This report describes the circumstances leading to the accident, attempts to reconstruct the nuclear reactivity conditions, and reviews the dosimetric means and results which were used to help determine the exposure of affected employees.

Describes the design criteria, design details, and final installation of a high precision temperature and intimate contact monitor.

Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.

Investigation to evaluate some of the designs, techniques, and methods for fabrication of a root pass.

Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.

"The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those produced and would be equivalent to 0.002 curie/ cm/ sup 3/ in the primary helium circuit. The maintenance problems associated with this contamination level are discussed. A cost analysis indicates that the capital cost of this nuclear station per electrical kilowatt would be around 0, and that the production cost of electrical power would be 7.8 mills/kwhr" (p. iii).

Report describing the helium atmosphere system in the Argonne National Laboratory's Facility 350. The atmosphere's ability to remove moisture, oxygen, and other impurities, how the atmosphere is purified, and experimental data regarding the use of activated carbon to absorb oxygen from helium are discussed.

Report issued by the Oak Ridge National Laboratory discussing the development of a high-density concrete. As stated in the abstract, "the basic approach to high-density concrete mix design is reviewed to show that theoretical calculations for concrete mixes do give results that are reliable" (p. 1). This report includes tables, illustrations, and photographs.

Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Progress of operations, construction, engineering analysis, and development is presented. This report includes tables, illustrations, and photographs.

Report containing the ongoing research and development of the Oak Ridge National laboratory's Analytical Chemistry Division.

Report containing reports from the Physics Division of the Oak Ridge National Laboratory that cover a wide variety of subjects.

Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.

Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.

Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.

Annual report issued by the Argonne National Laboratory discussing work conducted by the Metallurgy Division during 1963 including progress related to experiments, programs, and studies. This report includes tables, illustrations, and photographs.

Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.

Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.

The subject of this report is the generalized computer program written to solve problems involving steady fluid flow through heterogeneous, partially-saturated porous media.

Report on ecological investigations sponsored by U.S. Atomic Energy Commission.

From introduction: The scope of work of the study was to compile and analyze information on the resources and requirements of the southwestern, southeastern, and north-central coastal regions of the Commonwealth, and assess industrial and agricultural activities which in conjunction with the power and desalting plants, might comprise the energy center complex. The study was also to identify the need for any experimental, pilot or demonstration projects which benefit the practical application of the Energy Center concept in Puerto Rico.

From foreword: This report contains thirty-three papers that were presented at a symposium regarding the use of thorium and uranium-233 in nuclear reactors.

Introduction: Atomic Energy Facts is designed to serve as an introduction to nuclear operations in the United States and as a handbook of related information for the use of industrial firms and other active or interested in atomic energy.