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- Plasma stability analysis employing equilibrium constants of motion
- Status report no. 1 on Clinch River study
- 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
- 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