| Call Number (LC) | Title | Results |
|---|---|---|
| E 1.99:doe/er-0313/8 | Fusion reactor materials semiannual progress report for the period ending March 31, 1990 | 1 |
| E 1.99:doe/er-0313/10 | Fusion reactor materials semiannual progress report for the period ending March 31, 1991 | 1 |
| E 1.99:doe/er-0313/11 | Fusion Reactor Materials semiannual progress report for period ending September 30, 1991 | 1 |
| E 1.99:doe/er-0313/12 | Fusion Reactor Materials semiannual progress report for the period ending March 31, 1992 | 1 |
| E 1.99:doe/er--0313/14 | Fusion reactor materials semiannual progress report for the period ending March 31, 1993 | 1 |
| E 1.99:doe/er--0313/15 | Fusion reactor materials. Semiannual progress report for period ending September 30, 1993 | 1 |
| E 1.99:doe/er--0313/17 |
Fusion materials semiannual progress report for the period ending September 30, 1994 Dislocation development in V-5CR-5TI and pure vanadium Impact properties of 500-kg heat of V-4Cr-4Ti Hardness recovery of 85% cold-worked V-Ti and V-Cr-Ti alloys upon annealing at 180{degrees}C to 1200{degrees}C Effect of oxidation on tensile behavior of V-5Cr-5Ti alloy Ductile-brittle transition behavior of V-4Cr-4Ti irradiated in the dynamic helium charging experiment Fabrication and performance testing of CaO insulator coatings on V-5%Cr-5%Ti in liquid lithium Fabrication of aluminum nitride and its stability in liquid alkali metals Chemical compatibility of structural materials in alkali metals Status of U.S./Japan collaborative program phase II HFIR target and RB{sup *} capsules Vanadium alloy irradiation experiment X530 in EBR-II{sup *} Vanadium irradiation at ATR - neutronics aspects Neutron flux spectra and radiation damage parameters for the Russian Bor-60 and SM-2 reactors Neutron dosimetry, damage calculations, and helium measurements for the HFIR-MFE-60J-1 and MFE-330J-1 spectral tailoring experiments Correlation between shear punch and tensile data for neutron-irradiated aluminum alloys Comparison of defect cluster accumulation and pattern formation in irradiated copper and nickel Effect of internal hydrogen on the mixed-mode I/III fracture toughness of a ferritic/martensitic stainless steel Dependence of mode I and mixed mode I/III fracture toughness on temperature for a ferritic/martensitic stainless steel Embrittlement of Cr-Mo steels after low fluence irradiation in HFIR Initial tensile test results from J316 stainless steel irradiated in the HFIR spectrally tailored experiment Chemical and mechanical interactions of interstitials in V-5%Cr-5%Ti Fatigue behavior of unirradiated V-5Cr-5Ti Welding development for V-Cr-Ti alloys Effect of heat treatment on microstructure and fracture toughness of a V-5Cr-5Ti alloy Fabrication of 500-kg heat of V-4Cr-4Ti Effect of fission neutron irradiation on the tensile and electrical properties of copper and copper alloys Fatigue crack growth rate (FCGR) behavior of nicalon/SiC composites Advanced SiC composites for fusion applications Thermal conductivity degradation of graphites irradiated at low temperature Apparent activation energy of subcritical crack growth of SiC/SiC composites at elevated temperatures Effects of neutron irradiation on dimensional stability and on mechanical properties of SiC/SiC composites Effect of irradiation spectrum on the microstructural evolution in ceramic insulators Data acquisition system used in radiation induced electrical degradation experiments Cation disorder in high-dose, neutron-irradiated spinel Elastic stability of high dose neutron irradiated spinel Optical absorption and luminescence in neutron-irradiated, silica-based fibers Effect of dynamically charged helium on tensile properties of V-4Cr-4Ti Radiation-induced electrical degradation experiments in the Japan materials testing reactor Incubation time for sub-critical crack propagation in SiC-SiC composites Void structure and density change of vanadium-base alloys irradiated in the dynamic helium charging experiment An investigation of the desorption of hydrogen from lithium oxide using temperature programmed desorption and diffuse reflectance infrared spectroscopy Preliminary report on the irradiation conditions of the HFIR JP-23 experiment |
42 |
| E 1.99:doe/er--0313/18 | Fusion materials semiannual progress report for the period ending March 31, 1995 | 1 |
| E 1.99:doe/er--0313/19 |
Fusion materials semiannual progress report for the period ending December 31, 1995 Neutron dosimetry and damage calculation for the JP-10, 11, 13, and 16 experiments in HFIR Investigation of the feasibility of in-situ dielectric property measurements on neutron-irradiated ceramic insulators Impact behavior of reduced-activation steels irradiated to 24 dpa Charpy impact test results for low activation ferritic alloys irradiated to 30 dpa Irradiation creep and void swelling of two LMR heat of HT9 at {approx}400{degrees}C and 165 dpa Low-chromium reduced-activation ferritic steels for fusion Development of oxide dispersion strengthened ferritic steels for fusion Dynamic finite element modeling of the effects of size on the upper shelf energy of ferritic steels Status of ITER task T213 collaborative irradiation screening experiment on Cu/SS joints in the Russian Federation SM-2-reactor Fracture toughness and fatigue crack growth of oxide dispersion strengthened copper Fracture toughness of irradiated candidate materials for ITER first wall/blanket structures Summary report. Microstructural observations of HFIR-irratiated austenitic stainless steels including welds from JP9-16 Irradiation creep in austenitic and ferritic steels irradiated in a tailored neutron spectrum to induce fusion reactor levels of helium Influence of irradiation spectrum and implanted ions on the amorphization of ceramics Electrical integrity of oxides in a radiation field Loss tangent measurements on unirradiated alumina Capsule fabrication for in-situ measurement of radiation induced electrical degradation (RIED) of ceramics in HFIR ISEC-3 Results from the third in-situ electrical conductivity test on polycrystaline alumina. Summary of the IEA workshop on radiation effects in ceramic insulators Optical properties of silica fibers and layered dielectric mirrors Theory and modeling of radiation effects in materials for fusion energy systems Displacement rate dependence of irradiation creep as predicted by the production bias model Stochastic annealing simulation of cascades in metals Hydrogen generation arising from the {sup 59}Ni(n,p) reaction and its impact on fission-fusion correlations Summary of recommended correlations for ITER-grade type 316L(N) for the ITER materials properties handbook Schedule and status of irradiation experiments Status of DOE/JAERI collaborative program phase II and phase III capsules ATR-A1 irradiation experiment on vanadium alloys and low activation steels Disassembly of irradiated lithium-bonded capsules containing vanadium alloy specimens Microscopist̀s aide A computer program written to analyze TEM micrographs. Passive SiC irradiation temperature monitor Neutron dosimetry and damage calculations for the JP-17, 18 and 19 experiments in HFIR Corrosion of V and V-base alloys in high-temperature water Tensile and electrical properties of copper alloys irradiated in a fission reactor Kinetics of recovery and recystallization of the large heat of V-4Cr-4Ti Development of laser welding techniques for vanadium alloys Production and fabrication of vanadium alloys for the radiative divertor program of DIII-D Physical properites of O- and N-containing V-Cr-Ti alloys Tensile properties of V-(4-5)Cr-(4-5)Ti alloys Effect of heat treatment on precipitation on V-5Cr-5Ti heat BL63 Effect of Cr and Ti contents on the recovery, recrystallization, and mechanical properties of vanadium alloys Effect of specimen size on the fracture toughness of V-4Cr-4Ti Chemical and mechanical interactions of interstitials with vanadium alloys Solubility of hydrogen in V-4Cr-4Ti and lithium Hydrogen uptake in vanadium first wall structures CaO insulator and Be intermetallic coatings on V-base alloys for liquid-lithium fusion blanket applications Effect of dynamically charged helium on tensile properties of V-5Ti, V-4Cr-4Ti, and V-3Ti-1Si Density decrease in vanadium-base alloys irradiated in the dynamic helium charging experiment Microstructural evolution of V-4Cr-4Ti during ion irradiation at 200{degrees}C Unusual response of the binary V-2Si alloy to neutron irradiation in FFTF at 430-600{degrees}C Transmutation-induced embrittlement of V-Ti-Ni and V-Ni alloys in HFIR Status of silicon carbide composites for fusion Review of data on irradiation creep of monolithic SiC Microstructural effects of neutron irradiation on SiC-based fibers Improvement of the thermal conductivity of SiC{sub F}/SiC composite The monotonic and fatigue behavior of CFCCs Fatigue performance and cyclic softening of F82H, a ferritic martensic steel Fatigue behavior of copper and selected copper alloys for high heat flux applications Evaluation of Nb-base alloys for the divertor structure in fusion reactors Effect of oxygen and oxidation on tensile behavior of V-5Cr-5Ti Effects of low temperature neutron irradiation on deformation behavior of austenitic stainless steels |
62 |
| E 1.99:doe/er--0313/20 |
Charpy impact test results of four low activation ferritic alloys irradiated at 370{degrees}C to 15 DPA Tensile properties of V-(4-15)Cr-5Ti alloys irradiated at 400{degrees}C in the HFIR Fusion materials semiannual progress report for the period ending June 30, 1996 Production and fabrication of vanadium alloys for the radiative divertor program of DIII-D - Annual report input for 1996 Fracture toughness testing of V-4Cr-4Ti at 25{degrees}C and -196{degrees}C Effects of strain rate, test temperature and test environment on tensile properties of vandium alloys Evaluation of flow properties in the weldments of vanadium alloys using a novel indentation technique Effects of irradiation at low temperature on V-4Cr-4Ti Grain boundary migration induced segregation in V-Cr-Ti alloys Helium effects on irradiation dmage in V alloys Revised activation estimates for silicon carbide Time-dependent bridging and life prediction of SiC/SiC in a hypothetical fusion environment The cyclic fatigue behavior of a Nicalon/SiC composite Neutron irradiation effects on high Nicalon silicon carbide fibers Specimen size effect considerations for irradiation studies of SiC/SiC Technique for measuring irradiation creep in polycrystalline SiC fibers Progress in the development of a SiC{sub f}/SiC creep test Tensile and charpy impact properties of irradiated reduced-activation ferritic steels Fractographic examination of reduced activation ferritic/martensitic steel charpy specimens irradiated to 30 dpa at 370{degrees}C Low-chromium reduced-activation chromium-tungsten steels Heat-to-heat variability of irradiation creep and swelling of HT9 irradiated to high neutron fluence at 400-600{degrees}C Mechanical properties and microstructure of F-82H welded joints using CO{sub 2} laser beam The consequences of helium production on microstructural development in isotopically tailored ferritic alloys Tensile and electrical properties of unirradiated and irradiated Hycon 3HP{trademark} CuNiBe Fracture toughness of oxide-dispersion strengthened copper Effects of bonding bakeout thermal cycles on pre- and post irradiation microstructures, physical, and mechanical properties of copper alloys Influence of nickel and beryllium content on swelling behavior of copper irradiated with fast neutrons Temperature dependence of the deformation behavior of 316 stainless steel after low temperature neutron irradiation Tensile properties of a titanium modified austenitic stainless steel and the weld joints after neutron irradiation Irradiation creep and swelling of various austenitic alloys irradiated in PFR and FFTF Radiation-induced instability of MnS precipitates and its possible consequences on IASCC of austenitic stainless steels Tensile behavior of irradiated manganese-stabilized stainless steel In-situ measurement of the electrical conductivity of aluminum oxide in HFIR Summary of the irradiation history of the TRIST-ER1 capsule Summary of round robin measurements of radiation induced conductivity in Wesgo AL995 alumina Optical absorption of neutron-irradiated silica fibers An integrated approach to assessing the fracture safe margins of fusion reactor structures Defect interactions within a group of subcascades Neutron dosimetry and damage calculations for the HFIR-JP-23 irradiations A revaluation of helium/dpa ratios for fast reactor and thermal reactor data in fission-fusion correlations Schedule and status of irradiation experiments A master curve-mechanism based approach to modeling the effects of constraint, loading rate and irradiation on the toughness-temperature behavior of a V-4Cr-4Ti alloy Effect of time and temperature on grain size of V and V-Cr-Ti alloys Development of laser welding techniques for vanadium alloys Impact properties and hardening behavior of laser and electron-beam welds of V-4Cr-4Ti Microstructural characteristics and mechanism of toughness improvement of laser and electron-beam welds of V-4Cr-4Ti following postwelding heat-treatment Properties of V-(8-9)Cr-(5-6)Ti alloys irradiated in the dynamic helium charging experiment Study of in-reactor creep of vanadium alloy in the HFIR RB-12J experiment Oxidation kinetics and microstructure of V-(4-5) Wt.%Cr-(4-5) Wt.%Ti alloys exposed to air at 300-650{degrees}C CaO insulator coatings on a vanadium-base alloy in liquid 2 at.% calcium-lithium Feasibility of conducting a dynamic helium charging experiment for vanadium alloys in the advanced test reactor Status of ATR-A1 irradiation experiment on vanadium alloys and low-activation steels Preliminary results of the round-robin testing of F82H |
53 |
| E 1.99:doe/er--0313/21 |
Measurement of hydrogen solubility and desorption rate in V-4Cr-4Ti and liquid lithium-calcium alloys Fusion materials semiannual progress report for the period ending December 31, 1996 Tensile properties of V-Cr-Ti alloys after exposure in helium and low-partial-pressure oxygen environments Neutron dosimetry and damage calculations for the EBRII COBRA-1A irradiations Production and fabrication of vanadium alloys for the radiative divertor program of DIII-D Performance of V-4Cr-4Ti material exposed to DIII-D tokamak environment Electrical resistivity of V-Cr-Ti alloys Mode I and mixed I/III crack initiation and propagation behavior of V-4Cr-4Ti alloy at 25{degrees}C An evaluation of the susceptibility of V-4Cr-4Ti to stress corrosion cracking in room temperature DIII-D water Tensile properties of V-5Cr-5Ti alloy after exposure in air environment Evaluating electrically insulating films deposited on V-4% Cr-4% Ti by reactive CVD Recent progress on gas tungsten arc welding of vanadium alloys Studies on the effects of helium on the microstructural evolution of V-3.8Cr-3.9Ti Effect on fast neutron irradiation to 4 dpa at 400{degrees}C on the properties of V-(4-5)Cr-(4-5)Ti alloys Microstructural examination of irradiated vanadium alloys Creep behavior for advanced polycrystalline SiC fibers Thermogravimetric and microscopic analysis of SiC/SiC materials with advanced interfaces Threshold irradiation dose for amorphization of silicon carbide Stored energy in irradiated silicon carbide Effects of neutron irradiation on the strength of continuous fiber reinforced SiC/SiC composites The monitoring and fatigue behavior of CFCCs at ambient temperature and 1000{degrees}C Development oxide dispersion strengthened ferritic steels for fusion Fracture toughness of the IEA heat of F82H ferritic/martensitic stainless steel as a function of loading mode Summary of the IEA workshop/working group meeting on ferritic/martensitic steels for fusion Further Charpy impact test results of low activation ferritic alloys, irradiated at 430{degrees}C to 67 dpa The effect of fusion-relevant helium levels on the mechanical properties of isotopically tailored ferritic alloys Irradiation creep of various ferritic alloys irradiated at {approximately}400{degrees}C in the PFR and FFTF reactors Effect of test temperature and strain rate on the tensile properties of high-strength, high-conductivity copper alloys Fracture toughness of copper-base alloys for ITER applications A preliminary report. Recent results on the neutron irradiation of ITER candidate copper alloys irradiated in DR-3 at 250{degrees}C to 0.3 dpa Irradiation creep of dispersion strengthened copper alloy Extreme embrittlement of austenitic stainless steel irradiated to 75-81 dpa at 335-360{degrees}C The independence of irradiation creep in austenitic alloys of displacement rate and helium to dpa ratio The compositional dependence of irradiation creep of austenitic alloys irradiated in PFR at 420{degrees}C Irradiation creep and stress-enhanced swelling of Fe-16Cr-15Ni-Nb austenitic stainless steel in BN-350 Atomic scale modeling of defect production and microstructure evolution in irradiated metals Stochastic annealing simulations of defect interactions among subcascades The effects of self-interstitial clusters on cascade defect evolution beyond the primary damage state Neutron dosimetry and damage calculations for the HFIR-JP-23 irradiations The dependence of helium generation rate on nickel content of Fe-Cr-Ni alloys irradiated at high dpa levels in fast reactors Impurity content of reduced-activation ferritic steels and a vanadium alloy Status of DOE/JAERI collaborative program phase II and phase III capsules Status of ATR-A1 irradiation experiment on vanadium alloys and low-activation steels Progress report on the design of a varying temperature irradiation experiment for operation in HFIR Disassembly of the fusion-1 capsule after irradiation in the BOR-60 reactor Schedule and status of irradiation experiments High thermal conductivity SiC/SiC composites for fusion applications Dynamic finite element analysis of third size charpy specimens of V-4Cr-4Ti Assessment of the radiation-induced loss of ductility in V-Cr-Ti alloys |
49 |
| E 1.99:doe/er--0313/22 |
Fusion materials semiannual progress report for period ending June 30, 1997 Neutronics analysis of the DHCE experiment in ATR-ITV Heat treatment effects on tensile properties of V-(4-5) wt.% Cr-(4-5) wt.% Ti alloys Chemistry related to the procurement of vanadium alloys Production and fabrication of vanadium alloys for the radiative divertor program of DIII-D Revised ANL-reported tensile data for V-Ti and V-Cr-Ti alloys Tensile properties of vanadium alloys irradiated at 390{degrees}C in EBR-II Effect of helium on tensile properties of vanadium alloys Tensile properties of vanadium alloys irradiated at 200{degrees}C in the HFIR Tensile properties of vanadium alloys irradiated at <430{degrees}C Microstructural examination of V-(4-5%) Cr-(4-5%)Ti irradiated in X530 Tensile properties of aluminized V-5Cr-5Ti alloy after exposure in air environment Study of irradiation creep of vanadium alloys Recent progress on gas tungsten arc welding of vanadium alloys Investigation of reactivity between SiC and Nb-1Zr in planned irradiation creep experiments Analysis of neutron irradiation effects on thermal conductivity of SiC-based composites and monolithic ceramics Creep behavior for advanced polycrystalline SiC fibers Design of a creep experiment for SiC/SiC composites in HFIR Heat treatment effects on impact toughness of 9Cr-1MoVNb and 12Cr-1MoVW steels irradiated to 100 dpa Neutron irradiation effects on the ductile-brittle transition of ferritic/martensitic steels Effect of heat treatments on the tensile and electrical properties of high-strength, high-conductivity copper alloys Investigation of the influence of grain boundary chemistry, test temperatures, and strain rate on the fracture behavior of ITER copper alloys Microstructural evolution of austenitic stainless steels irradiated to 17 dpa in spectrally tailored experiment of the ORR and HFIR at 400{degrees}C The development of a tensile-shear punch correlation for yield properties of model austenitic alloys Analysis of in-situ electrical conductivity data from the HFIR TRIST-ER1 experiment Irradiation spectrum and ionization-induced diffusion effects in ceramics Defect production in ceramics Effects of in-cascade defect clustering on near-term defect evolution Influence of subcascade formation on displacement damage at high PKA energies Analysis of the DHCE experiment in the position A10 of the ATR reactor Progress report on the varying temperature experiment The Monbusho/US shielded HFIR irradiation experiment HFIR-MFE-RB-11J and 12J (P3-3) Neutron irradiation of V-Cr-Ti alloys in the BOR-60 fast reactor Description of the fusion-1 experiment. Design considerations of the irradiation test vehicle for the advanced test reactor Thermochemical instability effects in SiC-based fibers and SiC{sub f}/SiC composites Microstructural characterization of 5-9% chromium reduced-activation steels Summary of the 9th IEA workshop on radiation effects in ceramic insulators Schedule and status of irradiation experiments Oxidation and microstrucure of V-Cr-Ti alloys exposed to oxygen-containing environments |
39 |
| E 1.99:doe/er--0313/23 |
Grain boundary chemistry and heat treatment effects on the ductile-to-brittle transition behavior of vanadium alloys Fusion materials semiannual progress report for the period ending December 31, 1997 Revised ANL-reported tensile data for unirradiated and irradiated (FFTF, HFIR) V-Ti and V-Cr-Ti alloys Impact properties of vanadium-base alloys irradiated at < 430 C Tensile and impact properties of vanadium-base alloys irradiated at low temperatures in the ATR-A1 experiment Strain rate dependence of the tensile properties of V-(4--5%)Cr-(4--5%)Ti irradiated in EBR-II and HFBR Summary of the investigation of low temperature, low dose radiation effects on the V-4Cr-4Ti alloy Thermophysical and mechanical properties of V-(4-5)%Cr-(4-5)%Ti alloys Effect of thickness and loading mode on the fracture properties of V-4Cr-4Ti at room temperature Temperature dependence of the radiation damage microstructure in V-4Cr-4Ti neutron irradiated to low dose Microstructure of V-4Cr-4Ti alloy after low-temperature irradiation by ions and neutrons Tensile properties of V-Cr-Ti alloys after exposure in hydrogen-containing environments Tensile properties of V-Cr-Ti alloys after exposure in oxygen-containing environments Laser-welded V-Cr-Ti alloys Microstructural and mechanical properties. Performance of V-4Cr-4Ti material exposed to the DIII-D tokamak environment Irradiation creep of vanadium-base alloys Procurement of V-Cr-Ti alloys to study minor variations on V-4Cr-4Ti Methods of radiation effects evaluation of SiC/SiC composite and SiC fibers Fiber creep rate and high-temperature properties of SiC/SiC composites High thermal conductivity SiC/SiC composites for fusion applications -- 2 Minimum bar size for flexure testing of irradiated SiC/SiC composite A reassessment of the effects of helium on Charpy impact properties of ferritic/martensitic steels Development of oxide dispersion strengthened ferritic steels for fusion Microstructural evolution of HFIR-irradiated low activation F82H and F82H-{sup 10}B steels Effect of heat treatment and irradiation temperature on impact behavior of irradiated reduced-activation ferritic steels Irradiation creep of various ferritic alloys irradiated {approximately}400 C in the PFR and FFTF reactors Temperature and strain rate effects in high strength high conductivity copper alloys tested in air The effect of bonding and bakeout thermal cycles on the properties of copper alloys irradiated at 100 C Effect of initial oxygen content on the void swelling behavior of fast neutron irradiated copper The dependence of irradiation creep in austenitic alloys on displacement rate and helium to dpa ratio Extreme embrittlement of austenitic stainless steel irradiated to 75--81 dpa at 335--360 C Shear punch testing of {sup 59}Ni isotopically-doped model austenitic alloys after irradiation in FFTF at different He/dpa ratios Damage structure of austenitic stainless steel 316LN irradiated at low temperature in HFIR Postirradiation examination of beryllium pebbles Neutron irradiation of beryllium pebbles Thermal ramp tritium release in COBRA-1A2 C03 beryllium pebbles Helium analyses of 1-mm beryllium microspheres from COBRA-1A2 Tritium analyses of COBRA-1A2 beryllium pebbles Fundamental radiation effects parameters in metals and ceramics Validation of the shear punch-tensile correlation technique using irradiated materials Subcascade formation in displacement cascade simulations Implications for fusion reactor materials. Stochastic annealing simulation of copper under neutron irradiation Contribution to irradiation creep arising from gas-driven bubbles Neutron dosimetry and damage calculations for the HFIR-JP-9, -12, and -15 irradiations Neutron dosimetry and damage calculations for the HFIR-JP-20 irradiation Neutron dosimetry and radiation damage calculations for HFBR Production of {sup 4}He and tritium from Be in the COBRA-1A2 irradiation Production of {sup 4}He, {sup 3}He, and tritium from Be irradiated in FFTF-MOTA-2B Calculation and measurement of helium generation and solid transmutations in Cu-Zn-Ni alloys Neutron dosimetry and damage calculations for the HFIR-MFE-200J-1 irradiation Neutronic aspects of a DHCE experiment Description and status of the U.S./JAERI HFIR-MFE-RB-10J irradiation capsule Summary of the U.S. specimen matrix for the HFIR 13J varying temperature irradiation capsule Schedule and status of irradiation experiments Radiation response of SiC-based fibers Microstructural examination of irradiated V-(4-5%)Cr-(4-5%)Ti Research and development on vanadium alloys for fusion applications Radiation hardening and deformation behavior of irradiated ferritic-martensitic steels Stepped-anneal helium release in 1-mm beryllium pebbles from COBRA-1A2 |
59 |
| E 1.99:doe/er--0313/24 |
Tensile properties of V-Cr-Ti alloys after exposure in hydrogen-containing environments Fusion materials semiannual progress report for the period ending June 30, 1998 Tensile and impact properties of General Atomics 832864 heat of V-4Cr-4Ti alloy High temperature tensile properties of V-4Cr-4Ti Tensile properties of vanadium-base alloys irradiated in the Fusion-1 low-temperature experiment in the BOR-60 reactor Room-temperature fracture in V-(4-5)Cr-(4-5)Ti tensile specimens irradiated in Fusion-1 BOR-60 experiment Effects of irradiation to 4 dpa at 390 C on the fracture toughness of vanadium alloys Effect of irradiation temperature and strain rate on the mechanical properties of V-4Cr-4Ti irradiated to low doses in fission reactors Microstructural examination of V-(3-6%)Cr-(3-5%)Ti irradiated in the ATR-A1 experiment Reactions of hydrogen with V-Cr-Ti alloys Oxidation behavior of V-Cr-Ti alloys in low-partial-pressure oxygen environments Microstructural characterization of external and internal oxide products on V-4Cr-4Ti Development of electrically insulating CaO coatings Laser-welded V-Cr-Ti alloys Microstructure and mechanical properties. Thermophysical and mechanical properties of SiC/SiC composites A review of joining techniques for SiC{sub f}/SiC composites for first wall applications The HFIR 14J irradiation SiC/SiC composite and SiC fiber collaboration Neutron irradiation induced amorphization of silicon carbide Thermophysical and mechanical properties of Fe-(8-9)%Cr reduced activation steels Analysis of stress-induced Burgers vector anisotropy in pressurized tube specimens of irradiated ferritic-martensitic steel JLF-1. Mechanical properties of irradiated 9Cr-2WVTa steel Microstructural analysis of ferritic-martensitic steels irradiated at low temperature in HFIR Progress report on the influence of test temperature and grain boundary chemistry on the fracture behavior of ITER copper alloys Comparison of properties and microstructures of Trefimetaux and Hycon 3HP{trademark} after neutron irradiation Tensile and electrical properties of high-strength high-conductivity copper alloys Round robin comparison of tensile results on GlidCop Al25 Progress report on the behavior and modeling of copper alloy to stainless steel joints for ITER first wall applications Low-temperature low-dose neutron irradiation effects on Brush Wellman S65-C and Kawechi Berylco P0 beryllium Neutron dosimetry and damage calculations for the ATR-A1 irradiation Analysis and recommendations for DPA calculations in SiC Impact of structural design criteria on first wall surface heat flux limit Elastic-plastic analysis of the SS-3 tensile specimen Status of lithium-filled specimen subcapsules for the HFIR-MFE-RB10J experiment Specimen loading list for the varying temperature experiment Status of the irradiation test vehicle for testing fusion materials in the Advanced Test Reactor Irradiation-induced precipitation and mechanical properties of vanadium alloys at <430 C Schedule and status of irradiation experiments |
37 |
| E 1.99: doe/er-0313/25 | Fusion Materials Semiannual Progress Report for Period Ending December 31, 1998 | 1 |
| E 1.99:DOE/ER-0313/26 | Fusion Materials Semiannual Progress Report for the Period Ending June 30, 1999 | 1 |
| E 1.99:doe/er-0313/27 | Fusion materials semiannual progress report for period ending December 31, 1999 | 1 |
| E 1.99:doe/er--0313/100 | Fusion materials Technical evaluation of the technology of vandium alloys for use as blanket structural materials in fusion power systems. | 1 |
| E 1.99:doe/er-0316 | Master index for the carbon dioxide research state-of-the-art report series | 1 |
| E 1.99:doe/er-0326 | Coal Gasification Direct Applications and Syntheses of Chemicals and Fuels. | 1 |
