From abstract: "explain all important features pertaining to a new pulsed irradiation reactor, the Capsule Driver, Core, and to analyze the potential problems and hazards of operating this reactor in the existing Spert IV facility."

From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."

From abstract: "Verify rod mechanism characteristics reported by the United Shoe Machinery Corporation, demonstrate that rod mechanism characteristics were compatible with reactor kinetics and that over-all reactor system behavior was stable, and to recommend system modifications needed for satisfactory performance."

From abstract: "The time-dependent behavior of the Advanced Test Reactor was calculated by the Babcock & Wilcox Company on the Philco 2000 computer, using the Turbo depletion program."

From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."

Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.

From preface: "The purpose of this report is to present an engineering test program for investigating a loss of coolant accident for a pressurized water-cooled and moderated reactor system."

This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).

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.

From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."

Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.

Engineering test reactor design and operation.

Progress report discussing the activities in "a program of studies of nutron-deficient nuclides using the techniques of gamma-ray spectroscopy" (abstract).

From abstract: "The objective of this program is to produce a set of pulse-height spectra representing the response of a standard gamma-ray scintillation spectrometer to radiations emitted in the decay of neutron-deficient nuclides."

Progress report discussing the activities in "a program of studies of nutron-deficient isotopes using the techniques of gamma-ray spectroscopy" (abstract).

Graphs and tables summarizing detailed discharge data of the Big Lost River.

From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."

Report describing investigations to determine the effect of underground disposal of liquid radioactive waste upon the regional groundwater resources.

Interim report for the Army Gas-Cooled Reactor Systems Program, discussing various tests in a project to "develop and evaluate a ceramic-core, pin-type fuel element" (p. 1).

From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."

The fuel element damage which occurred during the SNAPTRAN-3 Destructive Test of a Snap 10A/2 reactor is described. Chemical analysis of the fuel indicated that approximately 15% of the hydrogen was released and that the core flux was higher toward the center both radially and axially. Metallurgical analysis of the fuel determined the presence of the epsilon, delta, and gamma phases in the grain structure and evidence of a possible alpha or beta phase.

From abstract: "This report describes in detail an extensive monitoring grid used to monitor the radiological effects of the destructive excursion and subsequent release of fission products."

From abstract: "Fuel materials proposed for use in the Advanced Test Reactor were evaluated."

Report describing the results of laboratory tests with procedures for calibration of equipment and performance requirements.