H. J. Matzke
#136,681
Most Influential Person Now
H. J. Matzke's AcademicInfluence.com Rankings
H. J. Matzkechemistry Degrees
Chemistry
#3350
World Rank
#4363
Historical Rank
Chemical Engineering
#377
World Rank
#392
Historical Rank

H. J. Matzkeengineering Degrees
Engineering
#4952
World Rank
#6179
Historical Rank
Nuclear Engineering
#15
World Rank
#16
Historical Rank
Applied Physics
#1328
World Rank
#1357
Historical Rank

Download Badge
Chemistry Engineering
H. J. Matzke's Degrees
- PhD Materials Science and Engineering Stanford University
- Masters Nuclear Engineering University of California, Berkeley
Why Is H. J. Matzke Influential?
(Suggest an Edit or Addition)H. J. Matzke's Published Works
Number of citations in a given year to any of this author's works
Total number of citations to an author for the works they published in a given year. This highlights publication of the most important work(s) by the author
Published Works
- Radiation effects in crystalline ceramics for the immobilization of high-level nuclear waste and plutonium (1998) (784)
- Radiation Damage Effects in Zirconia. (1999) (307)
- Gas release mechanisms in UO2—a critical review (1980) (254)
- A Pragmatic Approach to Modelling Thermal Conductivity of Irradiated UO2 Fuel. Review and Recommendations (1996) (243)
- Radiation damage in crystalline insulators, oxides and ceramic nuclear fuels (1982) (206)
- Effects of self-radiation damage in Cm-doped Gd2Ti2O7 and CaZrTi2O7 (1986) (202)
- MICROSTRUCTURAL FEATURES OF SIMFUEL : SIMULATED HIGH-BURNUP UO2-BASED NUCLEAR FUEL (1991) (187)
- ION-BOMBARDMENT-INDUCED RADIATION DAMAGE IN SOME CERAMICS AND IONIC CRYSTALS: DETERMINED BY ELECTRON DIFFRACTION AND GAS RELEASE MEASUREMENTS (1966) (133)
- Materials research on inert matrices: a screening study (1999) (107)
- On the rim effect in high burnup UO2LWR fuels (1992) (105)
- Transmission electron microscopy observation on irradiation-induced microstructural evolution in high burn-up UO2 disk fuel (2002) (100)
- Optimisation of inert matrix fuel concepts for americium transmutation (1999) (98)
- Swift heavy ion and fission damage effects in UO2 (2000) (95)
- On uranium self-diffusion in UO2 and UO2+x (1969) (94)
- Self-radiation damage in Gd2Ti2O7 (1985) (93)
- Thermal and physicochemical properties important for the long term behavior of nuclear waste glasses (1993) (88)
- Radiation damage in UO2 by swift heavy ions (1997) (85)
- Formation of the rim structure in high burnup fuel (1997) (84)
- Radiation enhanced diffusion in UO2 and (U, Pu)O2 (1983) (77)
- Transmission electron microscopy study of fission product behaviour in high burnup UO2 (1992) (76)
- Thermal conductivity of hyperstoichiometric SIMFUEL (1995) (74)
- Diffusion processes and surface effects in non-stoichiometric nuclear fuel oxides UO2+x, and (U, Pu)O2±x (1983) (73)
- Polygonization and high burnup structure in nuclear fuels (1997) (66)
- Inert matrices for the transmutation of actinides: fabrication, thermal properties and radiation stability of ceramic materials (1998) (66)
- Oxide fuel transients (1989) (66)
- An electron microscopy study of the RIM structure of a UO2 fuel with a high burnup of 7.9% FIMA (1997) (65)
- Location of Inert Gas Atoms in KCl, CaF2, and UO2 Crystals by H+ and He2+ (1967) (62)
- Irradiation-induced nanostructures (2000) (60)
- Oxygen potential measurements in high burnup LWR U02 fuel (1995) (58)
- The surface energy of UO2 as determined by hertzian indentation (1980) (57)
- Polygonization of single crystals of the fluorite-type oxide UO2 due to high dose ion implantation + (1994) (57)
- Thermal conductivity of SIMFUEL (1992) (56)
- Oxygen potential in the rim region of high burnup UO2 fuel (1994) (54)
- INERT GAS DIFFUSION AND RADIATION DAMAGE IN IONIC CRYSTALS AND SINTERS FOLLOWING ION BOMBARDMENT. (1968) (54)
- Fission-enhanced self-diffusion of uranium in UO2 and UC (1973) (53)
- Radiation damage in nuclear materials (1992) (52)
- Fluorine self-diffusion in CaF2 and BaF2 (1970) (49)
- High-resolution transmission electron microscopy of ion irradiated uranium oxide (1996) (48)
- Leaching behaviour of UO2 containing α-emitting actinides (2000) (46)
- Diffusion in Doped UO 2 (1966) (45)
- A computational study of the effect of Xe concentration on the behaviour of single Xe atoms in UO2 (1995) (43)
- α-Radiolysis and α-Radiation Damage Effects on uo 2 Dissolution Under Spent Fuel Storage Conditions (1999) (42)
- Radiation damage-enhanced dissolution of UO2 in water (1992) (42)
- Point defects and transport properties in carbides (1984) (41)
- Xenon migration and trapping in doped ThO2 (1967) (40)
- Effects of radiation on microstructure and fracture properties in Ca2Nd8(SiO4)6)2 (1986) (38)
- Modelling of UO2-based SIMFUEL thermal conductivity The effect of the burnup (1994) (37)
- The effect of fission spikes on fission gas re-solution (1973) (37)
- Radiation damage in nuclear fuel materials: the “rim” effect in UO2 and damage in inert matrices for transmutation of actinides (1996) (37)
- Radiation damage and xenon release in quartz and fused silica following ion bombardment (1966) (37)
- Stopping Power of 1-9-MeV He + + Ions in U O 2 , (U, Pu) O 2 , and Th O 2 (1973) (36)
- Hertzian indentation of thorium dioxide, ThO2 (1980) (35)
- 4 – Diffusion in Nonstoichiometric Oxides (1981) (34)
- Ion implantation studies of UO2 and UN (1992) (34)
- Science of advanced LMFBR fuels : solid state physics, chemistry, and technology of carbides, nitrides, and carbonitrides of uranium and plutonium (1986) (34)
- Corrosion and dissolution studies of UO2 containing α-emitters (2002) (34)
- Recovery and Restructuring induced by Fission Energy Ions in High Burnup Nuclear Fuel (2009) (33)
- A Channeling Study of the Structure of U4O9 (1971) (32)
- Erratum: Surface damage in UO2 due to mechanical polishing and ion bombardment (1983) (32)
- Heavy ion induced damage in MgAl2O4, an inert matrix candidate for the transmutation of minor actinides (1999) (32)
- Burn and bury option for plutonium (1999) (32)
- Temperature and fission rate effects on the rim structure formation in a UO2 fuel with a burnup of 7.9% FIMA (1998) (31)
- Diffusion in Carbides and Nitrides: Unsolved Problems (1992) (30)
- Temperature Dependence of Hertzian Indentation Fracture Surface Energy of ThO2 (1981) (29)
- Ion bombardment induced phase transformations and inert gas mobility in the semiconductors Ge, Si, and GaAs (1970) (29)
- The determination of rare gas diffusion following recoil labelling of plane or spherical solids (1967) (28)
- THE EFFECT OF CRYSTALLINITY AND BOMBARDMENT DOSE ON THE PENETRATION OF 40-keV XENON IONS IN IONIC CRYSTALS AND CERAMICS (1966) (28)
- Application of “channeling” techniques to fission gas release studies (1969) (28)
- Radiation damage effects in nuclear materials (1988) (28)
- α-Spectroscopy as a tool to measure very small diffusion coefficients (1974) (27)
- Indentation testing of nuclear-waste glasses (1984) (27)
- Oxygen potential of high burn-up fast breeder oxide fuel (1988) (27)
- On the correlation between solid-particle erosion and fracture parameters in SiC (1983) (27)
- Calculations on the in-pile behavior of fission gas in oxide fuels (1972) (27)
- Uranium self‐diffusion in stoichiometric uranium monocarbide (1974) (25)
- Stopping power and range of α- particles in (U, Pu)C and UC and application to self diffusion measurements using alpha-spectroscopy (1972) (25)
- Helium damage and helium effusion in fully stabilised zirconia (2002) (24)
- Damage produced in magnesium aluminate spinel by high energy heavy ions including fission products of fission energy: microstructure modifications (2001) (24)
- Grain‐Boundary Diffusion of U in Pure and Doped Uranium Carbides with Different C/U Ratios (1975) (24)
- Thermophysical property measurements and ion-implantation studies on CePO4 (1998) (23)
- Self-diffusion of plutonium in uranium-plutonium mononitride (1978) (23)
- Ion transport in ceramics (1991) (22)
- The behaviour of single atoms of molybdenum in urania (1997) (22)
- Interdiffusion and chemical diffusion in the UO2 — (U,Pu)O2 system (1982) (22)
- Oxygen potential measurements in irradiated mixed oxide fuel (1984) (22)
- Dependence upon oxygen potential of the interdiffusion in single crystalline UO2-(U, Pu)O2 (1984) (22)
- EFFECT OF HUMIDITY ON THE SURFACE OXIDATION OF UC SINGLE CRYSTALS AT ROOM TEMPERATURE. (1969) (21)
- Fluorine self diffusion in LiF and NaF (1970) (21)
- Radiation damage in spinel single crystals (1996) (21)
- Specific heat of UO2-based SIMFUEL (1997) (21)
- Channeling of MeV Projectiles in Diatomic Ionic Crystals (1971) (21)
- Fission gas bubble behaviour in uranium dioxide (1993) (21)
- On the effect of TiO2 additions on sintering of UO2 (1966) (21)
- Dense fuels in Europe (1989) (20)
- Volatile fission product bubble behaviour in uranium dioxide (1995) (20)
- Self-diffusion of uranium in uranium dicarbide UC2 (1973) (19)
- Rare-gas mobility in some anisotropic ceramic oxides: Al2O3, Cr2O3, Fe2O3, TiO2, U3O8 (1967) (19)
- Microstructure of Swift Heavyion Irradiated MgAl 2 0 4 Spinel (1998) (19)
- Zr diffusion in α-ti measured by RBS and HIRBS (1994) (19)
- Mechanisms and kinetics of leaching of UO2 in water (1991) (19)
- Trapping of fission xenon in neutron irradiated UC (1969) (19)
- Gradients of U, Pu and O at surfaces of (U, Pu)O2±x (1977) (19)
- Incorporation of Pu and Other Actinides in Borosilicate Glass and in Waste Ceramics (1996) (19)
- Resonant X-Ray Scattering Studies of the Magnetic Structure near the Surface of an Antiferromagnet. (2000) (19)
- DIFFUSION OF RADIOACTIVE LEAD IN LEAD METASILICATE GLASS (1960) (19)
- Fuel research and basic aspects of fuel in-pile performance (1989) (18)
- Formation and behaviour of barium silicate in UO2-based SIMFUEL (1991) (18)
- The evaporation behavior and metal self-diffusion processes in (U,Pu)C and (U,Pu)O2 (1974) (18)
- The Thermal Behavior of Pt/Al2O3 Catalysts Studied with the Channeling Technique (1981) (18)
- Oxygen potential measurements on irradiated oxide nuclear fuel (1979) (18)
- Self-diffusion of plutonium in high burn-up simulated (U, Pu) (C, N) and (U, Pu) N (1980) (18)
- Uranium self-diffusion in impurity-doped uranium carbide (1974) (17)
- Leaching Behavior and α-Decay Damage Accumulation of UO2 Containing Short-Lived Actinides (2000) (17)
- Radiation damage, its recovery and platinum behavior and lattice location in ion bombarded MgO and Al2O3 as used for catalytic studies (1982) (17)
- Study of Uranium-Plutonium Carbide-Based Fuel Simulating High Burnup (1977) (16)
- He-Ion Damage and He-Release from Spinel MgAl2O4. (2000) (16)
- The release of some non-gaseous fission products from CaF2, UO2 and ThO2 (1967) (15)
- Alkali diffusion and radiation effects in the waste glass VG 98/12 (1988) (14)
- The effect of composition and radiation on the fracture of a nuclear waste glass (1983) (14)
- Channeling study of coherent Pt precipitates in MgO single crystals (1981) (14)
- Quasiepitaxial Growth of a Monoclinic Phase on UO2 Single Crystals upon Leaching in H2O. (1997) (14)
- Radiation defects in the oxygen sublattice of UO2 single crystals (1993) (14)
- Crystallographic shear and ordered reduction of UO2 (1972) (14)
- Neptunium doping of the crystalline ceramic waste form synroc B (1988) (14)
- Hertzian crack growth in ThO2 observed by serial sectioning (1982) (13)
- Self-radiation damage in actinide host phases of nuclear waste forms. [CaâNdâ(SiOâ)âOâ; GdâTiâOâ; CaZrTiâOâ] (1984) (13)
- Analysis of the structure of layers on U02 leached in H2O (1996) (13)
- Some comments to “the thermodynamics of mixed oxide reactor-fuels” (1978) (13)
- On ion implantation in silicon carbide (1970) (13)
- Leaching of SIMFUEL in simulated granitic water: comparison to results in demineralized water (1996) (12)
- Inert gas diffusion in silver—I. Cold worked silver (1972) (12)
- Depth-profiling studies of ion-implanted cesium and rubidium in simfuel and uranium dioxide (1993) (12)
- The effect of Fe, Ni and W impurities on uranium diffusion in uranium monocarbide (1974) (12)
- Damage recovery in the U-sublattice of ion implanted UO2 between 5 K and 2000 K (1991) (11)
- Range, energy loss, energy straggling and damage production for α-particles in uranium dioxide (1999) (11)
- Uranium self-diffusion in UC doped with Y, Zr, La or Ce (1980) (11)
- Sodium diffusion in the nuclear waste glass GP 98/12 (1989) (11)
- Rare gas release as a means to measure the low temperature oxidation of metals: brass, Cu, Ni, Ti and stainless steel (1976) (11)
- Helium behaviour and defect evolution in amorphous spinel during thermal annealing (2002) (11)
- Fracture toughness and leaching behavior of ion bombarded waste glasses (1984) (11)
- Surface analysis of coated flat glasses: a comparison of various techniques (1990) (10)
- A channeling study of ion implantation damage in UO2, and UN (1990) (10)
- Introduction to workshop on radiation effects in nuclear waste materials (1988) (10)
- On the stabilization of radiation damage by rare gas atoms (1969) (10)
- Study of the diffusion of cesium in stainless steel using ion beams (1977) (10)
- Diffusion in Carbides and Nitrides (1990) (10)
- Determination of hydrogen in leached UO2 and SYNROC (1990) (10)
- Self-Diffusion Processes in Nuclear Carbonitrides UCxN1 − x and (U, Pu)C0.8N0.2 (1978) (10)
- The diffusion of uranium in U3O8 (1983) (9)
- Mass Transport in Carbides and Nitrides (1990) (9)
- DIFFUSION OF TRITIUM FROM LITHIUM FLUORIDE. (1966) (9)
- Effects of xenon implantation in spinel-zirconia/ceria composites (2001) (9)
- Release of volatile fission products from ThO2 with a simulated burnup of 4 at (1991) (9)
- Ion-bombardment-induced structural changes in Fe2O3, Cr2O3 and U3O8 (1976) (8)
- Diffusion of 83Rb and 84Rb tracers in waste glasses (1987) (8)
- Radiation damage, its recovery and platinum lattice location in Pb-bombarded MgO (1981) (8)
- Indentation Techniques for Evaluation of Mechanical Properties of Ceramics and Glasses (1991) (8)
- Lattice location of oxygen atoms in UO2 single crystals leached in water (1998) (8)
- Lattice location of fission products in UO2 single crystals (1992) (8)
- Application of ion beam techniques to solid state physics and technology of nuclear materials (1985) (8)
- Fundamental Aspects of Inert Gas Behaviour in Nuclear Fuels: Oxides, Carbides and Nitrides (1991) (8)
- Location of oxygen in leached UO2 single crystals by resonant scattering of He ions (1992) (7)
- Deuteron and helium ion channeling in uranium carbide (1970) (7)
- Fabrication and testing of non-oxide nuclear fuels for fast breeders (1991) (7)
- Interstitial diffusion of emanation in uranium monocarbide single crystals at and below room temperature (1969) (7)
- A thermodynamic properties study of the americium-oxygen system (1995) (7)
- The crystallization of amorphous UO2 (1974) (7)
- Rutherford backscattering for measuring corrosion layers on glasses for long-term storage of radioactive waste (1984) (7)
- Long-term leaching of silicate systems: testing procedure, actinides behaviour and mechanism (1977) (7)
- Surface Diffusion and Surface Energies of Ceramics with application to the behavior of volatile fission products in ceramic nuclear fuels (1989) (7)
- On mass transport in nuclear carbides by evaporation-condensation (1975) (7)
- Observation of a high burnup rim-type structure in an advanced plutonium–uranium carbide fuel (1997) (7)
- Concluding remarks to the workshop on radiation effects in nuclear waste materials (1988) (6)
- Ion beam analyses of ceramics and glasses in nuclear energy (1994) (6)
- Letter to the editorsSurface damage in UO2 due to mechanical polishing and ion bombardment (1983) (6)
- The effect of He-irradiation on the fracture toughness of ThO2 (1983) (6)
- Diffusion of inert gases in silver—II. Recrystallized and single crystalline silver (1975) (6)
- Radiation Enhanced Diffusion in Nuclear Carbides (1985) (5)
- MICROSTRUCTURE OF SWIFT HEAVY ION IRRADIATED MgAI 20 4 SPINEL (2008) (5)
- Fission Gas Behaviour during Power Transients in High Burn-Up LWR Nuclear Fuels Studied by Electron Microscopy (1991) (5)
- LATTICE DISORDER AND METAL SELF-DIFFUSION IN NON-STOICHIOMETRIC UO2 AND (U, Pu)O2 (2020) (5)
- Gas release from pressurized closed pores in nuclear fuels (1988) (5)
- Hertzian indentation of advanced lmfbr fuels with simulated burn-up (1982) (5)
- Ion channeling in spinel single crystals (1996) (5)
- Point Defects and Transport Properties in Carbides and Nitrides (1989) (5)
- DIFFUSION OF Th AND U IN THORIUM DIOXIDE (1976) (5)
- Diffusion of tungsten in uranium carbide single crystals (1975) (5)
- Diffusion of Cesium in Stainless Steel and Possible Implications for Chromium Depletion and Mobility (1983) (5)
- The effect of bombardment temperature on the trapping of xenon in some oxides and halides (1968) (5)
- Radiation damage and simulated fission product effects on the properties of inert matrix materials (2001) (4)
- {alpha}-radiolysis and {alpha}-radiation damage effects on UO{sub 2} dissolution under spent fuel storage conditions (1999) (4)
- Structural transformations in leached uranium dioxide (1996) (4)
- The Fracture Properties of NbC, Nb(C, N), and NbN by Hertzian Indentation (1982) (4)
- High mobility of heavy rare gases in potassium halides at low temperatures (20–100°C) (1969) (4)
- Self-diffusion of Na in GP 98/12 waste glass under α-ray irradiation (1992) (4)
- Radiation Damage in Nuclear Fuel Materials (1992) (3)
- Actinide behavior and radiation damage produced by α-decay in materials to solidify nuclear waste (1984) (3)
- Grazing-incidence X-ray magnetic scattering studies of UO2(0 0 1) surfaces (1996) (3)
- Release of heavy rare gases from Cu and Pt (1976) (3)
- Fracture toughness in nuclear waste glasses and ceramics: environmental and radiation effects. [Ca/sub 2/Nd/sub 8/(SiO/sub 4/)/sub 6/O/sub 2/, Gd/sub 2/Ti/sub 2/O/sub 7/, and CaZrTi/sub 2/O/sub 7/] (1986) (3)
- Leaching Study of the Behaviour of Spent Fuel and SIMFUEL Under Simulated Granitic Repository Conditions (2001) (3)
- Characterization of Waste Glasses Using Vickers Indentation, Short rod Fractometry and Drop Tests (1988) (2)
- Erratum: The fracture surface energy of (U0.8Pu0.2)O2 (1983) (2)
- Plutonium diffusion in advanced fuels (U,Pu)(C,O) and (U,Pu)(C,N) (1983) (2)
- Krypton release from nickel and stainless steel (1975) (2)
- Rare Gas Mobility in Pure and Doped Potassium Bromide (1967) (2)
- Self-diffusion of U and Pu in (U, Pu)C and (U, Pu)N (1979) (2)
- Study of advanced fuels in highly rated He-bonded pins (1975) (2)
- The fracture surface energy of (U0.8Pu0.2)O2 (1983) (2)
- Fission gases in nuclear fuels (1989) (2)
- Ion implantation studies of UO 2 and UN (1992) (2)
- MOBILITY AND PRECIPITATION OF RARE GASES IN SOLIDS DURING ANNEALING FOLLOWING ION BOMBARDMENT. (1970) (2)
- Chemical and Physical Modifications in Waste Glasses Ion Implanted at Different Temperatures (1992) (2)
- Calculations on the In-Pile Behaviour of Fission Gas in Oxide Fuels. An Extended Parametric Study. EUR 4877. (1972) (2)
- Radiation damage in nuclear waste glasses following ion implantation at different temperatures (1990) (2)
- Inert matrix fuels for incineration of plutonium and transmutation of americium (2001) (2)
- PROTON AND ALPHA-PARTICLE CHANNELING AS A TOOL FOR LOCATING FOREIGN ATOMS IN CRYSTALS. (1966) (1)
- 5 Diffusion in nitrides (1999) (1)
- Inert gases as a probe for chemical, physical or structural changes in solids (1991) (1)
- Plutonium Incineration in Lwrs (1999) (1)
- Rare Gas Diffusion in NaCl (1969) (1)
- Calculation of the Fractional Release of Gases from a Sphere After Recoil Bombardments. EUR 3488. (1967) (1)
- Mechanical Stability of a Cm-Doped Celsian Glass-Ceramic (1982) (1)
- Recent studies on the formation of the rim structure and on polygonization in LWR fuel (2002) (1)
- Xenon migration and trapping in ceramics following ion bombardment (1965) (0)
- Correlation between fuel structure and mechanical properties of UO/sub 2/ (1982) (0)
- Enhanced diffusion in Fe1−yO and Fe3−yO4 (1984) (0)
- Diffusion of Krypton in Cesium and Rubidium Iodide; A Comparison of Results Obtained Following Reactor Irradiation and Ion Bombardment (1970) (0)
- Self-Diffusion of Uranium in Uranium Monocarbide-Evaluation of Curved Arrhenius Diagrams. EUR 5078. (1974) (0)
- Characterisation of tin oxide films by complementary techniques. Report of ICG/TC 19 'Physical methods for studying glass surfaces' (1996) (0)
- Radiation effects in fuel materials for fission reactors (1982) (0)
- Microstructure of Swift Heavy Ion Irradiated MgAl(Sub 2)O(Sub 4) Spinel (1998) (0)
- Nuclear methods in studies of ceramic surfaces and interfaces (1991) (0)
- CHARACTERISTICS AND BEHAVIOR OF HIGH-TEMPERATURE NUCLEAR FUELS (1964) (0)
- APPLICATION OF THE ION BOMBARDMENT TECHNIQUE TO STUDY THE BEHAVIOR OF RARE GASES IN UO . (1970) (0)
- Oxygen distribution in fast reactor oxide fuels (1980) (0)
- Diffusion in Nonstoichiometric Oxides (350 Literaturangaben). (1982) (0)
- Self-radiation damage in actinide host phases of nuclear waste forms. [Ca/sub 2/Nd/sub 8/(SiO/sub 4/)/sub 6/O/sub 2/; Gd/sub 2/Ti/sub 2/O/sub 7/; CaZrTi/sub 2/O/sub 7/] (1984) (0)
- The defect structure of uranium carbides (1976) (0)
- DIFFUSION OF Ca-45 IN CaF$sub 2$ (1964) (0)
- Nuclear materials for fission reactors : proceedings of Symposium E on Nuclear Materials for Fission Reactors of the 1991 E-MRS Fall Conference, Strasbourg, France, November 4-7, 1991 (1992) (0)
- THE DIFFUSION OF RADON IN OXYGEN AFTER RECOIL INDICATION (1960) (0)
- DIFFUSION OF Xe-133, Rn-222, AND I-131 IN THORIUM OXIDE (1960) (0)
- Erratum to: Indentation testing of nuclear-waste glasses (1985) (0)
- DIFFUSION IN DOPED UO$sub 2$ (1965) (0)
- A Model for Thermal Conductivity of Irradiated UO2 Fuel (2021) (0)
- DIFFUSION OF Xe-133 IN URANIUM OXIDES WITH DIFFERENT OXYGEN CONTENTS (1959) (0)
- Stopping power of 1 to 9-MeV He$sup ++$ ions in UO$sub 2$, (U,Pu)O$sub 2$, and ThO$sub 2$ (1973) (0)
- CALCULATION OF THE FRACTIONAL RELEASE OF GASES FROM A SLAB AFTER COIL BOMBARDMENT (1964) (0)
- Mass Transport by Self-Diffusion and Evaporation-Condensation in High Temperature Kinetic Processes in UO2.PuO2 Nuclear Fuel (1977) (0)
- Tellurium and Palladium Diffusion in the German Waste Glass Vg 98/12 Measured with the Rbs Method (1991) (0)
- Channelling of MeV Projectiles in Diatomic Ionic Crystals (1971) (0)
- Review of fracture properties of nuclear materials determined by Hertzian indentation (1985) (0)
- DIFFUSION OF RADIOACTIVE RARE GASES IN URANIUM OXIDES AND URANIUM MONOCARBIDE (1959) (0)
- DIFFUSION OF Kr-85 IN ThO$sub 2$ (1961) (0)
- Atomic diffusion in nuclear carbides and oxydes; influence of temperature gradients (1985) (0)
- FISSION GAS BEHAVIOR IN THEORETICALLY DENSE FUEL. (1972) (0)
- Hydrogen profiles at the surface of leached Synroc [Authors' reply to ‘Comments on the paper by Hj. Matzke et al., Nucl. Instrum. Meth. B45 (1990) 194’] (1996) (0)
- Nuclear Waste Management, Materials Aspects of (2001) (0)
- Chapter 14. Nuclear Materials (2008) (0)
- MOBILITY OF TRITIUM IN SILVER AND ALUMINIUM AFTER ION BOMBARDMENT. (1967) (0)
- THE DIFFUSION OF HOMOGENEOUSLY DISTRIBUTED RARE GASES FROM SOLID BODIES (1961) (0)
- Review of uranium self-diffusion in uranium monocarbide (1974) (0)
- Nuclear Techniques in Surface Studies of Ceramics (1989) (0)
- DIFFUSION OF TRITIUM IN QUARTZ AND FUSED SILICA. (1967) (0)
- Effect of composition and radiation on the Hertzian indentation behavior of nuclear waste glasses. [77-MeV alpha particles] (1983) (0)
This paper list is powered by the following services: