TRAIL - Technical Report Archive and Image Library

Molten-Salt Reactor Program Semiannual Progress Report, July 31, 1963

Instrumentation and Controls Division Annual Progress Report: for Period Ending September 1, 1962

Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963

Molten-Salt Reactor Program Semiannual Progress Report: for Period Ending January 31, 1963

A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator

Research materials information center bulletin.

A study of the shield of the Virginia Polytechnic Institute UTR-10 reactor

Regional water supply by nuclear desalination

Effect of particle agglomeration on the penetration of filters utilized with double containment systems

Thermonuclear Project Semiannual Report For Period Ending October 31, 1962

Oak Ridge Metals and Ceramics Division Annual Progress Report: 1963

Army Reactors Program Annual Progress Report: 1962

Gas-Cooled Reactor Project Semiannual Progress Report: March 1963

Nuclear theory index.

Nuclear cross section program at ORN :February 15, 1963 - August 1, 1963

General Correlative Studies - Operation Bren

Neutron Physics Division Annual Progress Report, September 1, 1962

Conversion of simulated high-level radioactive waste solutions to glassy solids in a pot by a rising liquid level method :the RL-Potglass process

Equilibrium distribution of metal-ion complexes

An investigation of the influence of the holdup effect of double containment on reactor hazards

Handbook of shielding requirements and radiation characteristics of isotopic power sources for terrestrial, marine, and space applications

The herpetofauna of the Oak Ridge area

Fabrication development of U₃O₈-aluminum composite fuel plates for the advanced test reactor

Elastic and inelastic scattering of 5- to 13.5-Mev deuterons from Ni⁶⁰ :tabulated differential cross sections

The nucleon transport code, NTC

Pulse-height spectra of gamma rays emitted by the stainless-steel-clad bulk shielding reactor II (BSR-II)

A study of the response contours of the hot-pressed density of thorium oxide pellets

Review of ORNL thermal diffusion program January-December 1963

Diffusion of titanium-44 and vanadium-48 in titanium

The yield of elastically scattered 17 to 21 MeV neutrons from the reaction C¹² (n,n) C¹²

Gas flow calculations for fluidized-bed coating of nuclear fuel particles

Diffusion in body-centered cubic metals zirconium, vanadium, niobium, and tantalum

Characterization of spheroidal UO₂ particles and studies of fabrication variables for core B fuel plates of the Enrico Fermi fast breeder reactor

Measurement and shell model interpretation of the low-lying nuclear energy levels of niobium-92

Effects of hydrogen on the high-temperature flow and fracture characteristics of metals

Laboratory development of processes for fixation of high-level radioactive wastes in glassy solids :wastes containing (1) aluminum nitrate and (2) the nitrates of the constituents of stainless steel

Fabrication of the vertical-orifice teflon capillary of a teflon dropping-mercury electrode

Proposed head-end treatments of PUREX-1WW waste for fission product recovery by ion exchange

Studies of the ion-cyclotron resonance instability

Statistical model calculations of nucleon-nucleon and pion-nucleon collisions :center-of-mass spectra

Program STATEST :an application of the method of statistical estimation to the calculation of neutron flux in anisotropically scattering media by Monte Carlo

Some algorithms for the calculation of the characteristic roots and vectors of a normalizable matrix

Calculation of fission-source thermal-neutron distribution in water by the transfusion method

Prestressing a two-layer pressure vessel by controlled yielding of the inner layer

Purification of di(2-ethylhexyl)-phosphoric acid

Design and construction of eddy-current coolant-channel spacing probes

Compatibility of unsupported pyrolytic-carbon coated uranium dicarbide particles with water vapor

Effect of degree of vacuum on the slow-bend creep behavior of columbium-0.6% zirconium at 1000⁰C

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