Search
Search U.S. government technical reports digitized or harvested by TRAIL.
Keyword Search
749 results returnedSearch results
- Physics Division Annual Progress Report, January 31, 1964
- Instrumentation and Controls Division Annual Progress Report, September 1, 1963
- Solid State Division Annual Progress Report, May 31, 1964
- Electronuclear Research Division Annual Progress Report, December 31, 1963
- Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964
- Analytical Chemistry Division Annual Progress Report, September 30, 1968
- Gas-Cooled Reactor Project Semiannual Progress Report: September 1963
- Oak Ridge Analytical Chemistry Division Annual Progress Report: 1963
- Gas-Cooled Reactor Project Semiannual Progress Report: March 1964
- An Experimental Investigation of the Spatial Distribution of Dose in an Air-Over-Ground Geometry
- Ichiban: The Dosimetry Program for Nuclear Bomb Survivors of Hiroshima and Nagasaki - A Status Report as of April 1, 1964
- NBC :an IBM 7090 computer program for solving thermoelastic problems
- O5R, a general-purpose Monte Carlo neutron transport code
- Community organization and energy relationships in plankton
- Adsorption of protactinium on unfired Vycor :initial hot-cell experiments
- Summary of the Kilorod Project :a semiremote 10-kg/day demonstration of ²³³UO₂-ThO₂ fuel-element fabrication by the ORNL sol-gel vibratory-compaction method
- Dissolution of high-density UO₂, PuO₂, and UO₂-PuO₂ pellets in inorganic acids
- Evidence of the absence of long-lived isotopes of promethium from fission of uranium, and the purification of promethium for the establishment of a primary spectrographic standard
- Iodine vapor adsorption studies for the NS "Savannah" project
- Preparation of a cesium ( ¹³⁷Cs) borosilicate glass power source
- Photoelastic analysis of EGCR pressure vessel
- Techniques for performing in-reactor stress-rupture experiments
- Efficiency and flow capacity of pulsed columns used for the separation of uranium from thorium by solvent extraction with di-sec-butylphenylphosphonate
- Recovery of ¹³⁷Cs from fission-prodcut wastes and transport by an aluminosillicate ion exchanger
- Vacuum leak testing of radioactive source capsules
- ISOTOPES :a program for neutron product yields and decay calculations using a control data 1604-A computer
- Gamma radiation damage and decontamination evaluation of protective coatings and other materials for hot laboratory and fuel processing facilities
- Nucleon-meson cascade calculations :transverse shielding for a 45-GeV electron accelerator.
- Continuous scanning x-ray attenuation technique for determining fuel inhomogeneities in dispersion core fuel plates
- A generalized one-constraint LaGrange multiplier numerical formulation
- Determination of nuclide concentrations in solutions containing low levels of radioactivity by least-squares resolution of the gamma-ray spectra
- Dynamics of cylindrical electromagnetic universes
- 14-Mev neutron reactions
- Radioisotope production in power reactors
- Room-temperature mechanical properties of EGCR-type AGOT graphite
- Speculations on the interpretation of neutron noise experiments
- Electromagnetic separation and chemical refinement of osmium isotopes
- Concentrations, total stream loads, and mass transport of radionuclides in the Clinch and Tennessee Rivers :supplement No. 1 to Status Report No. 5 on Clinch River Study.
- The space, time, and energy distributions of the proton beam of the Harvard University Synchrocyclotron
- Dissolution of irradiated, stainless-steel-clad ThO₂-UO₂ in fluoride-catalyzed nitric acid solutions :hot-cell studies on pelletized, arc-fused, and sol-gel-derived oxides
- Impact resistance of fueled graphite spheres for pebble-bed reactor applications
- Utilization of a priori information by means of mathematical programming in the statistical interpretation of measured distributions
- Stress-strain measuring system for in-reactor use in high neutron flux
- Analysis of axisymmetrically loaded cylinder-to-sphere attachments
- Zone melting of inorganic fluorides
- Mechanical cladding-fuel interactions during thermal cycling of metal-clad fuel elements
- Determination of thermal-neutron flux distributions in the Bulk Shielding Reactor II by copper wire activation techniques
- A new technique for measuring range of low energy charged particles in conducting solids
- Neutron flux spectra in the experimental facilities of the Oak Ridge Research Reactor
- OR TEP :a FORTRAN thermal-ellipsoid plot program for crystal structure illustrations