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The report addresses the analysis of check value including failure and recommendations.

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This report discusses a meeting scheduled with a Subcommittee of the Advisory Committee on Reactor Safeguards to review the future need for retention of government land on the Wahluke Slope. A number of questions were asked by the Washington AEC Division of Production as a basis for the discussions. This interim report provides answers to several of the questions.

This report addresses the Application of Snap Reactor Power Systems to Manned Space Stations.

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The development and testing of a demonstration brushless alternator for the ML-1 mobile nuclear power plant is described. The brushless concept was selected after it became apparent that a conventional power generator could not satisfy the ML-1 weight and size requirements. The demonstration alternator fabricated and tested under this program did not meet all performance specifications; the efficiency was low and the unit could not be operated for significant periods of time without overheating. However, a large body of useful data was accumulated during the extensive development program. Of special interest are data on the rotor and stator design, the cooling requirements and on the distribution of eddy current losses. Analysis of the data indicates that a brushless alternator, only slightly larger and heavier than was specified for the ML-1, could be developed with a modest additional effort.

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This report, for May 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and weapons manufacturing operation.

To assure that the NEERVA reactor will function reliably during its test program, cleanliness must be controlled at each stage. These stages include design, manufacture, assembly, shipping, and test. The assembly stage is that phase which this handbook is concerned.

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This document defines the objectives, bases, and functional requirements that shall govern the preparation of design of the coolant backup system for the three remaining smaller reactors. This project will increase the reliability of the coolant backup facility at B Area by providing an independent last-ditch coolant system to B and C Reactors. The reliability of the last-ditch system for D Reactor will also be improved in that the present F and H leg of the export system will no longer be a part of the new export system. The objective of this document is to define the operational and technical requirements of the new facility and to describe the functional requirements of the proposed coolant backup system for the purpose of design.

This document presents the initial definition of a 2 Mwt, SNAP-50 Nuclear Powerplant Test and is intended to provide guidance to the Architect/Engineer in evaluating and costing various Nuclear Test Facility design concepts.

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This report summarizes the considerations and analysis leading to the design of the SNAP-15A generator, a Pu-238 fueled, metal thermocouple generator providing about 1 milliwatt of output power at greater than 4, 5 volts of years with very reliability even under extreme environmental conditions.

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