Techniques involving the use of high-intensity short-duration light pulses have been applied t o the study of the kinetics of photoconductivity in films of metal-free phthalocyanine. These experiments, in conjunction with measurements of steady-state photoconductivity, are consistent with the following scheme. The principal route for the formation of charge carriers is via the first excited singlet state, although the lowest triplet state can, t o some extent, contribute to charge - carrier production. The mobility of the carriers is low and is concentration-dependent, being lower at higher carrier concentration. The decay of the photocurrent is the result of a diffusion-limited bimolecular recombination, with a capture radius of approximately one molecular diameter. The experiments indicate that carriers produced thermally in the dark do not interact with light-produced carriers.

The addition of ortho-chloranil to the surface of films of metal-free phthalocyanine has been found (a) to increase the dark conductivity of such films by as much as 10{sup 7}, (b) to increase the steady-state photoconductivity by as much as 10{sup 5}, and (c) to result in the formation of unpaired electrons whose concentration decreases reversibly as a result of illumination. These systems exhibit a light-induced polarization, the phthalocyanine layer becoming more positive with respect t o the ortho-chloranil layer. Kinetic studies demonstrate that, upon illumination, a single process (time constant = 40 seconds) results in the increase in conductivity, the decrease in unpaired spins, and the increase in polarization. The results are consistent with the following scheme. An electron transfer from phthalocyanine to ortho-chloranil occurs in the dark at room temperature, producing holes in the phthalocyanine layer and ortho-chloranil negative ion radicals (high conductivity, ESR signal). Illumination results in the transfer of an electron from an excited phthalocyanine molecule to the ortho-chloranil negative ion, producing further phthalocyanine holes and ortho-chloranil double-negative ion (increase in conductivity, increase in polarization, decrease in ESR signal). By equating spin concentration with charge - carrier concentration (phthalocyanine holes) it is possible to calculate a …

Boron solution circulated through special poison tubes to achieve more variable control of neutron flattening'' was tested in the 100-DR Hanford reactor. About 2700 gallons of irradiated waste Ink solution from Production Test 105-529-A was discharged to an underground crib at 100-DR, after radiochemical analyses and evaluation of radiation protection aspects by the Radiological Sciences Department. In case the Ink method is considered for production use at Hanford in the future, further biological and biophysical study is recommended to determine whether irradiated waste Ink solution may be disposed of into the Columbia River, into the ground near the river, or into the ground several miles from the river. 10 refs, 2 tabs.

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This report provides details of a test to determine the feasibility of preventing corrosion of the 107- C retention basins by the installation of a small scale cathodic protection system.

The purpose of this memorandum is to present and analyze, in terms of the current status of knowledge of radiation damage to graphite, the data available at the present time on the expansion status of the graphite in the piles, and suggest, in terms of this analysis, several possibly feasible curative and preventive measures. The portion of the data to be covered in this memorandum consists of that obtained during the last four years from pile motion measurements and from tube bowing measurements, and particularly that from graphite mining operations during the last six months. The objective to be attained is twofold: (1) the information developed here should permit a better understanding of the need for and development of future corrective measures to be applied to the present piles, and (2) this summary will serve as a basis for further experimental work necessary to place the conclusions on a more firm foundation. This memorandum is being issued at this time, although present ideas and conclusions are in a somewhat uncertain state, in the hope that the currently most feasible preventive measure might be applied to the DR Pile before startup.

The lack of control rod capacity in the reactors with nine rods is causing significant production losses. The present control system, which functioned satisfactorily at a 300 MW equilibrium power level, is unable to counteract the larger startup reactivity transient effects at the current high power levels. This lack of strength causes the power level to be restricted during startup. The control system is also not flexible enough to prevent outages for the discharge of temporary poison. (1) A method of obtaining the required supplementary control strength and flexibility has been conceived. (2) and equipment developed for this purpose. The purpose of this test. (3) was to demonstrate the operational feasibility of the special front and rear face equipment which was designed to permit the routine charging and discharging of poison slugs at selected process tubes during periods of reactor operation. This report presents the data, results and conclusions obtained from the trial use of this equipment.

The purpose the production test described in this document was to evaluate by pile irradiation the stability and resistance to rupture of powdered metal compacts.

Production rates of the Hanford reactors can be increased in proportion to the quantity of process cooling water which can be supplied to them. This water must be of such a quality that slug and tube corrosion rates are acceptable, the gross activity of the effluent water must not be excessive, the concentration of specific radioactive isotopes constituting a radiological hazard must be minimized, and the film formation rates should be as low as possible. In the Hanford water treatment process, the filter plants are the controlling factor in determining the quality of the water, and one of the elements limiting the quality of water. A major development effort was therefore undertaken to develop methods of increasing the capacity of the existing filter plants. This report presents the result of this development work from its inception in 1951 to its conclusion in 1954.

The intent of this manual is to present a description of the main process building, equipment, and auxiliary facilities as well as a process summary. Material is of a scope nature with more detail devoted to features unlike those of existing separations systems. An attempt is made to convey some of the basic design philosophy and the problems encountered in the development of design criteria. This information is written primarily for Separations Section supervision who have not had an opportunity to become conversant with the Purex Project. The manual may also be of assistance in orientation and training of personnel. In order to avoid repetition and duplication of effort, one line service diagrams, equipment sketches, tables, and detailed data are not a part of this manual.

This report presents a study of the stresses induced in the elbow and downcomer of the B and C Reactors (bulk effluent systems) by flow momentum and pressurization effects. It is desirable to ascertain the limitations on the bulk outlet temperatures and flow rates from a stress viewpoint; the elbow, top coverplate of downcomer, and top baffle plate being the most severely stressed components.

The objective of the experimental studies reported herein was to demonstrate the laboratory-developed mercury-catalyzed dissolving procedure on a pilot-plant scale by conducting a series of test dissolutions of aluminum-jacketed, unirradiated uranium in the 150-gallon downdraft type semiworks dissolver in 321 Building. It was desired to establish: (1) the effect of the larger-scale operation on time cycle; (2) dissolution rates of aluminum and uranium, (3) controllability of the reactions, and (4) the concentration of mercury catalyst required.

Reactor gas costs have increased substantially each year since 1952 when the total cost was $108,000. In 1953, 1954, and 1955 the gross annual cost of reactor gas was $126,000, $348,000 and $606,000 respectively and are reported in Figure 1. These continued increases in reactor gas costs indicate the need for an analysis of gas usage and formulation of a program to reduce gas consumption. To provide basic information for such a program, a critical review has been made of the reaction gas system and gas consumption figures for the past four years.

This is a progress report of the production reactors on the Hanford Reservation for the month of June 1950. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.

Project C-431-A includes the design of the C Water Plant outfall structure. This report documents design assumptions and the design of the spillway, outfall sewers, spillway chute, trash racks, walkways, stop log and trash rack slots, main sewer, and retention sewers. The spillway capacity is to be 268,000 gpm with a crest elevation at 429.0. This flow capacity is composed of flow from the 105-C Retention Basin (80,000 gpm), 105-B Retention Basin (45,000 gpm), and the 190-C Area main sewer (143,000 gpm).

Since 105-C Pile was designed without thimbles, gas seals are required on all horizontal control rods to prevent the pile gases from escaping and contaminating the atmosphere.

This document is Revision No. 2 of the ``Process Specifications for Critical Mass Control -- Purex Plant``. It encompasses the changes in flowsheet, equipment and plant operating philosophy that have developed since the plant startup. It supersedes Document HW-44064 (Revision No. 1). Plutonium-239 and uranium-235, either as the metals or as dissolved or solid compounds are capable of spontaneous and violent nuclear reactions. Following initial dissolution of irradiated natural uranium fuel elements the Purex Plant is normally involved in the processing of liquid solutions containing these isotopes. However, in Purex Plant solutions, uranium-235 is invariably associated with a large fraction of neutron-absorbing uranium-238, a condition which precludes the possibility of a nuclear reaction. (These specifications are based on the premise that no enriched uranium is processed in the Purex Plant.) Plutonium-239, on the other hand, is separated from uranium by means of the Purex process; and even prior (process-wise) to its separation, the ratio of plutonium to uranium must be controlled during the off-standard conditions of plutonium rework or recycle. Critical mass control in the Purex Plant is concerned solely with prevention of nuclear reactions of plutonim-239, which has been produced by irradiation of natural uranium fuel elements.

The purpose of this report is to present results of an experimental program directed toward determining the degree of protection offered by the Panellit protection system to flow losses to a single process tube containing I & E fuel elements in K reactor.

A program to develop a new fuel element was initiated at Hanford in 1951. A survey of the possible methods of making such a fuel element was completed and a document listing all possible lines of research was written. The problem was outlined as it appeared at that time; various developments which have occurred subsequently have changed this problem to a greater or lesser extent. Essentially the problem concerned the development of a fuel element which would not fail or would fail in a slow and predictable manner and would not cause damage to the pile. A largenportion of the research and development was concerned with the application of these layers. This paper will review the research that was done on the development of these corrosion-resistant layers and will evaluate the problem as it appears now after approximately four years have elapsed.

This report for June 1958, 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.

During a routine beta-gamma hand and shoe count, an employee discovered that his shoes were contaminated. This document discusses the spread of particulate contamination at the Biophysics Laboratory, Building 329, 300 Area on July 6, 1954.

This monthly document details activities of the Hanford Operations Office during the month of July 1959. (FI)

Several decisions regarding basic project philosophy must be made in order to proceed with scope design and the preparation of equipment procurement specifcations. The purpose of this document is to present as much pertinent data as possible to allow the project representatives to become familiar with the problems involved. A meeting of Representatives is planned for the near future after receipt of project authorization to discuss the scope of this project and its relationship to CG-775. Emergency flow requirements of the K reactors for planned future power levels is approximately 32,000 gpm within 68 sec. A detailed study of the existing high-pressure cross-tie line reveals that a duplicate cross-tie line and five low lift pump operation would be required to provide this flow. The existing emergency generation capacity is not adequate to supply five low lift pumps and all other necessary emergency electrical loads. A possible solution to adequate emergency flows is to connect the proposed steam turbine pump directly to the risers and to consider the turbine pump as the last ditch system. If it is determined that this does not meet the criteria of separate systems, then an alternate solution must be found.