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The motivation for an interactive computer system is to obtain fast response for program generation, debugging, and running. The human user retains control of the computing process, and can modify program, change parameters, and correct errors as required during solution of the problem. An interactive system contains a man-computer interface as a distinguishing characteristic. This interface is not present in the more common, batch process, computer systems.

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The Multifunction Storage Unit, Type I is a storage device capable of storing geometrical information in visual display form. The storage is accomplished by means of an electrostatic storage cathode ray tube. The Storage Unit consists of this storage tube and its associated circuitry. Associated circuitry is considered to be all circuitry required by the storage tube itself which is necessary to make the unit a self-contained storage unit. The following six external signals are all that is required in order to write, store and erase in the unit: vertical deflection signal, horizontal deflection signal, gate signal, z axis signal, erase signal (local or remote) and AC power. The erase signal causes the entire screen to be erased and primed for writing.

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The purpose of this study is to provide budgetary data for modifying and monitoring the present water treatment process at B, C, D, KE, and KW reactor plants to effect a reduction in the activity of the reactor effluent water discharged to the Columbia River. The study is subdivided into three parts: facilities for sodium silicate addition at each reactor water plant, on-plant facilities for the manufacture and supply of sodium silicate, and instrumentation for monitoring the water treatment process for standardizing water quality in the water treatment plants. While the present concentrations of radionuclides discharged to the river are well below the maximum permissible concentrations established by the National Bureau of Standards, the proposed reduction is in the interest of providing greater protection from potential radiation exposure to people living downstream from the Hanford Plant where economically practicable.

This document details activities of the Reactor Operation Branch during the months of January, 1966 through December, 1966.

In fulfillment of a request by the Atomic Energy Commission, an inspection system was developed by the Hanford Atomic Products Operation of General Electric Company during 1964 for periodic monitoring of production reactors should they be shut down under international agreement. Ground rules included access to the reactor building and to the reactor core itself for installation, checking, and removal of equipment for determining whether or not the reactor had been operated between periodic inspection visits. Subsequent correspondence from the Atomic Energy Commission indicated that the in-core system proposed was satisfactory for the ground rules under which it was developed, but that the Arms Control and Disarmament Agency wished also to know whether or not a perimeter inspection system would be feasible. For purposes of this study ``perimeter`` access at a radius of one mile was to be assumed. Hanford was asked to investigate and report on the feasibility of such a system, the extent of work to be equivalent to a Title 1 design effort. This report describes the work carried out by Battelle-Northwest on this program.

On February 13, D Reactor sustained a bumpered enriched fuel element failure in process tube 3289. The element failed in the twenty-first position from the rear of the charge and was from lot KY-928-Q. Visual examination of the failed element indicated the failure mechanism to be cleavage of the uranium core. This conclusion was substantiated in part by the appearance of ``worm tracks`` in the aluminum jacket. The fuel failure was detected approximately three hours after the reactor had resumed operation from a minimum outage. Examination of reactor operation during the three-hour period revealed no evidence of a power transient which might account for the failure mechanism. As a result of a previous meeting between the management of Process Technology Subsection and Production Fuels subsection, verbal information was received from PFS which possibly explains the failure mechanism experienced with this lot. An agreement reached in the meeting was that PFS would provide Process Analysis with fuel lot canning history for evaluating continued irradiation of fuel failure lots with questionable quality integrity.

Data acquired from the temperature monitoring of Columbia River during 1963 through 1965 is presented.

This document summarizes the amounts of radioactive contamination discharged to ground from chemical separations and laboratory facilities through December 1965. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of January through December 1965. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to January 1965. Several changes in crib nomenclature were made during 1965. These changes are noted on the individual tables so reference may be made to them in previous reports.

A survey has been conducted of current methods of disposal of radioactive, chemical, and sanitary wastes used both at the 100 Area and 300 Area sites of N Reactor Department Operations. In addition, liquid storage facilities have been surveyed for situations which might result in river water pollution. The survey and this report have been prepared in response to the request of the Manager, Richland Operations Office of the Atomic Energy Commission in accordance with Executive Order 11258. An audit of N Reactor Department waste disposal procedures and practices was recently made. The audit report provides detailed data on effluent streams, methods,d and sampling points. Therefore, this report does not include that information and instead provides a summary of experimental and analytical data which have become available since the audit. It also includes information developed in response to specific provisions set forth in the Executive Order.

This report, from the Chemical Processing Department at HAPO for January 1966, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

Data for the vertical bowing of tubes 1574, 3074, and 4574 at different distances from the inlet flange are given in table form. The data were taken on January 17, 1966.

Data for the vertical bowing of tube 4574 of the B reactor at different distances from the inlet flange are given in table form. The data were taken on February 10, 1966.

A thermal analysis is carried out to determine the temperature distribution throughout a SNAP 10A reactor core, particularly in the vicinity of the grid plates, during atmospheric reentry. The transient temperatue distribution of the grid plate indicates when sufficient melting occurs so that fuel elements are free to be released and continue their descent individually.

Station 1A was the emplacement hole for the nuclear device used in the Advanced Research Project Agency's and U.S. Atomic Energy Commission's 5-kT nuclear Salmon Event of October 22, 1964. The hole penetrated the Pascagoula and Hattiesburg Formations, undifferentiated, and the Catahoula Sandstone, all of Miocene age, before entering the caprock at a depth of 882 feet. In continued through the calcite, gypsum, and anhydrite units of the caprock, which extend to a depth of 1,469.5 feet, and terminated in the salt stock at a depth of 2,802 feet. Five sand aquifer units lie above the caprock, whereas one sand aquifier lies within the calcite unit of the caprock. Drilling activities did not cause noticeable water-level fluctuations in the sand aquifers; however, during drilling in the calcite caprock, drilling fluid losses twice caused significant but temporary rises in water level in three observation wells that monitor the calcite limestone aquifer. The microscopic examination of drill cuttings collected at 10-foot intervals to a depth of 1,220 feet in Station 1A is presented. 2 figures, 1 table.

A method for determining numerically local minima of differentiable functions of several variables is described. In the process of locating each minimum, a matrix which characterizes the behavior of the function about the minimum is determined. For a region in which the function depends quadratically on the variables, no more than N iterations are required, where N is the number of variables. By suitable choice of starting values and without modification of the procedure, linear constraints can be imposed upon the variables. 8 figures.

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This report describes decontamination methods that have been used twice, flowing two periods of "hot" operation, to reduce radiation levels in excess of 2000 r/hr to values sufficiently low to permit extensive direct maintenance and equipment modification.

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