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The decay kinetics of the photo-induced absorbance changes in red and green algae are very sensitive to the wavelength of the actinic 11ght. A four to twofold increase in half-decay time is noted in going from short wavelength (550-650 mu) to long wavelength (> 700 mu) excitation. The slow decay ratios, produced by long wavelength light can be enhanced with a steady background of short wavelength light. A relationship between initial decay rates and 02 evolution rates is described. This relationship allows a direct correspondence between these spectroscopic studies and the 'red-drop' and 'enhancement' experiments of Emerson.

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This document details activities of the Irradiation Processing Department during the month of October 1964.

The monthly report for the Hanford Laboratories Operation, October 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, and physics and instrumentation research, and applied mathematics operations are discussed.

This report discusses 105 intermediate range test hole which was bored in 105-F to demonstrate reactor hole boring techniques. This test hole was then utilized to determine the performance of neutron sensitive gamma compensated ion chambers (CIC), the effectiveness of epoxy reactor shield plug designs, the compatability of the prototype.components intermediate range instrumentation, and demonstrate the performance of an intermediate range monitor system on a typical Hanford reactor application. In the process of determining the above information physical, nuclear, gamma, and temperature data was recorded as related to the 105-F intermediate range monitor test hole and is provided in this report.

This, report, for October 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; and employee relations.

The top thermal shields of the Hanford reactors were formed by placing single layers of large cast iron blocks on the top of the graphite stacks. Accumulative distortion of the graphite stack is causing several inches of variation in the elevation of the originally level top thermal shields. The integrity of the top thermal shield cooling tubes is of concern because of the high axial and bending stresses they are subjected to from the shield variations in addition to the normal service conditions common also to the side and bottom thermal shields. Concern for possible deteriorating condition of the top cooling tubes has increased with the discovery of a leaking cooling tube at the C Reactor. This report provides information of the present condition of the cooling tubes and discusses continued surveillance of their condition which is required for evaluation of their continued serviceability.

Because of the unexpected growth behavior of hot die size fuel elements during irradiation, it was necessary to re-evaluate the plans for hot die size irradiation testing and redirect the development effort. Tests were initiated to determine the cause of the growth, and plans were made to incorporate findings into subsequent irradiation tests. This report summarizes work done to determine the cause of the unexpected growth and the status of irradiation tests designed to measure improvements in the growth behavior of irradiated hot die size fuel.

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This document is a monthly report on the operation and engineering work associated with the N-Reactor department. It summarizes the operating history of the reactor during the month of Nov 1964. Included are brief descriptions of ongoing and planned work on testing and development of reactor components, fuel elements, safety tests, cooling systems, fuel production, materials testing, and other projects to provide safe and efficient plant operation.

The objective of the production test detailed in this report is to continue a program started under Production Test IP-690; the major change is an increase in sample enrichment. The higher enrichment is required to increase the portion of the fuel element core which is molten. This test will provide data to correlate maximum fuel temperature with post-irradiation microstructure, and data that are required to study the kinetics of fuel redistribution during the time interval between insertion of the capsule, into a constant, established neutron flux, and the time at which a steady state equilibrium structure is reached. This information will permit calculation of high temperature heat transfer coefficients and their variation during initial stages of irradiation. A quantitative understanding of fuel relocation and the time required to reach equilibrium are needed for optimum design of ultra-high temperature fuel elements.

Declassified 28 Aug 1973. Honeycomb structures in which uranium dioxide is dispersed in a tungsten matrix were made by two fabrication methods. These are discussed in detail and photographs of units produced by both methods are included. Several sizes of uranium dioxide powder were investigated as possible fuel materials. (73 figures, 25 tables) (auth)

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This report is to evaluate a silver plated aluminum Bar-X seal's effectiveness in extending the range of ability to seal such a damaged plug.

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On the NRX-A reactors the instrument ports are sealed by a Bar-X seal. Damage to the ports, which are part of the pressure vessel, required machining on the pressure vessel. A new design, using a Marman flanged piece to house the Bar-X seal port separate from the pressure vessel, was proposed. The test program was to determine the torque required to seal and the ability of each seal to hold during thermal shock.

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