In order to decide the value and type of information to be obtained from outer space with regard to its pertinence for the evolution of life, a brief review is presented of the current status of our thinking on the origin of life on earth. This points up the particular kinds of chemicals whose presence, or absence, on other astral bodies might be significant. Heretofore, the only data available are the result of telescopic spectroscopy. We report here information indicating the presence in meteorites of complex organic materials, some of them apparently uniquely pertinent to life processes.

In accordance with the policy that a centralized inventory shall be kept of all radioactive waste liquid discharged to ground, it is recommended that the volumes of condensate from the SX-farm, the dates or periods of discharge, and the activity densities of radioisotopes in the condensate discharged be determined by Separations Section and reported regularly to the Radiological Standards Unit. This paper is a description of the condensate system, with recommendations for sampling and analysis.

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The effect of temperature on the properties of graphite is being determined by exposing samples to pile neutrons at controlled temperatures in the range 75 C to 225 C. The first series of samples were charged into the newly installed dry, water-cooled test channel at B pile on January 23, 1951. This report presents details of the charging operation and observations noted during the initial operation of the test.

The nuclear safety specifications (1) for handling J-slugs have previously been reviewed. These specifications provided information for the storage of loaded 100-hole shipping containers and loaded 66-hole wood cart pallets in certain arrays. Storage of J-slugs in J-Material Crates conforming to Drawing No. H-3-6217 had not been reviewed for the previous specifications. It has become desirable to provide specifications for J-slug storage in these crates as well as make additions to the present specifications on the storage of these enriched slugs in shipping containers and pallets. The results of this study pertaining to arrays of J-slugs in shipping containers and pallets will be incorporated as an addition to the present specifications for handling J-slugs.

The purpose of this report is to present results of an experimental program directed toward determining the degree of protection offered by the Panellit protection system to flow losses to a single process tube containing I & E fuel elements in K reactor.

This Program detailed in this report is related to the Product Development, Palmolive, and Non-Production Fuels Programs under New and Special Products and Processes Category where the prime separations plants supply raw materials or processing support of these other programs. Likewise, Increased Plant Return Program items affecting the Purex, Redox, and UO{sub 3} Plants must be integrated with the Continuity of Operations Program. Since the primary separations plants feed the 234-5 Facility, the 234-5 Program is also related to Continutiy of Operation.

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This paper summarizes the proposed construction of the Priest Rapids Dam on the Columbia River by the Atomic Energy Commission. Power generation to the Hanford Works and flood control for the surrounding area is the main goal for the construction of the dam. The summary covers the feasibility of the dam from its design, operation, benefits, security, drawbacks, etc.

This document provides the conclusions and recommendations of the study of purging of surface condenser tubes. (FI)

Estimated water flow rates at H Pile for various postulated conditions are given. The conditions under which the data are valid are as follows: (1) the estimated accuracy of the tube flow rates is {+-}5%, and of pile flow rates {+-}7%; (2) the pile flow rates are based upon the present tube geometry, orifice zone pattern and total flow at H Pile; (3) the flow rates should be increased about 2% if film-free slugs and tubes are considered; and (4) flow rates for enlarged fittings are based upon fittings similar in shape to the present H Pile fittings. The maximum tube flow rates for the DR Pile would be about 2% greater than those given in the table for present tube fittings. For enlarged fittings, the rates for DR Pile tube would be the same as those given for H Pile tubes. The ultimate permissible flow will depend, in part, upon limitations on maximum cross-header pressure and maximum tube inlet pressure, and upon the instrumentation necessary to detect abnormal tube flow conditions.

This test is designed to accomplish two primary objectives: (1) to attempt to verify ex-reactor corrosion data which indicated improved corrosion resistance of cast blank X-8001 alloy material compared with wrought blank, and (2) to attempt to verify the resistance to groove pitting type of corrosion attack previously observed on M-388 components. Ex-reactor tests of cast blank M-388 alloy in autoclaves using water as the corrosive media up to 360 C, and in flow loops up to 120 C have indicated that the corrosion resistance of the cast blank material is equivalent to, and probably superior to the corrosion resistance of wrought blank material. Metallographic examination of this material indicated a more uniform nickel dispersion in the aluminum as a probable explanation of this performance. The sporadic occurrence of severe groove pitting has seriously challenged the use of X-8001 nickel aluminum alloy as a fuel element cladding material. Although the actual cause of the groove pitting has not been determined, non-uniform dispersion of the nickel in the alloy is suspected. The cause of the non-uniform nickel dispersion or segregation has been located and virtually eliminated by removal of additional aluminum (scalping) from the ingots prior to fabrication of the components.

The purpose of this report is to provide scope and justification for the installation of two new 16,500 gpm, 150-foot head pumps in the 181-C building in order to furnish sufficient additional water to increase production at 105-B and to supply the entire normal export demand from B Area. A minimum of 11,000 gpm will be required to be transferred from the 183-C reservoir to the 183-B clearwell via the cross-tie line during the adverse turbidity period when the I&E program is in effect at 105-B. It is contemplated to transfer 15,000 to 20,000 gpm so as to provide the necessary water for this increased flow at 105-B and to reduce the flow through the existing 183-B filters. It is apparent that the pumping capacity at 181-C is not adequate to supply this extra water at 183-C unless all export pumps are used to pump water to 183-C. If this increased demand were met by using the export pumps, the 100-D Area would have to supply most of the export demand to the 200 Areas which is anticipated to be 12,000 to 15,500 gpm. After the new expected I&E flows are achieved at 105-D and 105-DR, D Area will have …

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The liquid high-level radioactive wastes from the separations plant are stored in large underground tanks where radioactive decay of the fission products in storage gives off heat. In the case of the 241-A underground storage tank farm, for Purex wastes, advantage is taken of this heat to self-concentrate the wastes. The present practice is to permit boiling and concentration in the storage tanks. The vapors given off from the boiling wastes are collected in a vapor header and passed through a deentrainment vessel and on to two contact condensers where the vapors are condensed and intermixed with waste cooling water. Samples taken of the waste vapors have shown a considerable amount of cesium{sup 137} present as well as other types of radioactive material carry over from the waste tanks. For this reason the contact condenser effluent is discharged to an underground crib 216-A-8. Underground disposal of the increasing volume of condenser effluent as larger waste volumes are accumulated in the underground tanks presents a critical problem which is further complicated by the desirability to transfer the condensate waste to new disposal facilities near the 200 West area. The intent of this report is to present the scope of the facilities …

This is a personal letter to Kenneth Davis, AEC, concerning ORNL reactor activities. Topics covered include: HRP status; the gas-cooled system; molten fluorides; the ANP project; and maritime work.

This report provides data as regards safety experience of the Hanford Production Reactors.

An X-8001 clad, I & E natural uranium fuel element irradiated in tube 2762D to 886 MWD/T was discharged in February 1959 and sent to Radiometallurgy Laboratory for examination at the request of Irradiation Processing Department. After discharging tube 2762D which was loaded with X-8001 clad fuel elements, a fuel element (KL018D) was observed to be very badly pitted. Visual and photographic inspection revealed the pits had penetrated into the AlSi layer. The pitting appeared as the result of erosion-corrosion as there was no evidence for intergranular or transgranular corrosion and no mechanical deformation. Chemical analysis for %Ni and Fe indicated normal concentrations.

The primary purpose of this report is to present cost data associated with the recent construction of biological shields at Hanford. These data are useful for analyzing shields which have been built during the past four years and for ascertaining ways to improve future designs. Specifically, the objectives of this study are to: compile and analyze cost data associated with the construction of the high density concrete shields at 105-K and the steel-masonite shields at 105-C; and determine unit costs for erecting steel forms at Hanford and for filling them with high density concrete.

A direct means of monitoring and indicating the neutron flux in a reactor core is required to maintain neutron-flux equilibrium and to eliminate hot spots, flux peaking and flux oscillations. This report presents operating specification for an in-core flux monitor. The specifications are based upon the recognized requirements and operating characteristics for Hanford reactors and are presents as the criteria for development, application, and evaluation of prototype in-core flux monitor systems.

Reductions in irradiation costs and increases in production rate have provided a continuing incentive for more efficient operation of the Hanford Piles. These improvements have been obtained by means of higher specific powers, greater water flow rates, and better water utilization. However, the extent of the improvements which can be made in this manner may be limited by such factors as tube and slug corrosion, slug stability, and graphite damage rates at higher operating temperatures. Water purification and pumping costs are also factors to be considered. New slug designs are being developed which may be capable of much higher specific power operation. Higher graphite temperatures may also prove feasible, but the water plant performance limitations for the present single pass cooling systems may prove much more expensive to relieve. The use of recirculating cooling water as a means of attaining higher temperature, higher power operation has received preliminary study. A preliminary economic evaluation of an operating area equipped for recirculation versus single pass cooling is needed to better determine the relative merits of the two cooling methods. This report presents the results of such an evaluation and discusses the direction of future development work in the field of pile cooling.

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Preliminary experiments have been made to determine the vapor pressure of lanthanum fluoride between 0.001 and 0.1 millimeter of mercury by means of the Knudsen effusion method. A tantalum cell for this purpose is described. Only preliminary results were obtained and they were all in a relatively high pressure region. However, a plot of the vapor pressure against the reciprocal of absolute temperature approximates a straight line such as would be predicted from theoretical considerations.