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This report discusses the performance of exit gas thermocouple.

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.

Expressions are presented for the electric and magnetic fields due to a pulse of charge, which may be oscillating transversely while moving down an infinitely long highly conducting pipe of circular cross section. The expressions are evaluated at large distances from the pulse and the fields are shown to decrease algebraically in the distance behind the pulse. In the absence of transverse oscillations the longitudinal electric field varies as the inverse three-halves power of the distance; in the presence of oscillations the dominant field component is the transverse magnetic field, which decreases as the inverse one-half power. In the long-range limit the amplitude of the fields is proportional to the square root of the wall resistivity. The phase of the field associated with the oscillating pulse is shown to be the phase of the pulse at the time when it passed the point of observation.

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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.

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.

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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 report provides for each process tube the coolant flow rat (gpm) and temperature drop ({degrees}C) for the process tube containing the fuel rod bundles and for the four nearest neighboring process tubes. Reactor shutdown and startup times are also given. Peak thermal neutron flux in the adjacent fuel can be calculated.

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The reactor scrams are summarized in a table which identifies the component.that opens the safety circuit and the reason or cause for the safety circuit trip. Caution should be exercised in the use of the summary for specific analysis of reactor scram causes. In a high percentage of cases, the component that opens the safety circuit is not at fault. A description of the reason or cause for a particular scram is given in the body of the report. The actual outage time charged to the cause of the reactor scram is given with the exception of scrams caused by tube leaks or fuel failures.

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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.

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.

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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.

This report consists of a table which gives the change in height of tube No. 4674 at a specified distance from the inlet flange. Forty-one data points were taken beginning with a distance of 18 inches from the inlet flange and ending with a distance of 36 feet from the inlet flange.

This report presents a simple critical experiment configuration.

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