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chemical Research and Development Operation was contacted by R. Nilson of Irradiation Processing Department in order to obtain an analysis from a chemical viewpoint of the worst credible accident to a full E-N reactor loading. This analysis would be used to present to the ACRS directly or would be abstracted to prepare a supplementary report. The primary purpose of this report is to present an analysis of the chemical behavior of an E-N loading in the event of the sudden loss of coolant to the entire reactor, with, however, normal operation of the control devices such that the reactor is initially driven sub-critical. We are here concerned wit the effect of a rising temperature upon the E-N load, the rise in temperature being primarily caused by the release of fission product energy.

The reliability of the K-Reactor water plants has been reviewed by Research and Engineering personnel; this study augments a brief analysis of the KW generator failures incident given in my letter of October 6, 1958. Our attention has been directed largely to ascertaining the requirements of the system, the consequences of possible component failures, giving general assessment of the primary features upon which reliability depends and identifying potential improvements which would increase reliability or moderate the consequences of a major failure. Our attention is restricted to failures which might occur as a result of equipment failure, operator error or certain natural causes such as earthquakes; we have not weighed special considerations brought on by enemy action such as sabotage, for example, in this evaluation. R. S. Bell is providing an analysis of the operating and maintenance aspects of K water plant reliability to complement this engineering study. It is concluded that the basic elements of the system lend themselves to reliable operation. The lines of defense appear adequate in depth, that is, a primary system operated with BPA power, an emergency ``backup`` system consisting of two essentially independent steam driven generators driving selected pumps, and a ``last ditch`` system providing …

Report detailing various Bremsstrahlung theories since 1945. Citations for different theories are included.

This report represents a critical review of existing reactor cooling systems and discusses suggested supplementary-cooling system which might be employed in emergencies resulting from such natural hazards as earthquake, equipment failure, or personnel error. In addition the subject of building filtration is discussed. Maintenance of an uninterrupted flow of cooling water is of major concern to the safety of any HAPO reactor. For some time supplementary cooling systems which would be capable of removing heat output in the event of failure in the existing emergency backup systems have been under scrutiny. Loss of coolant may cause damaging power excursion (should this occur during operation) or will inevitably result in fuel melting and a subsequent release of fission products to the atmosphere, even if the reactor is shut down prior to the loss of coolant.