None

None

None

None

The purpose of this paper is to describe a few of the suggested advanced concepts for fast breeder reactors and to compare these with the standard approach as to their potential advantage. I have attempted to estimate the economic effect of full technical success with each of the proposed concepts. The proposed concepts include: (1) single sodium system, (2) steam-cooled core concept, (3) direct cycle reactor using potassium as reactor coolant and working fluid, (4) molten plutonium-fuel alloy circulated and cooled by a jet of sodium, (5) settled-bed core, (6) molten salt concept, and (7) paste-fuel system.

This report addresses two inspection systems that have been constructed which use strain gage pressure transducers to pick up changes in static pressure due to change in the hole diameter.

This report is an explanation of the response characteristics, some typical curves of displacements, velocities, etc., and the computer circuit diagram.

The report addresses the analysis of check value including failure and recommendations.

This report summarizes the results of apparent strain tests conducted on both temperature-compensated and uncompensated Microdot weldable strain gages as requested by the Sensor Application Engineering group.

This report describes the procedures and techniques involved in area reduction measurements of fractured tensile specimens.

This report presents the physical properties of tuff in the vicinity of the U12g.01 tunnel at the Nevada Test Site based off of two previous Technical Letters on the tunnel: Technical Letter: Area 12-1, and Technical Letter 12-1, Supplement 1.

A survey of the PITA-18 nonpoisonous spline program was conducted in conjunction with a study to determine the best method of eliminating the variability of axial flux on the fuel performance parameter, q. The results of this survey and the conclusions reached in the rupture coefficient study were found to be inter-dependent such that both are presented in this report. The data from the PITA-18 nonpoisonous spline program, as received, is the output of the NOLA-2 computer program. One quantity of interest is the rupture potential relative to a cosine, commonly referred to as the relative rupture potential. As programmed, the relative rupture potential, which was derived by applying the rupture model to individual fuel elements, might be expected to vary linearly with the rupture rate. The use of the relative rupture potential was studied over the period of July 1962 through December 1963. The results of this study are presented.

The purpose of this report is to provide a brief written description of the facilities existing at Hanford for research and development in the fields of heat transfer and hydraulics.

This report talks about Bibliography, SNAP program reports, memo's, TDR's, and motion pictures, January 1, 1966--September 30, 1967

This report is a further step in the efforts of the AEC NASA Space Nuclear Propulsion Office (SNPO) for the construction of a nuclear rocket propulsion module test complex at the Nuclear Rocket Development Station (NRDS) Jackass Flats, Nevada.

An experimental program was carried out to evaluate the validity of using the cesium-137 content of coating waste as an indirect measure of the uranium and/or plutonium content. A small number of large volume samples and a large number of normal (small volume) samples of Redox and Purex coating waste were used for the investigations. The distribution of cesium, uranium, and plutonium throughout the two-phase system was determined. a comparison of uranium by direct assay and uranium by cesium-137 was obtained for both Redox and Purex samples. A plant test was carried out to determine the extent of cesium migration and the extent to which product materials are transferred from the dissolver to underground storage in coating waste. Sampling for cesium-137 was found to be markedly more consistent than for product materials. In general, the cesium-137 content was found to be a more sensitive measure of the relative product content of coating waste than the uranium content as measured by direct assay. To date al the evidence indicates that the cesium-137 content of coating waste is a valid measure of the product content. However, more ``back-up`` data and a ``routine use`` evaluation are needed before the method can be considered …

BS>A total of nine sections are included in the report. Separate abstracts were prepared for each section. (J.R.D.)

The thermophysical properties of Armco iron such as thermal conductivity, electrical resistivity, and Seebeck coefficient have been extensively investigated and reviewed up to 1000 degrees C. Few investigations of such properties have been made on high purity iron. If such a study is made using the same apparatus to determine the properties of two purity levels of iron, then several significant intercomparisons can be made which add meaning to data on a single material. The systemic errors for a single apparatus are the same, therefore comparison of a property of two similar materials is more significant. A comparison of the property changes with temperature and purity can show the effects of impurities on the mechanisms contributing to a property and allows prediction of the properties of iron as a function of purity. For these reasons a study was initiated on the high-purity iron for comparison to Armco iron.

None

None

None

Tory 11-A, the first experimental reactor in the Pluto nuclear ramjet program, will be tested in late 1960 at the Nevada Test Site of the Atomic Energy Commission. The fundamental objective of Tory II-A is to demonstrate that a high power density, high-temperature, air-cooled reactor can be successfully designed, constructed, and operated. This application places requirements on the reactor control system which are considerably more stringent than those found in previous reactor systems, both from the standpoint of radiation environment and system performance. To fulfill the system requirements a high-performance reactor control system has been designed and built; control actuation hardware has been developed which can withstand the high-radiation environment of Tory LI-A. This actuation system features radiation-tolerant electrohydraulic components: actuators, servo-valves, solenoid valves, feedback transducers, accumulators and associated hydraulic components. To provide high reliability against undesired shutdowns while carrying out high power level transients, the Tory 11-A control philosophy includes a new concept in reactor safety: reliance on a nonlocking, fast-reset safety system during accident situations. The fast-reset system acts so as to hold the programmed power level rather than initiating an irreversible "scram" action. A reactor "scram", if tolerated, could produce thermal shocks which would seriously damage the …

None

This report addresses the cryogenic mock-up loop design study.