Call Number (LC) Title Results
E 1.99:ornl/m--4915 Characterization of grinding wheels An annotated Bibliography. Final report. 1
E 1.99:ORNL/M--4922 Benchmarking analysis of three multimedia models RESRAD, MMSOILS, and MEPAS. 1
E 1.99:ornl/m--4924 A comparison of several surface finish measurement methods as applied to ground ceramic and metal surfaces 1
E 1.99:ORNL/M--4941 Use of Ni₃Al-based alloys for walking-beam furnaces 1
E 1.99:ornl/m-4946 An Evaluation of Previously Recorded and Inventoried Archaeological Sites on the Oak Ridge Reservation , Anderson and Roane Counties, Tennessee 1
E 1.99:ornl/m-4950 Active Sites Environmental Monitoring Program FY 1995 Annual Report 1
E 1.99:ORNL/M--4951 Integrated assessment of climate change Characterizing key policy issues. 1
E 1.99: ornl/m--4953 CFCC working group meeting Proceedings. 1
E 1.99: ornl/m--4987 Simulation of a field scale tritium tracer experiment in a fractured, weathered shale using discrete-fracture/matrix-diffusion and equivalent porous medium models 1
E 1.99:ORNL/M--4988 CHEMFORM user̀s guide 1
E 1.99:ornl/m--4992 Carbon-carbon composites for orthopedic prosthesis and implants. CRADA final report 1
E 1.99:ornl/m--4997 Development of lifetime test procedure for powder evacuated panel insulation. CRADA final report 1
E 1.99:ornl/m--4998 Diffractive null compensators for aspheric testing 1
E 1.99:ornl/m--5003 The radioactive materials packaging handbook Design, operations, and maintenance. 1
E 1.99:ORNL/M--5018 Quarterly progress report for the chemical development section of the Chemical Technology Division October--December 1995. 1
E 1.99: ornl/m--5023 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
Effects of low temperature neutron irradiation on deformation behavior of austenitic stainless steels
Effect of oxygen and oxidation on tensile behavior of V-5Cr-5Ti
Loss tangent measurements on unirradiated alumina
Theory and modeling of radiation effects in materials for fusion energy systems
Density decrease in vanadium-base alloys irradiated in the dynamic helium charging experiment
Chemical and mechanical interactions of interstitials with vanadium alloys
Effect of Cr and Ti contents on the recovery, recrystallization, and mechanical properties of vanadium alloys
Tensile properties of V-(4-5)Cr-(4-5)Ti alloys
Summary of recommended correlations for ITER-grade type 316L(N) for the ITER materials properties handbook
Hydrogen uptake in vanadium first wall structures
Effect of heat treatment on precipitation on V-5Cr-5Ti heat BL63
Review of data on irradiation creep of monolithic SiC
Low-chromium reduced-activation ferritic steels for fusion
Microstructural observations of HFIR-irratiated austenitic stainless steels including welds from JP9-16
Evaluation of Nb-base alloys for the divertor structure in fusion reactors
Dynamic finite element modeling of the effects of size on the upper shelf energy of ferritic steels
Fatigue behavior of copper and selected copper alloys for high heat flux applications
Optical properties of silica fibers and layered dielectric mirrors
Unusual response of the binary V-2Si alloy to neutron irradiation in FFTF at 430-600{degrees}C
Development of laser welding techniques for vanadium alloys
Fatigue performance and cyclic softening of F82H, a ferritic martensic steel
Microstructural effects of neutron irradiation on SiC-based fibers
Influence of irradiation spectrum and implanted ions on the amorphization of ceramics
Status of silicon carbide composites for fusion
Irradiation creep in austenitic and ferritic steels irradiated in a tailored neutron spectrum to induce fusion reactor levels of helium
Effect of dynamically charged helium on tensile properties of V-5Ti, V-4Cr-4Ti, and V-3Ti-1Si
Production and fabrication of vanadium alloys for the radiative divertor program of DIII-D
Hydrogen generation arising from the {sup 59}Ni(n,p) reaction and its impact on fission-fusion correlations
Transmutation-induced embrittlement of V-Ti-Ni and V-Ni alloys in HFIR
Physical properites of O- and N-containing V-Cr-Ti alloys
Fracture toughness and fatigue crack growth of oxide dispersion strengthened copper
ISEC-3 Results from the third in-situ electrical conductivity test on polycrystaline alumina.
Microstructural evolution of V-4Cr-4Ti during ion irradiation at 200{degrees}C
Schedule and status of irradiation experiments
Displacement rate dependence of irradiation creep as predicted by the production bias model
Fracture toughness of irradiated candidate materials for ITER first wall/blanket structures Summary report.
Electrical integrity of oxides in a radiation field
Capsule fabrication for in-situ measurement of radiation induced electrical degradation (RIED) of ceramics in HFIR
Improvement of the thermal conductivity of SiC{sub F}/SiC composite
Solubility of hydrogen in V-4Cr-4Ti and lithium
Charpy impact test results for low activation ferritic alloys irradiated to 30 dpa
Status of ITER task T213 collaborative irradiation screening experiment on Cu/SS joints in the Russian Federation SM-2-reactor
Stochastic annealing simulation of cascades in metals
Development of oxide dispersion strengthened ferritic steels for fusion
CaO insulator and Be intermetallic coatings on V-base alloys for liquid-lithium fusion blanket applications
The monotonic and fatigue behavior of CFCCs
Effect of specimen size on the fracture toughness of V-4Cr-4Ti
Neutron dosimetry and damage calculations for the JP-17, 18 and 19 experiments in HFIR
Passive SiC irradiation temperature monitor
ATR-A1 irradiation experiment on vanadium alloys and low activation steels
Tensile and electrical properties of copper alloys irradiated in a fission reactor
Status of DOE/JAERI collaborative program phase II and phase III capsules
Disassembly of irradiated lithium-bonded capsules containing vanadium alloy specimens
Corrosion of V and V-base alloys in high-temperature water
Kinetics of recovery and recystallization of the large heat of V-4Cr-4Ti
Microscopist̀s aide A computer program written to analyze TEM micrographs.
Impact behavior of reduced-activation steels irradiated to 24 dpa
Summary of the IEA workshop on radiation effects in ceramic insulators
Irradiation creep and void swelling of two LMR heat of HT9 at {approx}400{degrees}C and 165 dpa 		62
E 1.99:ORNL/M--5050 CRADA final report for CRADA number C/Y-1203-0211, gelcasting of soft ferrite parts 1
E 1.99:ornl/m--5058 Short rotation woody crop trials for energy production in north central U.S. 1
E 1.99:ornl/m--5065 Design and testing of a continuous metal biosorption system. Final report, March 10, 1994--June 9, 1995 1
E 1.99:ORNL/M--5066 Metallization technology for tenth-micron range integrated circuits. CRADA final report for CRADA number ORNL92-0104 1