Browse TRAIL Inventories

Electronuclear Research Division Annual Progress Report, December 31, 1963

Molten-Salt Reactor Program Semiannual Progress Report, January 31, 1964

Publications on isotopes at Oak Ridge National Laboratory 1946 - 1963 / by Robert H. Lafferty, Jr., P. S. Baker [and] Martha Gerrard.

Research materials information center bulletin.

Groups IV, V, and VI transition metals :selected references on preparation, structure, physical properties, metallography, and transport properties.

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

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

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


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