Browse TRAIL Inventories

Preliminary Design of a Diesel-Powered Vapor-Compression Plant for Evaporation of Seawater

Cumulative indexes to the analytical chemistry division annual progress reports 1964-1967

The design and evaluation of a delayed-neutron leached-hull monitor

O5S :a Monte Carlo code for calculating pulse height distributions due to monoenergetic neutrons incident on organic scintillators

Pion-nucleon differential cross sections in the 0 to 700-MeV energy region in terms of the coulomb scattering amplitude coulomb phase shifts, and nuclear phase shifts up to ©� = 4

Behavior of oxide aerosols of uranium and stainless steel in humid atmospheres

FABC0ST 9 :a computer code for estimating fabrication costs for rod-bundle fuel elements

Steelmaking in an industrial complex

Thermonuclear Division annual progress report for period ending ...

A generalized multi-dimensional age-dependent branching process

Description of printed output from intranuclear cascade calculation

Data summaries (Nuclear-structure physics) :tabular and graphical summaries of experimental results reported in recent issues of selected journals

Special sources of information on isotopes

Nuclear Energy Centers : Industrial and Agro-Industrial Complexes

Indexed bibliography of nuclear desalination literature.

Chemical Technology Division Annual Progress Report, May 31, 1968

Potential agricultural productionfrom nuclear-powered agro-industrial complexes designed for the upper Indo-Gangetic Plain.

Oak Ridge Analytical Chemistry Division Annual Progress Report: 1961

Conceptual Design Study of a 250-Million Gallons Per Day Combined Vertical Tube-Flash Evaporator Desalination Plant

Emergency core-cooling systems for light-water-cooled power reactors

Management of radioactive wastes at nuclear power stations

The Unclad-Metal Breeder Reactor (UMBR) for desalting or power

Generalized capital and operating costs for power-intensive and allied industries

Temperature profiles within cylinders containing internal heat sources and materials of temperature-dependent thermal conductivities :description of fast computer programs as applied to solidified radioactive wastes

Journal control system at Oak Ridge National Laboratory

Strontium-90 data sheets

Maximum temperature rise in cylinders containing intermediate-level and high-level solidified radioactive wastes

Data summaries (Nuclear-structure physics) :tabular and graphical summaries of experimental results reported in recent issues of several journals

Nuclear Safety Program Annual Progress Report: for Period Ending December 31, 1968

Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968

Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1968

An Evaluation of Steam-Cooled Fast Breeder Reactors

Study of 250-MGD Multistage Flash Distillation Plant with Two-Level Brine Flow

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1969

Health Physics Division Annual Progress Report, July 31, 1969

Instrumentation and Controls Division Annual Progress Report, September 1, 1968

Studies in applied solid mechanics (nuclear safety) annual progress report

Statistical thermodynamics of molten salts and concentrated aqueous electrolytes

An investigation of the effect of certain minor elements on the elevated temperature ductility of incoloy 800

The MORSE code :a multigroup neutron and gamma-ray Monte Carlo transport code

Synthesis, characterization, and fabrication of UN

Analytical Chemistry Division Annual Progress Report, May 20, 1970

Siting of Fuel Reprocessing Plants and Waste Management Facilities

VTE Pilot Plant Annual Report for the Period Ending July 1, 1968

Feasibility of retrieving utility system capital and maintenance costs from annual reports

Data obtained on several possible locales for the agro-industrial complex

Project salt vault :a demonstration of the disposal of high-activity solidified wastes in underground salt mines

Effect of oxygen, heat treatment, and test temperature on the compatibility of several advanced refractory alloys with lithium

Completion report :evaluation of the use of permselective membranes in the nuclear industry for removing radioactive xenon and krypton from various off-gas streams

SPECTRAN :a computer system to analyze high resolution spectrum.


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