Abstract. The region where exact thermodynamic description of the state of matter at high pressure and high temperature is possible is located. In the remaining region various approximate theories and empirical relations are discussed. These considerations are applied to hydrogen to locate the density and pressure at which the diatomic bond collapses. Also the approximate conditions are determined at which no bound electron states exist.

The work described was undertaken to provide data for nuclear safety studies concerning NPF reprocessing equipment. The original objective was to determine the uranium density and water (hydrogen) content of UO2-H2O mixtures ranging from compact centrifuge cakes to dilute slurries. The scope was later expanded to include mixtures of UO2 with hydrocarbon oil and mixtures of UO3-H2O.

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.

Report describing the Enrico Fermi Atomic Power Plant, its fast breeder reactor, and heat transport systems.

Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.

From introduction: "Evaluation of the present economic and technological status of power reactors that are cooled and moderated by heavy water and fueled with natural uranium."

Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.

Abstract. The Tory II-A reactor is a small, air cooled, high power-density reactor which is to operate at quite high temperatures. Design of the reactor is essentially complete. First operation is scheduled for late 1960 at the Nevada Test Site of the Atomic Energy Commission. Since the reactor is unshielded, the control room which houses the recording and indicting equipment is located approximately two miles from the test bunker. Signals from reactor and facility transducers are amplified in the test bunker and transmitted by cable to the control point. The kinds of quantities measures include neutron flux level, temperatures, pressures, vibration amplitudes, strain and air mass flow rate. The recording and indicating system is centered around 258 channels of 1.5 cycle per second, pulse-width modulation tape recording equipment and 72 channels of 120 cps, analogue strip-chart records. In addition, there is a number of the usual meters, scalers and slow-response strip-chart recorders.

Report issued by the Bureau of Standards over studies on the importance of conductive flooring in hospitals. Types of conductive flooring are compared, and tested. The methods and results are presented, and discussed. This report includes tables, illustrations, and photographs.

The feasibility of removing and recovering cesium-137 from various HAPO process solutions by precipitation of Cs2ZnFe(CN)6 has been demonstrated previously. Pilot plant studies of calcination and steam hydrolysis of non-radioactive Cs2ZnFe(CN)6 precipitates by members of the Process Equipment Development Operation are currently in progress. In support of these pilot plant studies, experiments were performed to determine the extent, if any, to which cesium volatilizes during calcination and hydrolysis of Cs2ZnFe(CN)6 precipitates containing cesium-137. Experimental procedures and results are presented in this report.

This report is the third in a series of quarterly reports discussing the concept and progression of an improved method in nuclear measuring than the usage of the scintillation counter. This report indicates that in a chopped double beam system, commutation of the detector current permits selection of optimum response time and size of radioactive sources.

The fabrication processes applied to nuclear fuels are subject to severe limitations because of the conditions imposed by the reactor environment. The combined problems of neutrons fluxes, high heat fluxes, corrosion by the coolant , and embrittlement by hydriding or similar reactions may be minimized through establishing rigorous materials and fabrication specifications for fuel and cladding.

This partially annotated bibliography contains 334 references from papers published from 1945 to 1959 and includes references on the consumable - and nonconsumable - electrode vacuum arc melting process. References are also given on electrode preparation, furnace construction and operation, melting, sintering, vacuum techniques, and theory.

Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.

The amount of dry air or inert gas supplied to a "one pass" glove box ventilation system is proportional to the glove box inleakage. Most glove boxes in the 234r5 Building are equipped with sundry attachments, each contributing to the inleakage. No individual leak rate date is available for these auxiliary components in the "as installed" condition. Nor is the effect of time upon the leak rates known. Knowledge of these values, or at least an indication of the order of magnitude of the leakage attributable to each item, would provide a basis for analyzing glove box ventilation problems and for establishing criteria for new glove box designs.

The probabilities for nine electronic transitions among the low lying excited states in the C2 molecule are calculated by the dipole moment operator method and are given in the form of oscillator strength (or f values).

Current status of the High Flux Isotope Reactor which is being planned for construction at Oak Ridge.

A coolant line rupture during operation of a high temperature gas cooled graphite moderated reactor would present a serious hazard. The reactor would immediately depressurize and a great deal of air would be introduced into the coolant stream. As the air passed over the graphite moderator a runaway oxidation reaction would probably ensue unless an adequate safety system were available. This investigation was designed to evaluate chlorine as a reactor safeguard to be used to control a runaway reaction. Throughout this study, a small amount of chlorine in an air stream has demonstrated the ability to substantially reduce the oxidation rate of graphite. This has been the case even where the principal oxidizing agent was molecular oxygen or ozone.

Report concerning the technical feasibility of induction welding for use in remote maintenance at the Liquid Metal Fuel Reactor Experiment. Includes descriptions of the device used, test procedures, and results.

From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.

"The following is an alphabetical listing of terms and units in common usage at Hanford Atomic Products Operation. Other terms and definitions may be added as the need becomes apparent or as revisions or additional terms are issued by the NCRP and ICRP."

Late in 1958 it became apparent that some fuel elements were failing in the Hanford reactors as a result of water entering through the weld. The mode of entry appeared to be first through a void in the weld, then through a non-wet area or a train of voids in the braze, and finally to the uranium core. Defective closures of a similar nature were also typical of many fuel elements which have failed in the autoclaving operation as shown in Figure 1.

The components for the present aluminum clad, Al-Si bonded, internally and externally cooled (I & E), uranium fuel elements are composed of impact extruded cans and spire caps as shown in Figure 1. This type of component requires two impact extrusions; however, in December, 1957, J. E. Ruffin proposed another design of component in which there was only one impact extrusion. For this component, Figure 2, the spire was impact extruded as a part of the can.

The result of a leak in a PRTR process tube between the flow monitor and the heated section would be to increase the flow through the monitor, but to decrease the flow through the heated section. The concern for the case of small leaks is whether the increase in flow through the flow monitor is sufficient to cause a high flow tip and a reactor scram for the condition where the flow through the heated section is reduced to the point to cause excessive fuel element temperatures.