Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.

System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reactor use, 10,000 to 12,000 gpm was demanded by B Area through the 183 BC intertie. The maximum flow that the intertie line could handle, without reducing the filter capacity of the C Area filters, is about 21,000 gpm.

Recent (HCR) Horizonal Control Rod operating problems at the K Reactors, caused primarily by graphite stack distortion, have stimulated several designs of HCR`s capable of operating under adverse conditions. One such design is an aluminum HCR, not completely dissimilar to the present HCR`s, conceived by the Research and Engineering Operation of I.P.D. The successful use of aluminum as a structural material is strongly dependent upon the operating temperature of the aluminum. This study was conducted to determine anticipated operating temperatures of the HCR during reactor operation at the present K Reactor conditions.

Analysis of Columbia River temperature trends indicates conformity with those previously reported. Despite unusually high average temperatures, the temperatures of the upper and lower extremes continued to converge on the mean. The construction of the John Day Dam is expected to have little temperature effect other than a delay of ten days in the timing of the annual temperature peak. Measurements of radioactivity in 465 children were completed at the third Pasco elementary school on January 12. Whole-body counting at the fourth school began on January 24, following lectures to the staff and 17 classrooms. The whole-body counter was recalibrated for K{sup 40} and Zn{sup 65} in late January. Only small modifications in the calibration factors over those currently employed are expected. Washington State Game Department personnel have supplied sufficient pheasant and quail samples shot near the Columbia River for comparison of radionuclide content between species and collection of these samples has been discontinued. The Department of Game continues to supply ``road-kills`` for radiochemical analysis in exchange for x-ray data on the number of birds which contain shot. A game-bird questionnaire for mailing to a statistical sample of Tri-City hunting license holders was drafted in January.

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Nucleon-meson cascade calculations were carried out and the dose as a function of depth was obtained for an 800-Mev proton beam incident on a shield. The physical properties used for the shielding medium are only a rough approximation to the properties of any particular medium. Muon, neutron, pion, and proton dose rates and fluxes are listed. (auth)

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In a previous report nucleon-meson cascade calculations were carried out for several cases of interest in the design of the transverse shield for the proposed 45-Bev linear electron accelerator at Starford University. In this report results are given for several additional cases. Muon, neutron, pion, and proton intensities as function of energy and distance for varying angles are given. Corresponding doses are also included. (D.C.W.)

A study was made of the adaptation of the HAPO anion exchange process to the reprocessing of Fast Ceramic Reactor (FCR) fuel using the Idaho Small Plant Concept. It is shown that the anion exchange flowsheet meets the reprocessing objectives of the FCR case and can be adequately accommodated in the Small Plant Concept. Capacities of up to 1550 Md(e) are feasible in the Small Plant and unit reprocessing costs range from 0.14 to 0.28 mills/kwh depending on the number of reactors to be processed. (auth)

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In his relatively short life of 57 years, Ernest Orlando Lawrence accomplished more than one might believe possible in a life twice as long. The important ingredients of his success were native ingenuity and basic good judgement in science, great stamina, an enthusiastic and outgoing personality, and a sense of integrity that was overwhelming. Many articles on the life and accomplishments of Ernest Lawrence have been published, and George Herbert Childs has written a book-length biography. This biographical memoir, however, has not made use of any sources other than the author's memory of Ernest Lawrence and of things learned from him. A more balanced picture will emerge when Herbert Childs biography is published; this sketch simply shows how Ernest Lawrence looked to one of his many friends.

EURIPUS-3 calculates the one-dimensional spatial density of neutrons slowing-down past a given energy in an infinite homogeneous medium consisting of hydrogen and one other isotope with arbitrary mass and energydependent differential-elastic and absorption cross sections. DAEDALUS determines the corresponding spatial distribution of angular integrals of an arbitrary function times the vector flux density. Spatial moments of all density functions are furnished directly. Although scattering angles are calculated by Monte Carlo, the spatial distributions and, in DAEDALUS, the energy distribution are obtained partly from an analytic treatment which, besides saving tinne, enables the output to be in the form of actual density functions at specified planes and energies, rather than histograms covering finite intervals. At certain steps in the computation of both the spatial and energy distributions, part of the analytic treatment is replaced by Monte Carlo in order either to maximize efficiency and/ or to avoid round-off error. The neutron source may be monoenergetic with either isotropic or monodirectional angular distributions, or else the source may be that from deuterons bombarding deuterons. The volume displaced by a cylindrical tube from an accelerator to the source can be accounted for in the neutron first flight but not thereafter. (auth)

S>Critical studies of two fast reactor cores are described: one contains uranium and steel; the other contains uranium, steel, and sodium. Experimental results are given for fission ratio, central and edge reactivity coefficients, fuel bunching, average prompt neutron lifetime, and distributed worth measurements. (auth)

ABS> The removal rates of iron, nickel, and chromium from synthetic stainless steel waste solutions during electrolysis over a mercury cathode were studied. The loading capacity of the mercury for the stainless steel metals was estimated on the basis of laboratory experiments to be about two% by weight. The laboratory data indicated that, at an electrode potential of --1.80 voits vs S.C.E., 85 ampere-hours per liter of waste removed essentially all of the stainless steel ions from a sulfuric acid solution containing 0.13M metal ions at 35 deg C. (auth)

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No abstract currently available for this document at the current time.

Pressure drop tests were performed in the 189-D-Hydraulics Laboratory to determine the number of K-Reactor solid aluminum pieces (SAs) required to throttle the tube flow of a 46-piece KVE and a 38-piece KVN arch-rail I&E fuel charge to that of a corresponding bridge-rail charge. In addition, the effects on Panellit pressure and tube flow were determined for several cases.

This report addresses the calculational models for beta dose from spherical particles.

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The Large Component Test Loop is a facility for ASCR providing experimental capacity for subjecting large components, such as moderator assemblies and control rods, to thermal gradients and transients at varying rates of sodium flow to simulate reactor operating conditions. Two separate loops are used for heating and cooling the sodium as the testing is performed. The 3-inch pump loop, modified to operate at 1200 deg F, was operated at a flow of 130 gpm and a head of 25 feet. The 6-inch pump loop, limited to 1000 deg F operation by materials of construction, was operated at a flow of 2000 gpm and head of 65 feet. The rest of the facility has operated satisfactorily at 1200 deg F. (auth)

The diffusion of Kr/sup 85/ in two UO/sub 2/ powders was studied by performing a series of post-irradiation anneals on the powders. The emanation data were analyzed by considering the effect of sintering as well as the effect of a distribution of particle sizes within the sample. Measurements were made at 900 to 1500 deg C. The time at a temperature was between 8 and 24 hours. The diffusion coefficients for Kr/sup 85/ in the two powders are represented by the equations: D = 2.65 x 10/sup -4/ exp - 65,500/RT for UO/sub 2/ prepared from crushed UO/sub 2/ pellets and, for a chemically prepared UO/sub 2/ powder, D = 4.9 x 10/sup -4/ exp - 73,800/RT. (auth)

The studies were primarily directed toward selection of the optimum loading for Core lA and a prediction of its properties. Included are analyses of some relevant experiments on Core 1, and prelimlnary modifications of Core 1 to Core lA. The factors which must be considered for the optimum loading determination are discussed. Four different loading pattenrs were investigated, which were considered to span the numerous possibilitles. Adequate cold shutdown was found to be almost unobtainable without the use of boric acid. For this reason, and because the heat transfer and stability limitations are severe, greater weight was given to heat transfer as opposed to control requirements. The use of boron-stainless steel poison strips fastened to the sides of the spike elements is considered insofar as in improving the loading from either the heat transfer or control standpoint. The relatlve advantages and disadvantages of the use of stainless steel fuel followers as opposed to Zircaloy followers are discussed. (B.O.G.)

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