Abstract: A calculational method is presented which may be used to determine fast and thermal neutron flux distributions at deep neutron penetrations in hydrogenous shields.

Summary: A Laboratory operating and policy guide was issued which requires that all new KAPL, KAPL subcontractor, and AEC contractor personnel receive an indoctrination in radiation protection before beginning work at the Laboratory.

Report presenting "the evaluations of the series which represent the solutions to the Fourier equation in rectangular, cylindrical and spherical coordinates for the case in which the initial temperature field is that owing to a spatially uniform heat source" (p. 1).

Report that "is a supplement to IDO-16332, "The Engineering Test Reactor Critical Facility Hazards Summary Report", presenting information on the conduct in the Facility of certain experiments which are expected to be operated in the Engineering Test Reactor" (p. 3).

This report discusses the problem of obtaining thermonuclear temperatures as part of reaching a controlled fusion reaction for fusion power. Tables covering radiation losses and thermonuclear reaction rates are included. Talk before JCAEC in Washington, D. C.

Report containing basic operating instructions for the operation of the Army Package Power Reactor. This includes descriptions of the the plant's systems, operations, and safety procedures.

Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.

Report documenting an investigation undertaken "to establish the burnout limits of a polyphenyl mixture (...), diphenyl, Santowax R, and monoisopropyl-biphanyl for various pressures, fluid velocities, and fluid temperatures" (p. 7).

From abstract: The planes and modes of fracture as a result of the mixture of beryllium and other elements were investigated.

Abstract: The concept of a tapered fluidized bed is explored briefly. Data are given showing that in bench scale apparatus a tapered bed gives better fluidization with some materials that are difficult to fluidize in a conventional cylindrical bed.

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.

Report containing a series of reports from members of the Oak Ridge National Laboratory's Neutron Physics Division.

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Molten-Salt Reactor Program. Descriptions of the progress and studies conducted is presented. This report includes tables, illustrations, and photographs.

Abstract: A transistor trip circuit intended for critical assemblies and which provides maximum safety against human error or component failure is described.

Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).

Introduction: The experimental work reported here was undertaken as a part of the over-all design and development program for a nuclear reactor pressure vessel.

Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Plant design and system analysis including cost analysis and capital cost summary are given.

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."

Summary: A survey was made of KAPL personnel currently exposed to radiation relating to their previous work with radiation or radioactive materials.

Report describing the Hanford Atomic Works' Plutonium Recycle Test Reactor, its siting concerns, operation, and safety concerns.

From abstract: "Background material leading to the development of the metal quality of reactor-grade thorium is given. The metal should be sound and of uniform hardness, free of internal cracks and inclusions, and corrosion resistant. It should contain only small amounts of natural uranium, thorium oxide, and elements that act as reactor poisons. Because of their effect upon metal quality, various methods for the production of thorium are discussed. Use of consumable electrode arc melting as the final step has contributed much to the production of thorium of excellent quality for reactor use."

Report describing the maintenance system in place for the coolant system of an Engineering Test Reactor (ETR).

Report issued by the Argonne National Laboratory discussing selected physical properties of various solids, liquids, and gases of interest in nuclear reactor heat transfer and fluid flow analysis. In most cases, values for thermal conductivity specific heat, density, viscosity, and Prandtl numbers are given as functions of temperature. This report includes tables, and illustrations.

Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment.