Browse TRAIL Inventories

Processes for recovery of uranium and thorium from graphite-base fuel elements.

Separation of transplutoniums from lanthanides by tertiary amine extraction

Lid tank shielding facility measurements behind the ML-1 mockup

Interdiffusion of helium and argon in speer moderator no. 1 graphite :(a terminal report on large-pore graphites-experimental phase)

A survey of the hazards involved in processing liquid metal bonded fuels

Miscellaneous experiments relating to the processing of CETR fuel by sulfex-thorex and darex-thorex processes

Development of ring-joint flanges for use in the HRE-2

Determinations of the kinetics and mechanisms of deboronization at 1135⁰C

Barytes concrete for radiation shielding :mix criteria and attenuation characteristics

The ORNL badge dosimeter and its personnel monitoring applications

Zircex and modified zirflex processes for dissolution of 8% U-91% Zr-1% H TRIGA reactor fuel

Experiment on continuous release of fission gas during irradiation :(an interim report)

Atomic and molecular collision cross sections of interest in controlled thermonuclear research

Table of electronic radial functions at the nuclear surface and tangents of phase shifts

Postirradiation examination of 17-4 PH stainless steel control rod drive rack from SM-1 Reactor

A large-scale getter pumping experiment using vapor deposited titanium films

New solutions of the Boltzmann equation for monoenergetic neutron transport in spherical geometry

A small wrist dosimeter for beta and gamma radiation

The cosine-cubed neutron spectrometer

Survey of potential vapor-phase explosions in darex and sulfex processes

Papers published in journals and presented at meetings, reports issued, and theses completed, during 1960 by ORNL staff members.

Health Physics Division Annual Progress Report, July 31, 1961

Chemical Technology Division Annual Progress Report, May 31, 1961

Radiation Safety and Control Training Manual

Gas-Cooled Reactor Project Quarterly Progress Report: December 1960

Gas-Cooled Reactor Project Quarterly Progress Report: March 1961

Gas-Cooled Reactor Project Quarterly Progress Report: September 1961

Gas-Cooled Reactor Project Quarterly Progress Report: June 1961

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Analytical Chemistry Division Annual Progress Report, December 31, 1960

Thermonuclear Division Semiannual Progress Report, January 31, 1961

Technical Concept-Operation Bren

Equipoise 3A

A survey and evaluation of U²³³ fission yield data

Blankets for thermonuclear reactors

Energy removed from primary proton and neutron beams by tissue

Nuclear analyses of the N.S. Savannah reactor with Zircaloy or stainless steel as fuel-element containers

The effect of high alpha radiation on the corrosion of metals exposed to chloride solutions

Extraction of niobium-95 from nitric acid solutions with Tri-n©œ-butyl phosphate

Isoperimetric and other inequalities in the theory of neutron transport.

Preparation of charge materials for ORNL electromagnetic isotope separators

Analysis of UO₂ dissolution in nitric acid solution

Recovery of PuF₆ by fluorination of fused fluoride salts

Radiation stability of aqueous thoria and thoria-urania slurries

Review of zircaloy-2 and zircaloy-4 properties relevant to N.S. Savannah reactor design

Separation of transplutoniums and lanthanides by tertiary amine extraction.

Aging phenomena in columbium-base alloys

The strain-fatigue properties of Inconel.

Strain-fatigue properties of Inconel.

Ion exchange purification of promethium-147 and its separation from americium-241, with diethylenetriaminepentaacetic acid as the eluant


Published Year

Subject

Author

‹‹ previous 1 2 3 4 5 6 7 8 9 ... 14 15 next ››