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 experimental results on the oxidation of H from a He stream with CuO pellets were very close to the predicted behavior based on the mathematical model. Experimental measurements of uranyl sulfate loading rates on chloride equilibrated resin showed little variation with solution concentrations. A tentative flowsbeet was proposed for cost analysis of processing a Pebble Bed Reactor. A U-Zr plate was dissolved in nitrate-free Zirflex solution. An authentic TRIGA prototype was processed in engineering-scale equipment. Three 4- stage leacher model dissolution runs were made, two of which used 8 M HNO/sub 3/ and one used 4 M HNO/sub 3/. Flooding rates and holdup data were obtained for sieve plate pulse columns under 5% TBP - l.8 Mi Al(NO/sub 3/)/sub 3/ flowsheet conditions. A Purex waste calcination run (R-37) was made using sodium anid imagnesium to reduce sulfate volatility. (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)

Tests were performed to obtain station performance data at various steady-state generator loads. The station 0 was operated for four-hour periods at steady state conditions and levels of 5, 21, 42, and 61 Mw gross generator output. The various readings are presented in tabular form. A list is given of equipment in service during the test. All plant components operated satisfactorily during the test. (M.C.G.)

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.)

Information is presented in tabular form on the contributions of the individual resonances to the resonance integrals in U and Th. The cases considered are for isolated cylindrical rods and involve U/sup 238/, U/sup 238/O/ sub 2/, Th/ sup 232/, and Th/sup 232/O/sub 2/ (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 …

There are four district stratigraphic units within the Pasco Basin which if interpreted on the basis of recent field evidence and described properly could be traced over most of southeastern Washington. At the present time these post-basalt sediments are described in the literature in such a way as to make extensive correlations impossible. Some descriptions overlap more than one unit whereas others describe only a part of the unit. It is proposed that all interested geologists in the Pacific Northwest now consider reconciling the differences which exist in the names and descriptions of those sedimentary deposits in light of this new evidence.

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.

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A number of burnout tests have been run subsequent to the publication of the burnout equations in DP-355 and DP-725. The range of variables was extended in these tests and the burnout heat flux was measured. This memorandum presents a modified empirical equation, which correlates the new data, for use in the design of fuel assemblies for the HWCTR. We expect to submit this material for a journal publication within the next quarter.

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.

This report presents the dose rates which were observed during the removal of a Zircaloy-2 process tube from C Reactor. The corresponding calculated activity is also presented for the purpose of correlation with the observed dose rate. The tube was removed on July 22, 1964, after having been irradiated by a neutron flux for 560 days (based on time operated efficiency). The tube activity was monitored with a super high range TP (0-5000 R/hr) by suspending a probe through an access port in the floor of the ``D`` machinery room. As tube 3353 was pushed and cut into sections, the highest activity observed was 675 R/hr, which was seen in the center three-foot segment. The corresponding calculated activity was 650 R/hr. The neutron flux profile, as shown by tube activities along its length, was extremely peaked in the center; for example, the area under the activity curve was less than one-third of the area under a cosine curve of the same amplitude and cycle length.

Results of an investigation of fuel element outer annulus enthalpy imbalance are reported and analytical results of suggested methods to limit this imbalance are presented. Also included are comparisons of calculated and experimental enthalpy imbalance ratios along with other quantities. Results indicate that tightening fuel tolerances and clearances can substantially reduce the present outer annulus imbalance thereby increasing power capability. A basic pre-requisite to reduction of clearance between fuel support diameter and process tube diameter is a test establishment of the minimum allowable clearance compatible with charging requirements. Matching fuel elements to process tube diameters will also reduce the imbalance but is in general not feasible at the present time.

Purpose of this test was to evaluate the behavior of LiAl elements at N-Reactor operating conditions. The test was made to determine the swelling rate of the LiAl alloy, effect of irradiation on mass transport of lithium and tritium in the target assembly, and effect of Al surface treatment on transport of lithium and tritium.

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 …

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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.

The power of high flux fuel assemblies and three-tube drivers planned for future operations is limited by the burnout safety factor (BOSF). In the past, the power of standard production fuel assemblies was limited almost always by one of the hydraulic limits, and in most cases the assemblies operated at powers significantly below that permitted by the BOSF limit. The burnout conditions for an ``ideal`` fuel surface have been well established in mockups at SRL and Columbia University. Little experimental data are available on nonidealities (such as local hot spots), although calculated factors are applied to the BOSF to account for certain nonidealities. Because of operation at the BOSF limit, better knowledge is needed of the effects of nonidealities and other factors on heat transfer burnout of fuel surfaces. This memorandum presents a program designed to give a better understanding of BOSF.

The possibility was reviewed that errors in calculations might have resulted in an erroneously high theoretical strontium activity which would explain the unexpected low activity found ion the strontium recovered from Purex wastes. The new, corrected calculations (49,213 curies/T) improves the accounting from 65 to 75% of theoretical. The discrepancy still should be investigated.

The objective of this test authorization is to increase reactivity and thus reduce short term enrichment requirements by increasing graphite temperature limits during low exposure operation following full central zone discharge.

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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 …

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