This, report, for October 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

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, Waggoner Carr, regarding a legal question submitted for clarification: Authority of a county official to close his office on Saturday without the consent and approval of the Commissioners Court.

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The objective of the production test detailed in this report is to continue a program started under Production Test IP-690; the major change is an increase in sample enrichment. The higher enrichment is required to increase the portion of the fuel element core which is molten. This test will provide data to correlate maximum fuel temperature with post-irradiation microstructure, and data that are required to study the kinetics of fuel redistribution during the time interval between insertion of the capsule, into a constant, established neutron flux, and the time at which a steady state equilibrium structure is reached. This information will permit calculation of high temperature heat transfer coefficients and their variation during initial stages of irradiation. A quantitative understanding of fuel relocation and the time required to reach equilibrium are needed for optimum design of ultra-high temperature fuel elements.

The development status and incentives for the hot the sizing process for reactor production fuels is reviewed and updated and economic justification for the process for four different case studies presented. Based on whether the end bonding step can be eliminated, payout periods of 1.2 to 1.7 years can be realized if the present AlSi process (two-shift, five-day week) is converted to hot die sizing for all reactors. For K-Reactor operation only, Payouts of 1.5 to 2.2 years can be realized by converting to hot the sizing. Should incentives exist for the present six-inch and eight-inch length fuel to longer models (10, 12 inch), costs would be increased in the AlSi process, which-would not be incurred in hot the sizing. This provides additional incentives for hot the sizing and reduces all payout periods by about 0.2 years.

The objective of this production test was to evaluate the irradiation behavior of N. Reactor fuel elements at conditions equivalent to or more severe than those expected in N Reactor. The thermocouple train consisted of eleven 23-inch NAE1 elements (replicas of an N Reactor fuel element) plus five 16-inch tubular perfs. The elements were enriched to 0.947 per cent. They were coextruded Zircaloy-2 jacketed self-supported uranium tubes concentrically nested one within the other to provide an element with four heat transfer surfaces and three coolant channels. For specific dimensions, refer to Production Test IP-477-A.

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This report documents various ways presidential elections have changed over the years and how it has effected voters in the country.

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This report has Books, pamphlets, Govt. publications and periodical articles

This report provides various sources of information on the states.

This report addresses the advancements in nuclear propulsion for aeronautical system.

New experimental data and literature data are utilized to determine the upper temperature of usefulness of zirconium alloys. Three basic engineering assumptions are used: (1) service life requirements are on the order of four years; (2) tubular fuel cladding for rod-type fuel is considered with a maximum wall thickness of 1.27 cm; and (3) heat fluxes are above 157 watts/cm/sup 2/. The interrelation of three basic factors, corrosion rate, corrosion embrittiement by hydrogen and oxygen, and strength are considered. An upper limit for an acceptable corrosion rate for a long-term service of 1 mg/dm/sup 2//day is set primarily by the effect of heat-transfer on corrosion. For the best alloys anticipated, this requirement (even without considering transient conditions) limits cladding surface temperatures to less than 540 C. Oxygen embrittiement of the alloy substrate by oxide film dissolution is not expected to be a limiting factor. Corrosion hydrogen embrittiement was studied in detail and found to limit acceptable service to cladding surface temperatures of less than 525 deg C for established experimental alloys. Hydrogen embrittlement may not be a limiting factor if alloys corrosion resistant enough to be acceptable above 600 deg C could be developed. Zirconium alloys designed for higher strength …

One-region buckling measurements that were made on a series of D/sub 2/O- moderated lattices of heavy uranium metal tubes in the Process Development Pile at Savannah River Laboratory are presented. The purposes of these measurements are to provide normalization points for lattice bucklings and to extend the study of natural uranium- D/sub 2/O systems. The dependence of buckiing on the moderator-to-fuel ratio is studied for two types of lattices.

Report issued by the National Bureau of Standards over studies conducted on the effects of mortar on the strength of masonry. Materials, methods, and results are presented and discussed. This report includes tables, illustrations, and photographs.

Plutonium-238 is an important heat producing isotope which is being used in increasing amounts as fuel in isotopic power generators for space, terrestrial, and oceanographic applications. Only within the past few years has the quantity of plutonium-238 become large enough to be considered as a potential nuclear criticality hazard. In order to insure nuclear criticality safety in the storage, processing and assembly of devices containing plutonium-238, a program has been established at Mound Laboratory to investigate the nuclear criticality properties of this isotope. This paper will summarize what is presently known about the criticality behavior of plutonium-238, what are some of the criticality controls used as Mound Laboratory for processing plutonium-238, and what measurements are needed in order to establish a Nuclear Safety Guide for Plutonium-238.

This report presents the details of the activities of Douglas United Nuclear at the Hanford site during the month of October 1967.

Abstract: New experimental data and literature data are utilized to determine the upper temperature of usefulness of zirconium alloys. Three basic engineering assumptions are used; (1) service life requirements are on the order of four years; (2) tubular fuel cladding for rod-type fuel is considered with a maximum wall thickness of 1.27 cm; and (3) heat fluxes are above 157 watts/cm. The inter-relation of three basic factors, corrosion rate, corrosion embrittlement by hydrogen and oxygen, and strength are considered. An upper limit for an acceptable corrosion rate for long-term service of 1 mg/dm/day is set primarily by the effect of heat-transfer on corrosion. For the best alloys anticipated, this requirement (even without considering transient conditions) limits cladding surface temperatures to less than 540 degree C. Oxygen embrittlement of the alloy substrate by oxide film dissolution is not expected to be a limiting factor. Corrosion hydrogen embrittlement was studied in detail and found to limit acceptable service to cladding surface temperatures of less than 525 degree C for established experimental alloys. Hydrogen embrittlement may not be a limiting factor if alloys corrosion resistant enough to be acceptable above 600 degree C could be developed. Zirconium alloys designed for high strength to …