Studies indicated that the use of soluble poisons as a primary criticality control offers economic and other advantages in that it permits the factors of vessel size and shape and solution concentrations to be dictated by considerations other than those of criticality. It is believed that soluble poison criticality control can be made as reliable as other methods of coaditional control if the application is preceded by adequate development work and is monitored by multiple. independent safeguards. The studies included multigroup machine calculations of the required content of poisons in solutions of fissile and fertile material, a compilation of data on the detection, stability, decontamination, and costs of soluble poisons, and an assessment of the possible effects of a nuclear excursion. (auth)

The NIGHTMARE program calculates the gamma-dose rate at any point in or near a reactor by means of the NDA buildup-factor method. The source distributton is obtained from a two-group, two-dimensional diffusion code (EQUIPOISE-2). Seven gamma-energy groups are used. As many as nine different concentric cylindrical regions may be considered, but only radial variation of attenuation and buildup properties is permdtted. Two schemes of estimating buildup factors through a succession of materials are built into the code, and results may be obtained by using either or both methods. An IBM 7090 computer wtth seven tape untts is required. Computations are performed at the approximate rate of l0,000/n mesh points per minute, where n is the number of axial, radial, and angular increments. The program is run under the control of the IBM 7090 MONITOR system. (auth)

Research and development progress is reported on fuel dissolution, solvent extraction studies, corrosion studies, mechanisms of foam separation, waste treatment, ion exchange, and chemical applications of nuclear explosions. (M.C.G.)

A fuel jacket failure that occurred in May 1961 in the Type 304 stainless steel clad fuel element exposed in the Vallecitos Boiling Water Reactor superheated steam loop (SADE) was attributed to chloride stress corrosion cracking. In order to better understand the failure, a test program was carried out to try to reproduce the rapid stress corrosion attack in the simulated superheat reactor environment of the CL-1 superheat facility. The methods of corrosion testing under heat transfer conditions reported previously were modified: to apply a longitudinal stress on the test sheaths to produce a 0.1 per cent elongation in 1000 hours; to increase the chloride content of the moisture carryover with the steam by increasing the chloride in the recirculating water to 1.5 ppm; and to expose the solids deposits to various metal temperatures. After 1000 hours of exposure, no significant attack was noted on the test sheaths. The test procedures were further altered to simulate the significant amount of SADE fuel element exposure to saturated steam at varying temperatures with little to no superheat being generated. A 776-hour total exposure was carried out with the test conditions cycled several times. The entrance heater (calculated metal temperature during normal operation …

This report covers the following titles: (1) Synthesis of compounds from {sup 14}CO{sub 2} by Chlorella in the dark following preillumination; (2) The effect of oxygen on formation of glycolic acid and other products during photosynthesis by Chlorella; (3) Phosphatase action on phosphoglycolic, 3-phosphoglyceric, and phosphoenolpyruvic acids in spinach chloroplast fragments in the presence and absence of high concentrations of methanol; (4) Absorption spectra of scattering samples. I. An evaluation of three different spectrophotometric techniques using Chlorella; (5) Absorption spectra of scattering samples. II. Scattered transmission spectra of leaves, chloroplasts, and quantasomes of spinach; (6) The effect of sonication of spinach chloroplasts on photosynthetic phosphorylation; (7) Concerning the occurrence of {alpha},{alpha}-tocopherol and {alpha}-tocopherylquinone in chloroplasts and quantasomes; (8) Effects of ultraviolet and gamma radiation of thymine in frozen aqueous solution and in the solid state; and (9) A rapid method for the identification of small quantities of lipid-soluble vitamins and quinones in biological material.

Laboratory studies have been conducted under simulated reactor operating conditions to determine the effect of various chemical additives and coatings on the adsorption of trace elements on aluminum surfaces. Of the materials tested, silicate additives and organic ink coatings were by far the most effective, reducing the adsorption of arsenic and phosphorus tracers by as much as one to three orders of magnitude. The laboratory techniques and results are discussed.

The graphite temperature limits specified in the process standards-are being closely approached or have limited power levels at B, D, DR, and reactors. An increase of approximately 50--100 C in graphite temperature limits at these reactors would permit year-around operation on bulk outlet temperature limits. There has been considerable recent interest in extending to all reactors the use of nitrogen as a reactor gas constituent. With present graphite temperature limits, significant benefit from nitrogen usage will not be obtained during the winter months at reactors which are graphite temperature limited with approximately 100 per cent helium. However, during the summer months when bulk outlet temperature limitations result in graphite temperatures considerably below the maximum permissible graphite temperatures, the substitution of nitrogen for carbon dioxide could be of value. Under these circumstances, both a reduction in helium usage and a reduction in enrichment costs could result. With an increase in permissible graphite temperature limits, year-around benefit from reduced helium usage and reduced enrichment costs would be possible. To meet the Pu-240 specification with higher graphite temperatures however, would require a reduction in current goal discharge exposures with resulting increased fuel and burnout costs. Additionally, the incentives for higher graphite temperatures are …

The criteria contained in this report have been established to provide the technical bases for the design modifications involved in the K-Reactor tube replacement. The ultimate intent of these criteria is to provide the basic technical data and concepts to assure: (1) technical feasibility and operability of the reactor system as modified, (2) operation of the reactor and its services to minimize nuclear and radiation hazards, and (3) appropriate lifetime of the reactor and its service facilities as modified. The criteria are appropriately broad and may not contain all the data necessary to accomplish detail design. The information contained herein shall serve as a basis for evaluation and approval of all portions of the modification relating to the process as indicated in the above three points.

Currently the Irradiation Processing Department is working on a program which has as its goal the reduction of radioactive discharge to the Columbia River. The most significant radioactive isotopes of concern are the relatively long lived isotopes P{sup 32}, Zn{sup 65}, As{sup 76}, N{sub p}{sup 239} and Cr{sup 5l}. Because of their relatively long life they can be found in the Columbia River well below the Hanford Plant. P{sup 32}, because it is absorbed and concentrated by the river biota is of prime concern because the dose which it contributes to man through the eating of fish is not known for certain. Included in this reactor effluent decontamination study program are studies of process water recirculation systems, process water pre and post treatment methods, and effluent disposal to an artificial lake. This report reviews the artificial lake concept to determine its feasibility and possible effects on the concentration of radioactive isotopes in the Columbia River downstream of the Hanford Plant. The findings are based on the study and evaluation of available data. Meterological, hydrological, and biological absorption aspects of the artificial lake concept were studied several years ago. Little or no scientific work has been done in recent years to …

I&E uranium cores are to be jacketed by Sylcor and Hanford utilizing the ``Solid State Diffusion-Hot Pressure Bonding`` process. Hanford will also jacket cores by the ``Solid State Diffusion`` process, by ``Gas Pressure Bonding`` and ``Hot Die Sizing``. In this process, a layer of nickel is placed between the aluminum and uranium to prevent diffusion of the aluminum into the uranium and furnish a layer of metal capable of limiting diffusion with both the aluminum and uranium. The completed fuel element therefore, consists of a uranium tube, bonded by diffusion to a layer of nickel which, in turn, is bonded to the aluminum can. The bond set up by the ``Solid State Diffusion`` process has excellent strength, ductility, continuity, heat transfer abilities and, based on off-site experience, should withstand the changes which take place during irradiation. The objective of this test are to determine gross dimensional stability and bond quality differences between the Al-Si bonds and solid state diffusion bonds.

A project has been proposed and the funds allocated for the replacement of the central zone aluminum process tubes at both K Reactors with smooth bore zirconium process tubes of approximately the same outside diameter as the original tubes. Associated with this project is the problem of relieving the present graphite stack distortion in the vicinity of the process tube channels and counteracting or prereliving, at this time, the expected graphite stack distortion that, will take place over the next ten years. Such relief becomes increasingly important when it is realized that long reactor life is required for the zirconium tubes in order to justify the cost of the project. This justification is also based upon the ability to charge normal sized, self supported fuel elements during the reactor life of the tubes. Relieving the restrictions in the graphite process channels caused by stack contraction will be done by removing localized portions of the graphite from the tube blocks and trunion blocks with a guided cutting tool. This immediately brings up the question of graphite temperatures and the presently imposed maximum graphite in temperature limits. Combined coring and graphite stark distortion could result in excessive graphite temperatures or localized hot …

This report documents the answers to specific questions posed by management on December 17,1962. The questions asked were: (1) What were the design and construction start and completion dates of project CG-558-600?, what was the percent power level increase design for CG-558-600?, what was the actual power level increase achieved?, what was the construction completion date of DR reactor?, what was the expansion-overbore program initiation date?, on what date was the oral overbore-type proposal made to HOO-AEC?, when was the initial documentation of overbore-expansion program?, on what dates were the budgets submissioned for the Reactor Modification Program?, what is the conversion ratio increase from the RMP?, what is the production capacity increase from the RMP?, and what are the design completion dates for the H, C, DR, and K reactors?. (GHH)

The objective of this production test is to authorize the irradiation of three natural uranium corrugated I&E-type fuel elements in a KE Reactor front-to-rear test hole. The ultimate exposure of Zircaloy-2 clad, coextruded, uranium-cored fuel elements may be limited by localized tensile necking and splitting of the jacket. The total deformation capability of a fuel element is increased by corrugating the outside surface so the perimeter is greater than that of a circle circumscribing the equivalent cross sectional area. Thus, swelling of the uranium core is accommodated by bending of the clad rather than by large clad tensile strains. The test is designed so the knowledge gained will be applicable to the NPR fuel assemblies.

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Research progress is reported on solid-state theory, crystal physics, metals, nonmetals, radiation metallurgy, and reactor materials. Separate abstracts were prepared for each topic. (M.C.G.)

The thermal decomposition of ferric nitrate nonahydrate, chromium nitrate nonahydrate, aluminum nitrate nonahydrate, and nickel nitrate hexahydrate as well as the mw- tures of these compounds in the proportions produced in the dissolution of Nichrome and stainless steel alloys was investigated. The experiments were conducted in air at two heating rates, approximately 1.1 deg C and 2.6 deg C per minute. The intermediate producte and final products were analyzed by x-ray diffraction and chemically where it was appropriate. (auth)

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The relative cross section for the production of protons from water by electron bombardment was measured by a modulated crossed beam technique over an energy range from threshold to 500 ev. The appearance potential for protons was measured by comparison with the ionization potential of hydrogen and found to be 19.4 ev. This result is in agreement with earlier results. The overall curve is smooth with the exception of a slight shoulder at about 45 ev. This shoulder may indicate the presence of more than one process for the formation of protons. (auth)

Several 300 series stainless steels were corrosion tested in raffinate storage tanks made of the same materials. After exposure to the rafflnate solutions for periods of up to seven years, maximum penetration rates of 0.1 mil/ yr were noted. (auth)

Thorium and uranium carbide nuclear fuel particles were evaluated by metallographic and x-ray diffraction techniques. Techniques were developed to etch the polished surface of Th--U carbide to reveal the grain structure. In addition, techniques to determine particle density and coating thickness were developed. Comparison of the data indicates that the use of spherical particles allowed for more precise determination of the coating thickness, density, and strength of coatings. Strength of individual particles was about 700 to 1300 g per particle. A large scatter in crushing-strength values was observed when individual particles were crushed. Consequently, a relative crushingstrength test was developed for comparing coating strength: loads were applied to a column of particles in stepped increments, and broken coatings were detected by observing a weight gain in moist air from hydrolysis of the Th--U carbides. A correlation of relative crushing strength and coating thickness was obtained. The crystal structure of the C coatings was found to depend on the temperature of deposition in the range from 1400 to 2400 deg C; the twodimensional structure became more defined with increasing deposition temperatures. Subsequent annealing at 2400 deg C of the coatings deposited at 1400 deg C and at 2200 to 2400 deg …