Summary of the trumpeter swan, including geographic distribution, habitats for breeding and wintering, life cycle, nesting, food, limiting factors, longevity, population dynamics, and human management.

Potential cladding materials for a flat-plate fuel element containing a dispersion of UC or UC/sub 2/ in U--15 wt.% Mo alloy were surveyed on the bases of compatibility with the fissile compounds, matrix material, protective cover materials, and liquid sodium as well as the feasibility of fabricating fuel plates by roll cladding. Radiative-capture cross sections, thermodynamic data, eutectic and intermediate compound formation, mechanical properties, and corrosion by 1000 tained F Na are reported for austenitic stainless steels, chromium, nickel, niobium, molybdenum, tantalum, vanadium, and zirconium. It was recommended that "A" nickel (molybdenum barrier), Zr-3 wt.% Al. Nb--2 wt.% Cr, and Fansteel 82 be relected for investigation. (auth)

This document details activities of the Fuels Preparation Department during the month of March 1960. (FI)

A calculation was made to determine the fuel plate heat fluxes resulting from after shutdown fission product heating. Fission product source strengths were obtained via the IBM Internuc code. Slab geometry was assumed. The results indicated that the maximum heat flux would occur slightly inboard of the center of the fuel annulus, with the heat flux at the inner annulus radius running about 8% below the maximum, and the outer radius heat flux 10% below the maximum. For decay times of 1.0, 10, 10/sup 2/, 10/sup 3/, 10/sup 4/, and 10/sup 5/ seconds the maximum calculated fuel plate heat fluxes were 42.0, 30.0, 18.0, 9.5, 4.0, and 1.3 x 10/sup 3/ Btu/hr-ft/sup 2/, respectively. The core coolant gamma heating rate during reactor operation was also calculated using the same techniques, but including the fission and capture gamma sources. Average coolant gamma heat generation rate was about 33 watts/cc at the start of the fuel cycle, and 57 watts/cc after the fission products built up. (auth)

From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."

Abstract. An inexpensive method for detection of dust-loaded high efficiency filters is described. Air flow is continuously indicated by elementary pitot tubes and plastic rotameters. Accuracy obtained is within +- 15%. Information as to construction, installation, and use is presented.

A program consisting of two related phases is described Ia Phase I, a study was made to find the relationship between the amount and nature of radioactivity, particle size distribution, and weight of particulate matter present in the lower troposphere. Emphasis was placed on the distribu tion of strontium-90 and total beta activity. Results of a limited number of analyses indicate that strontium-90 and total beta activity is associated primarily with particles below approximately 0.1 micron diameter. Phase II consisted of experimental studies on scavenging of solid particulate matter by water droplets. It was found that water vapor gradient around a condensing droplet promotes scavenging of particles of 1.3 micron and 0.3 micron diameters. The effect of water vapor gradient around an evaporating droplet is not well defined. (auth)

This is the summary report on the ARF Project C 127, entitled "Preliminary Studies Related to Radioactive Fallout", covering the period from April 1, 1959, to April 29, 1960.

Changes in operation and corresponding changes in the reactivity status of Hanford reactors are the result of a continuing effort to improve operating efficiency. Trends data related to these changes in operation and reactivity have been published previously for the periods from 1950 through 1958. The purpose of this report is to include trends data for 1959. Bar graphs in the first part of the report show yearly averages of selected data, and tables in the last part of the report show maximum, average, and minimum values. This document presents trends data for B, D, DR, and F reactors while a second document, HW-64932, presents trends data for C, H, KE, and KW reactors. Data included in past years which have not been included in this report are trends in pile power level at shutdown omitted due to a security status change regarding power levels, and number of temporary poison columns per startup omitted due to virtual elimination of temporary poison startups at B, D, DR, and F Reactors; added were potential non-equilibrium gains and potential equilibrium gains. Notice that all reactivity values are listed in the unit per cent excess k.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether or not a charter amendment which will result in an insurance company issuing fractional shares of stock can be approved.

Pressurized water nuclear reactors may be designed based upon either of two concepts: (1) pressure vessel, wherein the entire core is placed in a large, high strength fuel channels within a low pressure container. The Plutonium Recycle Test Reactor is a pressure tube type reactor. Selection of this basic type of pressurized water reactor depended to an appreciable extent upon the availability of suitable pressure tubing.

It is the purpose of this document to provide assistance to the Manufacturing Section personnel in determining their future operating plans. In general, the inter-relationship of such engineering parameters as flow, reactor orificing, rupture performance, etc. has been considered. The effect of these engineering parameters are summed up in our recommendations for {open_quotes}Operating Plans{close_quotes} shown graphically in this document. It is to be emphasized that these plans do not reflect operational considerations which may modify the desirability of the indicated level increases nor has allowance been made for ability of the indicated level increases nor has allowance been made for major projects, major maintenance outages, or major changes in pile loadings. Many factor, which only Manufacturing personnel are capable of evaluating, may make it desirable to operate below or above these {open_quotes}Operating Plans.{close_quotes} These {open_quotes}plans{close_quotes} are based on incremental metal cost and burnout cost estimates obtained recently from L. W. Lang. A change in these assumed costs would require a revision to be made to these {open_quotes}plans.{close_quotes} It is also to be noted that many of the engineering parameters and basic assumptions which have been factored into these {open_quotes}plans{close_quotes} are subject to continual re-evaluation and revision. Thus, in a strict …

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From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.

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This bibliography contains 94 references on metal hydrides, with particular emphasis placed on the hydrides of titanium, yttrium, and zirconium. The bibliography covers the period 1955 through 1959. The references are arranged alphabetically by title. Sources used in compiling this bibliography are: Applied Science and Technology Index, Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program, Classified and Unclassified Parts, Industrial Arts Index, Internal Card Catalog, Monthly List of Bibliographies in the Atomic Energy Program, U.S.A.E.C. Technical Information Service Extension, Nuclear Science Abstracts.

Calcination of liquid radioactive wastes, the process of converting metal nitrates and sulfates to oxides by heat, is under development at Hanford as a means of reducing these liquids to a dry powder or solid which can be stored safely. Radiant-heat spray calcination, one of the methods under study, was first investigated at the Oak Ridge K-25 Plant (1) as a possible method of calcining uranyl nitrate to uranium trioxide. The process has also been under extensive development at the Pulp and Paper Research Institute of Canada (2) and is designated by them as the Atomized Suspension Technique.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Would a practitioner who fills prescriptions be required to have a permit from the Texas State Board of Pharmacy and can the practitioner authorize his nurse or aide to fill and dispense prescriptions.

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This report discuss the design of the Plutonium Reclamation Facility the capacity of which will be 300 kilograms per month or 3600 kilograms per year or plutonium. The subject facility, as the name implies, must be extremely flexible in its ability to handle a wide variety of feed materials. The new facility will be operating on a three-shift day, five-day week, 40-week year with an overall efficiency of 75 percent; twelve weeks per year will be required for ``turnaround`` time to enable campaign operation for segregation of feed plutonium by isotopic content.

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The intent of this document is to establish criteria for equipment for: Receiving, handling and component inspection; miscellaneous handling and storage; final inspection; and finished storage in the new fuel cladding facility.

As power levels have been raised at the K Reactors, the graphite temperature limit has caused significant production losses. These losses have come from three sources: (1) Occasions vhen pile power was directly limited because the graphite temperatures were limiting; (2) Losses in ECT because control rod movements to control graphite temperatures are not necessarily the best rod movements for pile, flattening; and (3) Losses due to lack of control in the final stages of an operating period because COp could not be used as a means of controlling long-term reactivity gains. This document attempts to establish the magnitude of these losses and shows the justification for increasing the graphite temperature limit. The data which is presented here is based upon operating data from December, 1959) through March, 1960, at KW. The results apply to KE as well as KW.

Facilities shall be provided in the 221-U Building for storing the metal solution product of the dissolution step in existing tankage from U, T, and B Plants until a reprocessing campaign is scheduled through Redox. This section shall provide a sampling tank for fuel accountability sampling and a pump tank from which the solution will be pumped via a cross-country pipeline to Redox for further processing.