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

From abstract: "A previous study of equipment necessary for clean-up following a nuclear accident indicated a need for a portable television system capable of operating in hazardous environments during recovery operations. A system to accomplish this is described and justified in this study."

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.

Report regarding the Safety Test Engineering Program (STEP), the transient and destructive testing of the aerospace SNAP 10A/2 reactor, and the evaluation of the results of these tests.

Report surveying the "[i]nstrumentation and control practices at the Hanford Plant, the Idaho Chemical Processing Plant, the Oak Ridge national Laboratory, and the Savannah River Plant" (p. iv).

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

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

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

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

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."

Report discussing a hydrofluoric acid dissolution process that allows the processing of zirconium- or Zircaloy-clad zirconium-uranium fuels.

Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).

Gamma-Ray Spectrum diagrams.

Engineering test reactor design and operation.

Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.

From introduction: "This report presents lithologic and geophysical logs and construction data for NRTS research observation wells."

From introduction: "The present report indicates additional preliminary progress in the interpretation of the geology of the area on the basis of preliminary gravity and magnetic surveys and sketches the progress made in operational phases of the study of the hydrology of waste disposal."

From summary: "Reactor fuel material consisting of U3Si particles embedded in an aluminum matrix have been examined with an electron microprobe to determine reaction between fuel particles and matrix. Partial reaction was observed with no observable tendency for the uranium or silicon to diffuse outward into the matrix.

Report discussing the use of TOPIC Sn computer code in the attempt to find a solution to the Boltzmann transport equation.

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."

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

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."