Search
Search U.S. government technical reports digitized or harvested by TRAIL.
Keyword Search
1702 results returnedSearch results
- Preliminary Design of a Diesel-Powered Vapor-Compression Plant for Evaporation of Seawater
- A generalized multi-dimensional age-dependent branching process
- 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 ...
- Description of printed output from intranuclear cascade calculation
- Indexed bibliography of nuclear desalination literature.
- 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
- 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
- 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
- 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
- Data summaries (Nuclear-structure physics) :tabular and graphical summaries of experimental results reported in recent issues of several journals
- Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968
- Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1968
- Nuclear Safety Program Annual Progress Report: for Period Ending December 31, 1968
- Study of 250-MGD Multistage Flash Distillation Plant with Two-Level Brine Flow
- An Evaluation of Steam-Cooled Fast Breeder Reactors
- 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
- 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
- Studies in applied solid mechanics (nuclear safety) annual progress report
- Statistical thermodynamics of molten salts and concentrated aqueous electrolytes
- 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
- 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.
- A linearly constrained nonlinear programming algorithm
- Measurement and correlation of thermal resistances of UN-metal interfaces