The following report records the use of the double-precision THEMIS code to integrate the motion of Mars and Venus in order to obtain a complete set of rectangular equatorial coordinates over the interval 1600-2000 A.D.

Technical report was prepared by the Health and Safety Laboratory (HASL) with the objective of presenting a current picture of the Strontium Program. Abstract: Strontium 90 levels in fallout, milk, canned fish and tap water are summarized for data available up to April 5, 1958. Original data submitted during the month of March are included as an appendix. Data are presented to show the amount of Strontium 90 in fallout at sampling stations within and outside the United States.

Preface; Subsequent to the analysis in the body of this report metallurgical developments indicated that it would not be feasible to build the APPR-1 Core II with the increased boron loading specified herein. At the time of the issuance of this report the Core II boron loading is to be the same as that for Core I. At the time of procurement of the core in the fall, if metallurgical developments warrant, the increased boron loading will be employed. The loading discussed in the body of the report and the first three appendices is that designed to meet the specifications outlined in the introduction. Appendix IV discusses changes in the loading to account for the various methods of employing boron.

Abstract: A study has been made of the radiochemical composition and the specific activity of insoluble corrosion products (crud) removed from the primary system of the APPR-1. This report presents the results of analysis of twelve crud samples collected during the interval from September 3, 1957 to December 1, 1957. The samples were radiochemically analyzed for long-lived gamma emitting nuclides only. Data are presented on the measured values of the specific activity of crud, the ratios of the nuclide specific activities, and the concentration of crud (crud level) in the circulating primary water. Also included in data, based on the analysis of a single sample, comparing the specific activity of the deposited and circulating corrosion products.

American Mining Congress 9/24/58. Summary. Results of a recent underground test by the Atomic Energy Commission indicate possible applications of nuclear energy in mining and allied industries. The safety, feasibility and economy of nuclear detonations have been demonstrated and further considerations reveal a number of interesting situations which might lend themselves to the use of this new type of explosive. Possible applications include stripping, crushing, quarrying, and the exploitation of petroleum products, water resources, and low-grade ore deposits. The heat reservoir created by the explosion might be used to produce steam (and power) to promote the recovery of oil or tar. The mining industry can supply know-how and test sites for future tests.

The Aircraft Reactor Experiment (ARE)was successfully concluded in November of 1954, and a detailed report of the operation was published the following year. At that time it was thought that an extensive examination of the reactor and system components after disassembly was warranted. It was realized, of course, that the level of radioactivity of the components would necessitate extensive delays in the examinations. Since examination of a few critical ARE samples showed nothing unexpected, much of the planned hot-cell inspection was postponed and complete examination of all but a few specimens was indefinitely suspended. The few examinations that were completed are described in this report, along with a description of the disassembly of the ARE system. Diagrams of the fuel system, sodium system, and off-gas system are presented in Figs. 1, 2, and 3 for reference use in visualizing the disassembly process.

The APPR-1 is a pressurized water reactor having a low specific heat fuel and a water primary coolant. The primary coolant loop delivers heat from the reactor to the steam generator. The secondary water in the steam generator is converted to steam and then taken to the turbine to drive an electrical generator. The simulation of this system is broken down into three primary areas: the neutron kinetics in the reactor which are necessary to generate the primary power function, the heat transfer in the reactor, and the heat transfer in the steam generator.