Report that reviews the yearly progress made in Reactor Fuel and Materials Development Program at the Engineering Test Reactor (ETR) and Materials testing reactor (MTR).

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.

Report documenting "the chemical and physical properties of the ground water beneath the National Reactor Testing Stations (NRTS), Idaho. The chemical properties described are chiefly the concentration and proportions of the dissolved constituents" (p. 1).

Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).

The purpose of this document is to present criteria for the Titles I and II design of the Fast Flux Loop Facility which is to be a part of the Advanced Test Reactor. This facility is to be used for irradiation of fast reactor assemblies under simulated fast reactor operating conditions.

Report regarding the process development work at the Oak Ridge National Laboratory, including project objectives, design considerations, descriptions of equipment, and estimated costs.

Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.

Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.

Report documenting the MUFT-R program, which is "designed to solve the fast neutron transport problem for general mixtures of elements and obtain sets of average fast neutron diffusion constants for specified portions of the fast energy spectrum" (p. iii). Includes detailed derivations of utilized equations.

Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.

Report documenting results of a study of the cause of failure at the SPERT III reactor facility.

Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS).

Report that describes an engineering drawing microfilm system that was developed for the United States Atomic Energy Commission's Idaho Operations Office and its contractors at the National Reactor Testing Station.