Monthly magazine discussing natural resources, parks, hunting and fishing, and other information related to the outdoors in Texas.

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1950, activities, ideals, finance, public relations, organizational leadership, and other information about scouting programs.

As a result of unreported information, it was suspected by some people that a change in dimension was experienced by 2S Aluminum due to a sudden change in neutron flux impinging on it. This was thought to be of the order of 500 microinches per inch in magnitude. Such an effect, if present, could help explain some of the creep phenomena reported lately (i.e. change in creep rate due to cyclotron bombardment.)

It is the purpose of this report to present a quantitative picture of the overall waste problems at the presently operating major A.E.C. sites. Presented herewith are data on the volumes and radioactive concentrations of the wastes handled and effluents discharged, available tankage and processes flow sheets from each site.

Abstract: An appraisal is made of the radiologic hazard created by a 1000-ft. high air burst of a nominal sized nuclear bomb. Three sets of graphs are included which show the relations between dose rate (milliroentgens per hour), time post-shot, and distance from Ground Zero for a soil having given constituents. Estimates are given for fall-out activity (gamma) for distances up to about 200 miles from Ground Zero immediately after fall-out. It is pointed out that the radiologic hazard due to fall-out in the example cited is insignificant; further, that the radiologic hazard from similar nuclear bombs bursting at different heights above the ground will vary to a considerable extent.

Cost estimates for two types of Th producing plants are offered. One utilizes Th(NO3)4 as raw material, the other uses monazite sand. Final processing schemes and plant designs are not fixed, so the estimates represent maximum costs. Recommendations for research and development of Th producing methods are given.

Report documenting the suitability of Virginia for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.

Report documenting the suitability of Alabama for plant locations to produce synthetic liquid fuels, based on raw materials, coal, natural gas, and oil-impregnated strippable deposits.

Report documenting the suitability of California for plant locations to produce synthetic liquid fuels, based on raw materials such as oil-impregnated strippable deposits, coal, and natural gas.

This report describes the Temple Mountain district in Utah, specifically four Shinarump-capped areas that are recommended for ore mining.

A report regarding Preliminary reserve statement 13, reserve blocks D, E, F, and G, Outlaw Mesa, Mesa County, Colorado.

Discussing recommendations for wagon drilling in the Temple Mountain District, Utah

Monthly report of the U.S. Geological Survey's trace element investigations including an outline of field work, laboratory work, and staff activities that have been completed or are in process.

The trip into the Henry Mountains Area used to examine the Reo Hunt's deposit s of uranium and vanadium.

Report on pegmatites of the Van Horn Mountains and discussing the economic possibilities of mining in the area.

Calculations presented were done to determine what maximum temperature gradients and stresses would be in typical designs of flat thorium plates, 100 mils thick and coolled on both sides by NaK.

Calculations indicative of the power loss for 75 in.radius gap splitters are given.

Technical report outlining the fabrication of twenty-five fuel assemblies and three shim-safety rod fuel sections for use in the Materials Resting Reactor Mock-Up Critical Experiments. Results show that two of the assemblies exceeded tolerance in a few of the key dimensions, but were considered acceptable and as a consequence, production was carried out with no rejects. [From Abstract]

Technical report and preliminary design calculations describing a type of liquid fuel reactor adaptable for production or breeding on a U-233 cycle based on data at Brookhaven National Laboratory. Describes design calculations for generating significant amounts of power and neutrons by use of uranium-bismuth solutions with fused salts in the reactor system.

At the 100{endash}300 Areas Steering Committee meeting of March 7, following a general discussion of pile level increases, the chairman pointed out the necessity for programming tentative level objectives as far in advance as possible so that the P and Service Divisions may proceed with the planning details incidental to making the necessary equipment changes. A committee consisting of Mr. Warren and Mr. McCullough was appointed to prepare an outline of pile level objectives and to determine the major equipment changes involved in attaining such levels.

This is a progress report of the production reactors on the Hanford Reservation for the month of March 1951. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

The {open_quotes}O{close_quotes} ring seal has been proposed to replace the van stone flange and the bellows thermal expansion assembly currently used on the existing Hanford piles to achieve water and gas seals, respectively. Possible advantages of the {open_quotes}O{close_quotes} ring seal are: (1) simplification of component parts and elimination of van stone corrosion; (2) simplification of maintenance; (3) lower costs of initial erection; (4) increased strength. This test supplements Test Project No. 27 (a preliminary thermal cycling test) in applying the {open_quotes}O{close_quotes} ring seal assembly to actual pile operating conditions.

This is the monthly 100 areas technical activities report from the engineering division for the month of March 1951. It reports on engineering activities related directly to the different production reactors, and gives progress reports on various engineering projects which are in development by the engineering group.

Preliminary meetings on coring of the graphite have been held with interested parties of the Technical and Production Divisions at which time the advantages and problems of coring were discussed. The advantages and the problems which must be surmounted in order to core have been presented to the working committee. A study of the means of accomplishing coring has been made considering only the central and maximum fringe coring. It is important that the minimum and maximum coring be established as soon as possible so that the coal coring pattern can be worked out and the design completed. From the studies that have been made thus far the 10 mil center core-60 mil fringe core appears to be the most favorable choice. The advantages and disadvantages of several possible coring combinations (central to fringe) are tabulated. The statements and graphs of temperatures made in this tabulation are based on the results of the analogue tests. The estimates of pile expansion resulting from various coring patterns are based on report HDC-1987 by R.K. Andersen. These results are summarized in Figures 1, 2, and 3. The results of the analysis which Technical plans to make on the DR graphite sample will be …