Browse TRAIL Inventories

The immersed ultrasonic inspection of metal plate

Resonance absorption of neutrons in nuclear reactors

Tables for the transformation between the laboratory and center-of-mass coordinate systems and for the calculation of the energies of reaction products

Phase diagrams of nuclear reactor materials

Physical characterization of acidic and neutralized synthetic fuel reprocessing waste solutions on evaporation and calcination

Experiments on the release of fission products from molten reactor fuels

Dispersions of uranium carbides in aluminum plate-type research reactor fuel elements

The determination of trace elements in water by neutron activation analysis

Multiaxial creep studies on inconel at 1500⁰F

Development of the excer process v :recovery, purification, and iron reduction of uranium using a sulfate ion exchange system

Thermodynamic estimate of the reaction of hydrogen with oxygen-bearing impurities in Salado salt at elevated temperatures

Initial post neutron measurements in the ORR

Development of silicon-modified 48 Wt % U-Al alloys for aluminum plate-type fuel elements

On the disk to point or infinite plane shielding transformations

A technique for preparing neptunium targets of uniform cross section

The inert-gas-shielded metal-arc welding of titanium

Preparation of high purity neptunium on multi-gram scale

Measurements through a hot cell window using optical tooling

Review of thermal conductivity and heat transfer in uranium dioxide

A thermal problem associated with underground storage of radioactive wastes

Plutonium release incident of November 20, 1959

Development of the Sulfex process for decladding stainless-steel-clad power reactor fuel elements with sulfuric acid

Neutron activation analysis methods for the Group VIII elements

Proceedings of Symposium on Magnetic Field Design in Thermonuclear Research :held at Gatlinburg, Tennessee, December 11 and 12, 1958.

Nucleate-boiling studies with aqueous ThO₂ slurries

Extraction of protactinium with diisobutylcarbinol

Nuclear characteristics of spherical, homogeneous, two-region, molten-fluoride-salt reactors

Physics Division annual progress report for period ending ...

Articles published in technical journals, reports published, papers presented at the Geneva conference, at scientific meetings, and inventions disclosed during 1958 by ORNL staff members.

An IBM-704 code for studying particle orbits in cyclotron fields

Improvement of the high-temperature strength properties of reactor materials after fabrication

Articles published in technical journals, reports published, papers presented at the Geneva conference and at scientific meetings, and inventions disclosed during 1958 by ORNL staff members.

Thermonuclear Project Semiannual Report, January 31, 1959

Metallurgy Division Annual Progress Report, September 1, 1959

Instrumentation and Controls Division Annual Progress Report, July 1, 1958

Instrumentation and Controls Division Annual Progress Report, July 1, 1959

Physics Division Annual Progress Report, March 10, 1959

Molten-Salt Reactor Program Quarterly Progress Report: October 1958

Molten-Salt Reactor Program Quarterly Progress Report: April 1959

Homogeneous Reactor Project Quarterly Progress Report: November 1958-January 1959

Homogeneous Reactor Project Quarterly Progress Report: August-October 1958

Homogeneous Reactor Project Quarterly Progress Report: February-July 1958

Homogeneous Reactor Project Quarterly Progress Report: February-April 1959

Operation of the aircraft reactor experiment

Homogeneous reactor program progress report for the period ...


Published Year

Subject

Author

‹‹ previous 1 2 ... 13 14 15 16 next ››