This is a geological report on the uranium mine in Hack's Canyon, Mohave County, Arizona.

A report discussing a method of computing the critical mass of U₂₃₅ contained in a water solution confined to a spherical core and surrounded by an infinite water tamper, a modification of said method in which the effect of the resonance fission and absorption is taken into account, and physical constants required to calculate the critical mass using these methods.

Abstract: "Computations have been made of the total beta activity of the fission products arising from the slow neutron fission of U-235. A curve is given exhibiting the activity the activity per unit fission, for time intervals after fission ranging from 0.01 second to 10 years. This influence function is compared with some published experimental data and with the statistical curve of Way and Wigner. A curve facilitates estimation of the activity in the particular case where the fission rate has been constant throughout a known time interval. Finally, an influence function for the particular group of fission products consisting of complete and partial chains having volatile first members is given. This report is based on studies conducted for the Atomic Energy Commission under Contract AT-11-1-GEN-8."

This note is concerned with the numerical integration of the integrals of the form anti l*SUB infinity/*SUP infinity/ f(x) *phi/(x) dx is "smooth."

In connection with the study of aqueous-tributyIphosphate (TBP) systems, the study of the interactions of various diluents with the TBP has been extended. The diluents used were mineral oil, Amsco 125-90W, dodecane, n-hexane, cyclohexane, benzene, n-octyl bromide, carbon tetrachloride, chloroform and pentachloroethane. The solubility of TBP in water from solutions of these diluents and the solubility of water in the organic phase was determined. For the paraffin hydrocarbons as diluents the solubility of TBP in water was found to increase with increasing molal volume of the diluent. No evidence for the formation of TBP-water complex of simple mole ration was found.

"The Atomic energy Commission has undertaken a development program to provide the technology needed for the evaluation and economic design of nuclear power plants. This program is to be carried out during the next five years at several national laboratories and industrial organizations. The Sodium Graphite Reactor (the SGR) is one of those to be investigated and experimentally tested as part of this 5-year effort. The program on the SGR is intended to expand our area of information covering sodium-graphite technology, experimentally demonstrate the feasibility of this reactor complex and extend its performance limits, and apply in information developed to designs suitable for the full-scale nuclear power plant. As a principal part of this program, a Sodium Reactor Experiment (the SRE) is to be constructed and operated; it will be the major experimental facility in which the performance of this reactor will be studied and new technological advances tested. This report continues an earlier series 2-7 in which previous work on the SGR and the SRE has been described. In this report, the progress on the program is described in two main sections. Section A is devoted to work relating to the general technology of Sodium Graphite Reactors, and to …

This technical report includes (1) World-wide Network (Maps). (2) Fallout of Sr90 at selected sites during June and July. (3) Comparison of Sr90 collection by gummed paper and pot on the roof of the New York Operations Office March through July. (4) Sr90 contamination of cow's milk in Metropolitan New York. (5) Sr90 content of the upper air prior to Castle. (6) Sr90 contamination of pooled fetal bones collected during June from the Metropolitan Area. (7) Sr90 contamination of water supply in the Metropolitan Area June and July.

Report that generally describes sodium cooled fast reactors, the features and facilities of such a reactor proposed by Atomic Power Development Associates, and then its safety and siting considerations.

Twelve neutron activation analyses for naturally occurring technetium-98 were performed. Positive results were obtained in ten cases. Precautions were taken to avoid interference by molybdenum and technetium-99. the cross section for the reaction [formula] as found to be equal to 4 +- 2 mb for the neutron spectrum of the vertical thimbles of the Argonne CP-5 reactor. The chemical state of molybdenum (VI) in basic solution was studied by an anion-exchange technique. Evidence was obtained for the existence of polymeric species at pH-values up to 14. Preliminary work on the stability of Domax-1 anion exchange resin in perchlorate media indicates rapid deterioration even at 0.2F ClO4-.

A report which studies the feasibility of measuring the thermal conductivity and electrical resistivity of irradiated uranium rods clad with Zircaloy 2, with NaK as the heat-transfer medium.

Report describing "the startup operation of a batch production facility for separating and purifying barium-140 from short-cooled MTR fuel" (p. 3).

A report about equipment constructed and methods being explored to determine the effect of irradiation on the thermal and electrical conductivities of encapsulated uranium and on the thermal conductivity of UO2.

From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker."

From abstract: "The design, fabrication, and irradiation results are described for a 0.028 inch thick 304 stainless clad fuel element (SH-4B) exposed in the Vallecitos Boiling Water Reactor loop under superheat conditions."

Abstract: This technical report describes the Martin Co. PM-1-M-2 test element and analyzes the potential hazard incurred by its inclusion in the SM-1 Core II. A nuclear analysis develops power distributions and reactivity effects. Hydraulic and thermal analyses develop anticipated burnout heat flux ratios. An evaluation of the risk involved with the inclusion of this element is presented. In view of the narrow margin by which the PM-1-M-2 test element meets the minimum burnout ratios as defined by Alco Products, Inc., it is recommended that if time permits that critical facility design verification be accomplished. The PM-1-M-2 test element meets the minimum requirements for insertion in SM-1 Core II and in view of the importance of this element to the PM-1 and PM-3A program, should be considered for insertion.

"Uranium and zirconium were bonded by melting the two metals in contact with one another in a bimetallic casting process. Tensile tests of specimens containing the original zone of interface between the two metals showed that all failures were at locations other than the interface. The coefficients obtained for diffusion between molten uranium and molten zirconium varied from 2.13 cm squared per day at 3,380 degrees F. to 9.17 cm squared per day at 3,510 degrees F. the activation energy for the diffusion process was calculated to be 182,000 calories per gram mole."

Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.

Technical report describing that the pressure drops along 3/4-inch, 1-inch, and 1-1/4 inch straight pipes and across three contraction-expansion inserts in a 1-inch pipe have been measured under both single- and two-phase flow conditions. Pressure was varied from 600 to 1400 psia, flow from 0.25 x 10(6) to 1.66 x 10(6) lb/hr ft, and quality from zero to 90 percent. The single-phase pipe friction factor agrees with the Moody value for smooth pipe. The two-phase friction for horizontal flow shows no size effect in the range of pipe sizes from 3/4 inch to 1-1/4 inch. The values lie below the Martinelli curve at the lower qualities (x<0.6), but at high qualities tend to be above the Martinelli curve. The single-phase loss coefficient for the three contraction-expansion inserts show very little Reynolds number effect in the range of channel Reynolds numbers from 3 x 10(4) to 5 x 10(5). The two-phase data for insert number 1 has not yet been reduced. The two-phase loss for insert numbers 2 and 3 lies generally below the loss prediction based on a homogeneous flow model. The two-phase loss for insert number 2 shows excellent agreement with the corresponding loss for the S-1 insert in …

Report that describes Hanford Laboratories' overall N-Reactor plant simulation model and its use to study the characteristics of the plant, plant operational procedures, and the effects of plant, operator, and control system malfunctions.

The results of a high-sensitivity, aerial gamma-ray spectrometer and magnetometer survey of the Holbrook two degree quadrangle, Arizona are presented. Instrumentation and methods are described in Volume 1 of this final report. The work was done by Carson Helicopters, Inc., and Carson Helicopters was assisted in the interpretation by International Exploration, Inc. The work was performed for the US Department of Energy - National Uranium Resource Evaluation (NURE) program. Analysis of this radiometric data yielded 260 statistically significant eU anomalies. Of this number, forty-four were considered to be of sufficient strength to warrant further investigation. These preferred anomalies are separated into groups having some geologic aspect in common.