Search U.S. government technical reports digitized or harvested by TRAIL.
The high flux isotope reactor accident analysis
Angle calculations for 3- and 4-circle x-ray and neurron diffractometers
Abstracts of papers :water desalination information meeting, March 28-29, 1967
An optimization problem in nuclear reactor economics
Progress in terrestrial and freshwater ecology
Radiation pasteurization of fruits and vegetables :a bibliography
Civil Defense Research Project Annual Progress Report: March 1966 - March 1967
Estimates of maximum subcritical dimensions of single fissile metal units
A bibliography on tracer diffusion in metals :supplement II to parts I, II, and III
Vertical-Tube Evaporator Pilot Plant Report, Volume 1, July 1, 1967
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
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
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
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1961
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
Journal control system at Oak Ridge National Laboratory
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