This memorandum is an outline of the principles and methods employed by 5100 Human Engineering Personnel in consultation on test equipment panel layout. The process of control panel layout is partially formalized with particular emphasis on test equipment panels. An experimental method is proposed for selecting an optimum panel layout. The essential role of experimentation is pointed out. The optimal layout for a nonrepetitive procedure is deduced and generalized to give methods of layout solution for the general repetitive procedure.

Fused uranium dioxide was separated into fractions of varying particle size by air separation. Specimens of the nominal size of 1/8 by 1/4 by 1½ in. were formed by hydrostatic pressing, firing, and lapping. Specimens prepared from the 0 to 5 μ fraction were the strongest and most dense. The room-temperature density was about 92% of theoretical and the room-temperature flexural strength was about 12,000 1b. per sq. in. When tested at 1000°C., the strength was about 18,000 1b. per sq. in. The flexural strength of specimens decreased and their density decreased as the starting particle size was increased. The crystallization of the urania fragments which had occurred during the firing treatment was observed.

The primary purpose of these researches was to clarify the various functions of organic substrates in bacterial photosynthesis. The following aspects were investigated; (1) metabolic pathways under photosynthetic and oxidative conditions, (2) energy transfers occurring during the metabolism in cell free extracts, and (3) the relationship between photosynthetic rate and light intensity for selected organic substrates. The results of these investigations were summarized in a paper entitled "The Application of Carbon-14 to Studies on Bacterial Photosynthesis" which was submitted to the United Nations as a contribution to the International Conference on the peaceful Uses of Atomic Energy, Geneva, Switzerland, August 8-10, 1955. A reproduction of this paper constitutes a major portion of this report.

Equipment lists and operating procedures are present for a laundry designed to wash contaminated clothing.

Twelve neutron activation analyses for naturally occurring technetium-98 were performed. Positive results were obtained in ten cases. Precautions were taken to avoid interference by molybdenum and technetium-99. the cross section for the reaction [formula] as found to be equal to 4 +- 2 mb for the neutron spectrum of the vertical thimbles of the Argonne CP-5 reactor. The chemical state of molybdenum (VI) in basic solution was studied by an anion-exchange technique. Evidence was obtained for the existence of polymeric species at pH-values up to 14. Preliminary work on the stability of Domax-1 anion exchange resin in perchlorate media indicates rapid deterioration even at 0.2F ClO4-.

This technical report describes a simple way to calculate numerical values of K and l shell photoelectric absorption coefficients (averaged over subshells) for highly ionized atoms.

The theory and preliminary laboratory investigations presented in this technical report were intended to examine the general feasibility of injection disposal of radioactive wastes and to establish an understanding of the phenomena governing the travel of trace chemicals through natural porous media. Detailed studies of fluid velocity variations resulting from density differences between the injected and displaced liquids have been made. the ion exchange studies have been limited to strontium and calcium. Strontium 90 is considered to be the most hazardous of the fission products and should represent the radioisotope upon which to judge the merits of injection disposal. Consideration should also be given to cesium in evaluation the health hazards of injection disposal.

Three groups of balloon flights carrying unshielded boron trifluoride counters were made from geomagnetic latitudes 10.1°N, 55.1°N, and 88.6°N. From the data obtained, curves of slow-neutron intensity versus atmospheric depth for depths less than 700 millibars are plotted. The mean absorption lengths for neutrons in the equilibrium portion of the atmosphere were found to be [formula]. The depths of the neutron intensity maxima were found to be [formula]. From these results and those of other investigators, the variation of the mean absorption coefficient and the depth of the neutron intensity maximum are plotted as functions of the geomagnetic latitude. A family of curves of neutron intensity versus atmospheric depth is drawn for geomagnetic latitudes at 10-degree intervals between 0° and 90°N, and from this the low-energy neutron capture per square centimeter per second by the N14(n,p) reaction in the atmosphere is calculated and plotted as a function of geomagnetic latitude. It is found that the observed neutron intensity varies by about 420% from 0° to 90°N. A value of 5.8×10(18) sec-1 is obtained for the total number of low-energy neutrons captured in the atmosphere.

The purpose of this report is to present the information obtained relative to the characteristic adsorption of radioisotopes in a long (forty feet) laboratory soil column treated with a high salt, process waste of high activity density. The movement of adsorbed cations in a soil column subjected to prolonged leeching by water also was determined.

An Alpha Scintillation Probe for use with the HAPO Cart Poppies has been designed to replace the air proportional probes presently used. The new probe has an average geometry of about 15 or 16 percent over an effective probe area of 23.4 in². Stability of operation under normal conditions of vibrations, humidity and temperature are inherent qualities and the average background count is stable at about two counts per minute. The high voltage used is in the order of 1,200 to 1,250 volts with a current requirement of 100 microamperes.

Fillerwelding is a fusion welding process that provides for the automatic addition of controlled amounts of fillerwire during inert-gas-shielded tungsten-arc welding. Fillerwelding aluminum jacketed fuel elements has been successfully demonstrated and is being used on a routine basis. This manual was written to provide the necessary information to operate and maintain the fillerweld equipment.

A design study has been made of a graphite superheating reactor, a graphite moderated reactor with a heat rating of 305 Mw which produces superheated steam. It is designed for the production of plutonium and electrical power or for the production of electrical power only. The fuel elements for dual- purpose operation are U metal, while for single purpose action, they are uranium oxide. The fuel elements are cooled by a 7-pass system in which preheated water enters the bottom of the first pass and is discharged as superheated steam at the top of the seventh pass. The reactor control consists of shim control by the gas system, vertical gas-cooled control rods, vertical safety rods, and a ball safety system. Rough cost estimates indicate that the capital cost of the reactor should be comparable to other reactors of similar heat output.

The water plant for a high temperature reactor must be capable of providing several purities of water to the various components of the installation. The actual treatment methods will depend on the location and size of the reactor, the size and sources of the water and the ease of disposal of radioactive wastes. This document examines the needs for the various water purities. It also defines the area of future work to provide the information necessary for the design of water plants for high temperature reactors or for the conversion of existing reactors to recirculation cooling.

The surfaces of cold rolled, half hard, nitric acid treated, autoclave etched, 2S aluminum coupons were studied by optical and electronoscopic methods, before and after exposure to hot water alone and hot water and neutron bombardment. The non-exposed aluminum surfaces have a characteristic pattern which is absent in the exposed coupons. All of the exposed coupons were corroded. In general the coupons exposed to the higher flux intensities of irradiation were more severely corroded than those exposed to the lower flux intensities of irradiation or to the hot water alone. Representative photo-and electron micrographs illustrate the various types of surface structure observed on the control and experimental coupons.

Equations are developed for the computation of MPC's for radioisotopes assuming the excretion or retention to follow a power law rather than an exponential law. Computations are made for four isotopes on which some human data are available. Uncertainties in the initial data due to the use of intravenous injection to obtain the primary data, the definition of retention and the effects of age and diet are discussed.

Ten materials in which gold was alloyed with copper, silver, graphite, platinum, nickel or zinc (compositions given in Table 1) were evaluated in this study. Corrosion tests to determine the resistance of the alloys to boiling 60 to 65% nitric acid showed that with the exception of an alloy containing 51 wt % gold and 49 wt % graphite (Gold Graphalloy 811) which dissolved in 48 hr and an alloy containing 90 wt % gold and 10 wt % graphite which lost 2.3 wt % in 240 hr the alloys were essentially corrosion resistant.

As potentially suitable alternate methods of installing closure plugs in cored slugs, four different schemes were considered. One of these schemes, whereby a flat chamfered uranium disc is crimped into a counterbored recess at each end of the bare slug after pickling, was developed to a workable state, and partially evaluated prior to reassignment of the job to another group. From the results of initial evaluation tests, this process appears to provide leak-free core closures and offers economic benefits that make it attractive as a production method, should cored slugs be adopted as standard.

This report has been prepared to review the status of design for buried waste line and presents the major factors involved in support of the conclusions. This report is the second in a series reporting on the general subject of underground corrosion. The first on cathodic protection of waste lines noted the technology of stainless steel and its effect on existing waste line and recommended continued use of the cathodic protection. Experience with buried stainless pipe had shown that, unless protected, such installations are subject to severe pit corrosion. As designs developed the use of encasements has become a standardized approach. This discussion will evaluate this trend.

Part 1. The neutron fission cross section of U237 has been measured in a thermal neutron spectrum and in a somewhat degraded fission spectrum. The fission cross section for thermal neutrons is found to be <2 barns; the ratio of the fission cross section of U237 to that of U235 in the degraded fission spectrum is found to be 0.476 +- 15% which corresponds to [formula] in this spectrum equal to 0.66 +- 0.10 barns. Part 2. The average neutron fission cross section of U237 has been measured in a neutron energy range extending from approximately 100 ev to fission spectrum. the average fission cross section in this spectrum is found to be 0.70 +- 0.07 barns. Part 3. The low thermal fission cross section for U237 (<2 barns) indicated that the excitation function for fission probably shows an effective threshold. If the excitation function is like all other heavy element (Z > 90) neutron fission excitation functions, it will exhibit a region of approximate constancy starting at a neutron energy of 0.5 to 1 Mev above its effective threshold and extending to a neutron energy in the neighborhood of 5.5 Mev. A hypothetical excitation function for neutron fission of …

This report of the Battelle Memorial Institute covers information on development regarding various materials.

Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."

Abstract: "By a simple illustration it is pointed out that, conceivably, the real coupled character of the general magnetohydrodynamic equations may lead to much slower instability growth rates, if not stabilization, than predicted from the linearized set of equations."

Report describing "Program D", a nuclear reactor calculation program for the AGT Evendale IBM 701 digital computer. Explanatin of necessary input data and the machine output is included.

A report which concludes information pertaining to WAPD concerned with the development of PWR fuel materials and fuel elements.