Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."

Commonwealth Edison Company for the purpose of supplementing the license application for the Dresden Nuclear Power Station submits herewith Amendment No.1 to the portion of the Final Hazards Summary Report entitled Preliminary Hazards Summary Report.

"This bibliography is a list of references pertaining to factors affecting the motion of the artificial earth satellite. References are foreign and domestic literature."

Abstract: "Neutron nonelastic cross sections measured at different detector biases have been used to determine the cross sections for inelastically scattering 14 Mev neutrons into 9- to 14-Mev energy range. The cross section for producing these high energy neutrons, which may be attributed to direct interaction processes, is roughly 10% of the nonelastic cross section, for all elements. A comparison is made with data of Coon and co workers, who measured angular distributions for the same high-energy inelastically scattered-neutron group."

This is a bibliography referencing documents based on fused lithium salts within the years 1950-57.

Abstract: "Neutron nonelastic cross sections have been measured for 23 elements at 14 Mev, and for a selected set of these elements over the energy ranges 7 to 14 Mev and 21 to 29 Mev. Conventional sphere transmission techniques were used for the measurements. A comparison with optical model calculations of Bjorklund and Fernbach shows excellent agreement."

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 May 1, 1958. Original data submitted during the month of April 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.

The purpose of this report is to describe the nuclear power plant for the N.S. Savannah and the program in progress for the analysis of potential hazards associated with the operation of a nuclear merchant vessel. Particular emphasis is given to the safety features embodied both in the design and operation of the plant.

Delta-stabilized plutonium can be welded to itself or almost any other metal using the inert-gas metal-arc process. Equipment and procedures suitable for the welding of delta-stabilized plutonium under various conditions are described.

Introduction: This report is principally concerned with analysis of measurements taken on the APPR-1 core during the course of the extended Zero Power Experiments (ZPE-2). The bulk of these measurements are reported in APAE No. 21. There are some additional measurements reported in APAE Memo 115. In addition to the analysis of the ZPE-2 data some re-evaluation has been made of a few of the results obtained from the first set of Zero Power Experiments (ZPE-1). The ZPE-1 measurements are reported in APAE No. 8. During the course of analysis work it became apparent that a considerable amount of basic experimental data had been taken on the APPR-1 core. It seemed worthwhile to organize this report in such a fashion that other investigators could make maximum use of this data. It provides excellent opportunity for individuals and groups interested in basic reactor reactor analysis problems to check calculational techniques. An attempt has been made to include all of the fundamental information concerning the material content and geometry of the APPR-1. This material is in included in the Appendices. In addition, cross-section files and group constants have been listed rather extensively in order that other investigators could compare results presented in …

Report discussing experiments on particle density, plasma compression, electron heating, and electron energy distribution of plasma in a pyrotron. Past experiments that led to this investigation are discussed as well.

"This bibliography is a compilation of titles to unclassified reports, journal articles and conference papers written by members of the University of California Radiation Laboratory, Livermore and Berkeley, relating to Project Sherwood (Controlled Thermonuclear Reactions) from 1953 through 1957."

From abstract: "The combined attack of HNO3 and HNO2 on tributyl phosphate - kerosene solvent used in the Purex process produces degradation products that cause abnormal quantities of zirconium to be extracted along with the plutonium and uranium and thus limits the decontamination."

From abstract: "An electrolytic refining process was developed to produce tritium of high isotopic purity with negligible loss. The operation is semicontinuous, with multiple stages in cascade. All tritium oxide is handled within the confines of a hermetically sealed enclosure. The mechanical operability of the process was demonstrated in a five-stage prototype line designed to process 15 gram-mols of feed per day. An average separation factor per stage of 5.3 was obtained with a feed of tracer-level tritium. The equipment is described in detail."

A report about the start of preliminary measurements of the thermal conductivity of clad uranium and Zircaloy 2 prior to irradiation.

Results of an initial examination of non-fuel-bearing materials for the Marine Gas Cooled Reactor are presented. Areas given specific attention include structural and cladding materials and graphite moderator. Other areas not included because of classification include zirconium hydride moderator and control materials. In each report section, available pertinent information is summarized and a plan for future work is given.

"The effect of beam loading upon the design and performance of the accelerator is examined. Results are given in dimensionless form so that the various equations and grams can be used at any operating frequency. The constant gradient accelerator is somewhat less subject to beam loading than the uniform accelerator structure. For an accelerator of given filling time and 20% more."