There is but little known about the thermal process involving the dynamics and thermodynamics of the cycling liquid H2 in the chamber and those of the H2 fluid flow in the cooling coil as well as the geometrical characteristics of the chamber body. This the physical equations governing this process are involving so many variables that this analysis becomes rather complex even if simplifying assumptions are made. To those difficulties is added the ignorance even of an approximative expression for some physical quantities such as film heat transfer coefficients entering as major parameters the process equation.

From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."

This report was prepared by Battelle-Northwest under Contract No. AT(45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during October 1969.

This report was prepared by Battelle-Northwest under Contract No. AT(45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during September 1969.

This report was prepared by Battelle-Northwest under Contract No. AT (45-1)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during February 1969.

This report was prepared by Battelle-Northwest under Contract No. AT(4S-l)-1830 for the Atomic Energy Commission, Division of Reactor Development and Technology, to summarize technical progress made in the Fast Flux Test Facility Program during March 1969.

The purpose of this report is to determine the amount of refrigeration capacity required to cool down the 80" bubble chamber from ambient temperature to liquid hydrogen temperature.

Reliability of individual components and the ability to produce refrigeration even if one or two of these components should be in operable are the prime design parameters of this cycle. Each component was looked at with these two parameters in mind and any item that had obvious objections was either rejected or backed up with another piece of equipment. Along this line, you will notice (refer to line schematic) two hydrogen compressors and two nitrogen compressors; for full capacity all are required. However, in the event of the loss of use of one of these compressors, it will still be possible to produce at least 50% of the rated capacity. To eliminate outside influences, the cycle was designed around what may be called a closed cycle cascade system; with the assumption that there is no loss of power, cooling water, the equipment can run indefinitely. The nitrogen and hydrogen cycles are of the Simple Linde type with pre-cooling making use of the Joule-Thompson Effect for the refrigeration produced. The low-temperature components of the cycle have no moving parts other than valves, consisting entirely of counter-flow heat exchangers to lower the temperature of the incoming high-pressure gas to a level where …

When the design of the refrigerator was begun, one of the important parameters was refrigeration capacity required. In order to estimate the required hydrogen refrigeration load the following had to be considered: 1. Dynamic Load due to pulsing of the chamber. Although this has been determined some two years ago through test work, it has not been published as of this date and will be presented here. 2. Static losses due to conduction, radiation, and convection. This is covered by Eng. Note BC-03-0-B. 3. Cool-down requirements. This is covered by Eng. Note BC-03-0-C.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period. Data are given in table form. Information given includes: TISR number; request number; material; piece number; operating time; CMK absorbed; charge date; location; exposure to date; discharge, date and times; and shipping data.

For an experiment to measure the magnetic moment of the Λ hyperon, it was necessary to extract the external beam of the Cosmotron with maximum efficiency and with minimum time duration. To accomplish this end, the standard external beam of the machine was supplemented with the Rapid Beam Ejector. It was found that, unfortunately, the ejection efficiency of the beam was less than normal when the RBE was used. Measurements of the ejection efficiency were made by irradiating polyethylene foils at the second focus of Beam 1 with 3 BeV protons. The external beam was tuned up and optimized in a standard manner. It was found that the ratio of the number of protons ejected with the RBE to the number ejected without the RBE was 0.3 in one run and 0.22 in another try. It was also observed that the RBE did not shift the position of the external proton beam focus to within ± 1/8 in.

The macroreticular anion exchange resin, Amberlite IRA-900-OH, and an experimental resin from Ionac Chemical Company were irradiated by a /sup 60/Co source to doses of 5 x 10/sup 7/ rad and 10/sup 8/ rad. These doses approximate or exceed the dose encountered by the deionizer resins in 100-Area service. The loss in exchange capacity and the volume changes of Amberlite IRA-900 on irradiation were similar to those found previously for Amberlite IRA-400. The Ionac experimental resin, which had a considerably lower initial exchange capacity, likewise was not stable to radiation. It is concluded that Amberlite IRA-900 offers no advantage over Amberlite IRA-400 for 100-Area purification service. Since there is little justification for further evaluation of macroreticular resin for 100-Area use, the present work completes RTA-893-R.

We consider the kinetic isotope effect in three center reactions of the type of A+BC→AB+C. Such model calculations are a good approximation to primary hydrogen isotope effects. For abstraction or transfer reactions, B becomes H, D, or T. The dynamics of the three storm system are calculated for a general quadratic potential, with the assumption that the potential energy is constant along the reaction coordinate (flat top barrier). This model system can be calculated in detail and serves to illustrate the relationship between kinetic isotope effect and chemical bonding in the transition state. The statistical mechanical part of the calculation can be carried out exactly within the framework transition state theory or in any one of a number of approximations. The γ bar method gives particularly good insight into the chemistry of the problem with a minimum of arithmetic.

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The status of aqueous processing methods for tharium fuels is reviewed. A specially designed 250-ton shear was successfully tested for shearing full-size simulated Consolidated Edison type unirradiated assemblies into 0.25-1.5 in. lengths.

Despite similar atomic arrangement, Brucite (Mg(OH)2) and phlogopite (KMg3(OH)2(Al,Si3)O10) present striking difference in their infrared spectra. A single absorption band is observed in phlogopite whence brucite possesses a total of 15 bands on both sides of the fundamental. A comparison of the hydroxides with micas provides supporting evidence that the complexity of the hydroxide spectra is due to interactions between neighboring hydroxyl groups. Each mineral contains a layer of magnesium ions possessing trigonal symmetry. Both minerals contain hydroxyl ion is located in such a way that it is in contract with three magnesium ions.

The wrist badge provides a dosimeter that is useful in estimating the radiation dose to the hands and forearms. Its new shield system gives good gamma and slow neutron dose discrimination with duPont 552 film packets. The film can be evaluated using the present technique and equipment. Several attempts to develop hand dosimeters have been made. Finger rings using film have been used routinely but have not been entirely satisfactory for all situations. The wrist badge was developed to provide improved gamma and slow neutron dose measurement of the upper extremities under certain appropriate conditions. The wrist badge dosimeter is not a substitute or alternate for finger ring dosimeters but is a necessary dosimeter for some extremity exposure situations.

The purpose of this report is to compare multi-layer insulation and liquid nitrogen shielding as methods of insulating the 80-inch Liquid Hydrogen Bubble Chamber.

The following information is provided to assist you with your engineering evaluation of the gaseous wastes released to the atmosphere via stacks and roof vents in the 200 Areas for inclusion in the Hanford Low Level Waste Management Reevaluation Study report. Included in discussion are: release rates and public radiation dose rates.

A new concept for separation of the isotopes of uranium has been developed. The invention consists of a new process with essentially no moving parts. The new process is called the Ionized Vapor Process and is described in this report.

This report is a compilation of available data on ruptures that have occurred since KER start-up. Some of the data presented in this report are inconclusive, but are reported to insure a complete summary of all potential and confirmed ruptures.

The capability of calculating the close-in effects of the shock wave from an underground nuclear explosion has been demonstrated. Agreement was obtained between calculation and measurements using .a spherically symmetric, hydrodynamic, elastic-plastic code called SOC for the Hardhat event, a 5-kiloton nuclear detonation in granite. This capability is dependent upon having a more or less complete de scription of the elastic and dynamic properties of the materials involved. When this information is available, agreement within the limits of uncertainty of the measurements can be calculated for peak pressures, peak particle velocities, shock wave time of arrival, and pressure pulse shapes.

The geologic map of the Paiute Ridge (Papoose Lake SW) 7 1/2-minute quadrangle shows an area of about 4 square miles on the east side of Yucca Flat that is underlain by basaltic rocks. These rocks are estimated to be as much as 1,000 feet in places and occur as a capping on a small mesa and as lopoliths, igneous masses that in cross section are saucer-shaped. This area was further studied to determine the geologic features of the basaltic rocks in order to evaluate the potential use of this area for underground test sites in media other than tuff, alluvium, and granite, particularly in media of high density. The results of this work are set forth in this report. There are two possible test sites in basaltic rock in the area. Site 1 (within Nevada State coordinates E 709,500 and 710,500 ft and N 854,000 and 856,000 ft) is suitable for a shallow test. Site 2 (bounded by Nevada State coordinates E 707,000 and E 712,000 ft and N 848,000 and N 853,000 ft) could be used for a deep confined test in basaltic rock.