES DE COMBUSTIBLE UO₂-PUO₂ DU GROUPE DE RECHERCHES FR2-SA. EVALUATION DES RESULTATS DES ETUDES APRES IRRADIATIONDIENST W; GOTZMANN O; SCHULZ B et al.1975; KERNFORSCH.-ZENTR. KARLSRUHE, K.F.K.; DTSCH.; DA. 1975; NO 2134; PP. 1-40; ABS. ANGL.; BIBL. DISSEM.Article

Selectionm characterization and testing of ceramic breeder materialsKUMMERER, K. R; DIENST, W.Journal of nuclear materials. 1985, Vol 133-134, pp 176-180, issn 0022-3115Article

UO₂-PUO₂-BRENNSTAB-BESTRAHLUNG DFR-435. AUSWERTUNG DER UNTERSUCHUNGSERGEBNISSE AN DEN BESTRAHLTEN BRENNSTAEBEN. = UO₂-PUO₂ FUEL ROD IRRADIATION DFR-435. EVALUATION OF THE POST-IRRADIATION EXAMINATION RESULTS = ESSAI D'IRRADIATION DFR-435 DE BARRES COMBUSTIBLES A UO₂-PUO₂. EVALUATION DES RESULTATS D'OBSERVATION DES BARRES IRRADIEESDIENST W; GOTZMANN O; KLEYKAMP H et al.1976; KERNFORSCH.-ZENTR. KARLSRUHE, K.F.K.; DTSCH.; DA. 1976; NO 2218; PP. 1-74; ABS. ANGL.; BIBL. 7 REF.Serial Issue

FUEL-CLADDING MECHANICAL INTERACTION IN FAST BREEDER FUEL PINS; OBSERVATIONS AND ANALYSISDIENST W; GUERIN Y; GATESOUPE JP et al.1980; J. NUCL. MATER.; ISSN 0022-3115; NLD; DA. 1980; VOL. 91; NO 1; PP. 73-84; BIBL. 18 REF.Article

Thermal shock resistance of ceramic materials in melt immersion testsDIENST, W; SCHOLZ, H; ZIMMERMANN, H et al.International journal of high technology ceramics. 1989, Vol 5, Num 6, pp 365-370, issn 0267-3762, 6 p.Article

Chemical interactions between UO₂ and zircaloy-4 from 1000 to 2000°CDIENST, W; HOFMANN, P; KERWIN-PECK, D. K et al.Nuclear technology. 1984, Vol 65, Num 1, pp 109-124, issn 0029-5450Article

ADVANCES IN CARBIDE FUEL ELEMENT DEVELOPMENT FOR APPLICATION TO FAST REACTORS.DIENST W; KLEYKAMP H; MUHLING G et al.1977; IN: NUCL. POWER FUEL CYCLE. INT. CONF. PROC.; SALZBURG; 1977; VIENNA; INT. AT. ENERGY AGENCY; DA. 1977; PP. 493-510; ABS. FR. RUSSE ESP.; BIBL. 11 REF.Conference Paper

Cladding strain due to power cycles on FBR test fuel pins: corroborating results and alternativesDIENST, W; MÜLLER-LYDA, I; STEINER, H et al.Journal of nuclear materials. 1983, Vol 119, Num 2-3, pp 141-145, issn 0022-3115Article

Fracture mechanics analysis of iodine-induced crack growth in zircaloy-4 tubing between 500 and 700°C = Analyse de la mécanique de rupture d'une fissure produite par de l'iode dans des tubes en zircaloy-4 pour des températures comprises entre 500 et 700°CDIENST, W; ECKSTEIN, H; HOFMANN, P et al.Nuclear engineering and design. 1983, Vol 75, Num 2, pp 223-233, issn 0029-5493Article

Kriechverhalten von Cr-Ni-Stahl unter Halogen- und Chalkogen-Einwirkung bei hohen Temperaturen = Creep behaviour of Cr-Ni steel under the influence of halogens and chalcogens at high temperaturesDIENST, W; GIBS, V; GOETZMANN, O et al.Werkstoffe und Korrosion. 1982, Vol 33, Num 10, pp 533-541, issn 0043-2822Article

UO₂-PUO₂-BRENNSTABBUENDEL-BESTRAHLUNG DFR-350. AUSWERTUNG DER UNTERSUCHUNGSERGEBNISSE AN DEN BESTRAHLTEN BRENNSTAEBEN = ESSAI DFR-350 D'IRRADIATION DE FAISCEAUX D'AIGUILLES DE UO₂ ET PUO₂. EVALUATION DES RESULTATS D'EXAMEN APRES IRRADIATIONEHRLICH K; GOTZMANN O; KLEYKAMP H et al.1974; KERNFORSCH.-ZENTR. KARLSRUHE, K.F.K.; DTSCH.; DA. 1974; NO 1960; PP. 1-102; ABS. ANGL.; BIBL. DISSEM.Article

Cladding strain due to power cycles on FBR test fuel pins: corroborating results and alternatives = Huellrohrverformung infolge von Lastzyklen an SBR-Testbrennstaeben: bestaetigende Ergebnisse und AlternativenDIENST, W; MUELLER-LYDA, I; STEINER, H et al.Journal of nuclear materials. 1983, Vol 119, Num 2/3, pp 141-145, issn 0022-3115Article

Tritium release of Li₄SiO₄, Li₂O and beryllium and chemical compatibility of beryllium with Li₄SiO₄, Li₂O and steel (SIBELIUS irradiation)DIENST, W; SCHILD, D; WERLE, H et al.Kernforschungszentrum Karlsruhe. 1992, Num 5109, pp I-III, issn 0303-4003, 38 p.Serial Issue

Investigations on ceramic materials for fusion technologyDIENST, W; FETT, T; HEIDINGER, R et al.Journal of nuclear materials. 1990, Vol 174, Num 1, pp 102-109, issn 0022-3115Article

Reduction of the mechanical strength of Al₂O₃, AlN and SiC under neutron irradiationDIENST, W.Journal of nuclear materials. 1992, Vol 191-94, Num A, pp 555-559, issn 0022-3115Conference Paper