Nickel plated aluminum was considered as a jacketing material for nuclear fuel elements as early as 1954, and both static and dynamic corrosion tests were carried out by Argonne National Laboratories and by Atomic Energy of Canada Ltd., employing demineralized water at temperatures of from 260 to 316{degree}C. Results generally indicated that the nickel had excellent corrosion resistance; however, difficulties were experienced in achieving satisfactory continuity and adhesion of the plate; subsequent work emphasized Ni-Aluminum alloy development. At Hanford, our earliest experience employed Ni plate on aluminum-jacketed fuel elements primarily to minimize mechanical damage to the jacket surface during an irradiation test. The appearance of these fuel elements after discharge suggested that the nickel plate might also be a highly satisfactory coating for corrosion and abrasion resistance. Incentives were manifold, including reducing the incidence of in-reactor fuel element failures and permitting reduction of the aluminum jacket thickness with a concomitant increase in space available for uranium or for cooling water passage. A program has been carried out for the past three years aimed at determining various methods of employing nickel plated aluminum jacket material and testing the capabilities of high quality commercially adequate plate. Almost exclusively chemically deposited plate has …

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 Highway Commission to refuse permits to place gas pipelines on highway right of ways.

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The uranium OD increased about 20 mils in 97W-17 and 12 mils in 96W-18. The ID did not change. Remaining cladding thicknesses of 97W-17 were 37 mils minimum and 41 mils maximum external, and 42 mils minimum and 44 mils maximum internal, excluding the A{sub l}-S{sub i}. Remaining cladding thicknesses of 96W-18 were 35 mils minimum and 45 mils maximum external, and 36 mils minimum and 45 mils maximum internal, exclusive of A{sub l}-S{sub i}. Metallographic examination disclosed small grains to a depth of about 10 mils on the internal surface of the uranium in both elements. The spire bond in 97W-17 was cracked completely around the spire.

A brief discussion is given of the long-term stability of particle motions through periodic focusing structures containing lumped nonlinear elements. A method is presented whereby one can specify the nonlinear elements in such a way as to generate a variety of structures in which the motion has long-term stability.

A brief discussion is given of the long-term stability of particle motions through periodic focusing structures containing lumped nonlinear elements. A method is presented whereby one can specify the nonlinear elements in such a way as to generate a variety of structures in which the motion has long-term stability.

Currently the B, C, KE and KW reactors are in operation. The B and C reactors are operating to produce 12% Pu-240 in both the E metal (0.95) and natural loadings. Some columns will be taken to 15% Pu 240 on a test basis. Production of 12% Pu-240 will result in exposures of 1400 MWD/ton on natural metal and 2,000 MWD/Ton on E metal. Currently exposures are such that 10 1/2% Pu-240 has been achieved. Some control problems and temperature cycling have been encountered with this mode of operation. Both K reactors are on enriched-depleted loads. The depleted metal is scheduled for irradiation to produce 27-30% Pu-240 (about 3,000 MWD/Ton; 15 months residence) and is currently at 30% of goal. The E metal drivers (0.95) will be discharged at weapons grade Pu exposures. The relatively small quantity of natural uranium in the K reactors will be exposed to produce 12% Pu-240.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the materials being irradiated, awaiting disposition and material shipped during the report period. The data are given in table form. Information consists of: TISR No.; request number; target material; piece number; operating time; CMK absorbed; charge date; location; exposure to date-NVT; discharge, date and time; and shipping date.

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This report is about the Classical Dynamics of Triatomic Systems which is divided into three parts.

Technical report. From Abstract : "Reaction of NbBr5 and niobium metal in a sealed tube under a temperature gradient from 410° to 350° gave NbBr4 in good yields. However, an increase in the higher temperature from 410° to 450° was sufficient to eliminate NbBr4 as a product and cause deposition of a lower bromide."

Technical report. From Abstract : "The necessary conditions for preparation of TaBr4 and TaI4 by reduction of the pentahalides with tantalum or aluminum metal in a sealed tube under a controlled temperature gradient have been demonstrated."

From Abstract: "The data for gummed film fallout measurements through December 1959 are reported. The bulk of the report consists of summary tables for each gummed film station listing the monthly estimates of strontium 90 deposition and infinity gamma dose."

Human iron metabolism has been extensively studied in the past twenty-five years with the radioisotopes iron⁵⁵ and iron⁵⁹. Before the availability of the whole body counter, however, iron absorption studies were performed by the indirect methods of fecal assay of unabsorbed radioiron, and estimation of red cell incorporation of absorbed tracer. The few long-term excretion studies performed required numerous assumptions, since human iron excretion was less well understood. Whole body counting provides a simple and accurate method of measuring the total body retention of administrative tracer iron⁵⁹, thus making absorption and subsequent excretion determinations possible with a single radioiron study. The energetic gamma emissions of iron⁵⁹ permit ready external detection with small quantities of isotope, Normal radioiron distribution is uniform throughout the circulating red cell mass and thus minimize geometry influences on the counting efficiency, 0nly the 45.1 day half-life of iron⁵⁹ limits long term iron turnover studies. Measurements of iron⁵⁹ absorption and long-term body turnover have been under way at Brookhaven National Laboratory for over two years. The present paper outlines some of the results of these studies, and discusses some implications of the method.

This statistical analysis examines volume increase data from PTA-040. The purpose of this analysis is to compare four 1.25 enriched uranium core alloys (Standard, British, High Silicon, and Modified British), two heat treatments (Induction and Salt Bath), and the alloy-treatment interaction. The four core alloys were each processed using the two treatments and then canned as 5.540-in. AlSi fuel elements. Test pieces were charged in 16 tubes with 40 pieces per tube. The eight fuel types (4 alloys {times} 2 treatments) were arranged in a series of Latin squares in the test tubes to eliminate the effect of position and tube. A comparison of volume increase was deemed worthwhile after analyzing PTA-040 with regard to fuel element distortion. Volume increases in the present analysis were calculated by H.D. Huber using OD and ID measurements taken at C-Basin with consideration for can wall corrosion and geometric distortion. these volume increase calculations were not completely substantiated, since a thorough check with water displacement measurements at the Radiometallurgical Laboratory was not possible. Despite this fact, the present analysis was continued since a good correlation between the volume increase calculations and element exposure was observed.

From time to time, in discussion of possible naval-based nuclear ramjet missile systems, a question arises concerning whether or not a particular reactor would or would fall within the `Tory II-C Technology`. Such a question is meaningless unless a definition is furnished. This report provides such a definition.