The stability of fluorothene (polytrifluorochloroethylene, Kel-F) to gamma radiation has been investigated to estimate the probable life expectancy of fluorothene equipment exposed to Purex process solutions. Samples of fluorothene were exposed to total gamma radiation dosages up to 10 degree R. The results of these tests substantiate the findings reported by Sisman and Bopp in their compilation of data on the affects of radiation on plastics.

From statement of objectives: The purposes of the work described in this report are to provide data useful for designing and operating the dissolver solution clarification equipment to be installed in the Redox production plant.

A method of determining enclosure pressure in the event of a reactor rupture is presented and a sample calculation is shown. This method was used in calculating the design pressure of the Dresden Nuclear Power Station enclosure.

This report describes the development and design of a large bakeable valve that is based on a unique seat arrangement and a novel motion seal.

This quarterly progress report details the ongoing research and experiments at the Oak Ridge National Laboratory as part of the Aircraft Nuclear Propulsion Project. The first part of this report discusses reactor theory and design. The second part of this report is not included. The third part of this report discusses materials research. The fourth part of this report includes appendixes

This report discusses the production of large-diameter zirconium crystal bars in a 16 inch diameter, Hastelloy B, de Boer unit in order to increase production efficiency.

From introduction: This report summarizes a study of the composution and physical properties of a number of hydrocarbon diluents together with some generalizations regarding relations between [vapor pressure, density and viscosity] properties.

This report covers an investigation made to develop a gasometric determination that can determine 1.2 x 10-(-5) g. of nitrite with a precision (99% limits) of +/- 8%, and discusses how this procedure works.

From introduction: "At the request of WAPD, a study has been made of the effect of minor compositional variables on the corrosion behavior of uranium-molybdenum alloys in 650 F degassed water."

Report discussing experiments on particle density, plasma compression, electron heating, and electron energy distribution of plasma in a pyrotron. Past experiments that led to this investigation are discussed as well.

This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.

The description of the thick-target neutron yields from the D(t,n)He4 and the D(d,n)He3 reactions is calculated as a function of the energy of the bombarding particles. For 60-kev particles the ratio is 108. I increases to 168 at 100 Kev and to 194 for 120-kev particles. A qualitative discussion of the yields from various deuterium target leads to the conclusion that the greatest yield would come from the target which has the lowest stopping cross section per deuterium atom.

This study was started in May 1949 to find methods of reducing the number of element failures in the salt bath bronze furnaces. Determining the cause of the failure and methods of eliminating them is followed to completion.

Report presenting a correction to an age-diffusion equation used by ANP Physics Group, as well as a test calculation using the corrected equation.

General considerations involving the transportation of irradiated fuel and radioactive wastes are reviewed. It is assumed that many reactors will supply feed to a few large multipurpose chemical plants which ultimately send radioactive waste to a few disposal sites. General economic considerations of irradiated fuel reprocessing, economic aspects of the nuclear economy complex, growth predictions of the nuclear power economy in the U.S., general requirements for the shipment of fuel and waste, regulations applicable to fuel shipment, and permissible radiation levels are discussed.

Abstract: "The niobium-carbon system has been determined by X-ray and metallographic examination of sintered and arc-cast alloys. Two carbides exist: hexagonal Nb2C with a limited range of homogeneity, and cubic NbC with a solubility range from 8.25 to 10.25 weight per cent carbon. Dilute alloys freeze by eutectic reaction at 2230 C. The solubility of carbon in niobium is 0.80 at the eutectic temperature, but this decreases rapidly with temperature. Metallographic evidence indicates a peritectic reaction between melt, Nb2C, and NbC; alloys richer in carbon than NbC freeze by eutectic reaction."

A report about anomalous low temperature thermal conductivity of grapnite samples.

Abstract: "This specification covers the cleaning of Zir caloy-2 components of PWR fuel rods and such tools, gauges, or other devices as may be required in subsequent handling, welding and inspection per Fuel Rod Specification AP-292545, Section II-A-4 and Section II-B-3."

Report discussing the progress made on a study of electric propulsion for space travel during the period from July 1, 1958 to December 31, 1958 at the Lawrence Radiation Laboratory in Livermore, California.

From abstract: "This bibliography consists of reports compiled from the AEC Library Card Catalog. Only the Classified and Unclassified report literature is included. For the published literature the reader is referred to an unpublished paper by V. Carson (UCRL - Livermore Library)" titled "Radioactive Waste Disposal" (April 25, 1957). "All progress reports covering the work have been omitted in order to exclude a large amount of duplicate information which is usually found in more detail in topical reports."

This paper discusses technical bases, operating standards, and instrumentation systems required to achieve the goal of nuclear safety in operation of high-level reactors. Because of the relatively long neutron lifetime in a thermal reactor and the comparatively modest time rates of reactivity change associated with fission poison and temperature effects, the rod system used for compensating reactivity transients and for maintaining flux distribution control may be operated manually. Manual operation of the reactor and the prediction of pile reactivity statue during outages of course involve factors of human error, normal reaction time, and judgment. It is the aim to specify procedures for the operation such that manual control of the reactor may be adequately maintained at all times within the range of reasonably expected calculational errors and human reaction times. The technical considerations used in developing these standards, including the available monitoring indications are discussed first; then the automatic trip devices which should back up the procedures are also mentioned.

The purpose of the test was to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load transients. The only limits exceed were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the the load change. The pressurizer spray was effective in reducing reactor coolant pressure positive surges; however, this resulted in larger negative surges than when the spray valve was closed.

To obtain a better understanding of the mechanism involved in scaling behavior of zirconium, kinetic studies were made of the weight pickup in air after the following pretreatments; (1) exposure to oxygen or nitrogen, (2) exposure to air, oxygen or nitrogen and removal of the resulting surface compounds.

The introduction of aluminum in hot process water has been studied extensively and numerous reports have been issued on the subject. The conclusions reached have been largely empirical and can only be used to state what is happening under the given conditions existing in the corrosion experiments. It is only with difficulty and a great deal of uncertainty that these empirical results can be used to predict what will occur under a different set of conditions. If the fundamental mechanism of aluminum corrosion in water were known, it is possible that more accurate predictions could be made and that steps might be taken to affect the controlling factors and thus reduce the severity of corrosion. To keep the system as simple as possible one would attempt to study the corrosion mechanism by corroding aluminum in pure water. However, this is undesirable because of the extremely low corrosion rate of aluminum in pure water and the large water supply and treatment facility required to supply sufficient high purity water for circulation about the corrosion samples.