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This report descriptively talks about the advanced space nuclear power program. Starting with the 1967 third- quarter report, each quarterly report of the Advanced Space Nuclear Power Program is published in two parts. The first contains unclassified material only, the second contains classified material only.

This report addresses a quarterly report of the Advanced Space Nuclear Power Program containing a result of recommendations made by the Congressional Joint Committee on Atomic Energy.

Report talking about Alkali- Metal Corrosion of High- Temperature

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This is an Applied Mathematics Division Summary Report

A highly accurate output monitor system utilizing a current transformer was developed for the 30 nanosecond pulse field emission electron source. Charge and energy fluence were determined as a function of distance from the source.

This report talks about the Chemical Effects of Nuclear Transformations, Flash Heating or Flash Photolysis. Technical Progress Report, February 1, 1967--October 31, 1967.

The Elk River Reactor is a second-round, ThO$sub 2$--UO$sub 2$ fueled, stainless-steel clad, boiling water reactor built by Allis-Chalmers Manufacturing Company under contract to he U.S. Atomic Energy Commission for the Rural Cooperative Power Company. One of the stated objectives of the reactor is the demonstration of of the thorium cycle. The final physics design and pre-start-up analysis were done in 1958 to 1962. The reactor was loaded in 1963, reached full power in 1964, and shut down for it first refueling in April 1966. At the time of shutdown, the core had achieved an average burn-up of 7040 Mwd/metric ton. Agreement between predicted and observed performance was excellent throughout the core life.

The purpose of this monthly report is to make available to the fast reactor program the current experience being gained from the Enrico Fermi Atomic Power Plant.

This report address the correlation between radiation and chemical induced molecular damages and their biological expression in mammalian cells.

The principal objective of this program is to provide a better definition of the operational limitations of Zircaloy fuel cladding.

This report addresses the creep mechanisms in B. C. C. alloy crystals.

Commencing on September 5, 1967, after the completion of the low power startup program, construction of the items required for power operation was resumed. In order to reduce the possibility of any foreign objects being dropped into the reactor vessel, the reactor vessel head was installed before construction personnel were permitted at the 701-ft level.

An important limitation on the design of an inpile thermionic reactor is the fast neutron irradiation damage to the insulators, which is expressed quantitatively by the energy weighted neutron flux, or damage flux. The behavior of the damage flux has been investigated for a set of hypothetical critical assemblies containing different types of fuel and different amounts of moderator. It is shown that for a given fuel, the damage flux is reduced by moderating the neutron spectrum, and for a given amount of moderator the damage flux is reduced by increasing the amount of fuel in the fuel pin. Some effects of damage flux considerations on reactor design are also shown.

This report describes the work performed by the Paducah Gaseous Diffusion Plant relative to the design and fabrication of a demonstration fuel element shipping cask utilizing laminated depleted uranium metal as shielding material.

This paper covers the highlights of the Paducah Gaseous Diffusion Plant nondestructive and destructive testing programs performed on the "Demonstration Fuel Element Shipping Cask from Laminated Uranium Metal."

An in-line process differential colorimeter, with automatic check system, has been developed with thhe capability of analyzing Pu(IV) in the range of 0.1 to 2.5 grams per liter. The instrument measures the difference in light transmittance at two wavelengths, 580 and 660 nanometers. These wavelengths are a characteristics of Pu(IV), ad the difference in transmittance is a measure of the plutonium concentration.

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