The potential of shipping a bucket of metal that has not had sufficient decay time is a common problem to all Reactor Processing Operations. The only method at present to assure shipping adequately decayed metal is by procedural control. This study was performed to determine the feasibility of establishing decay time for irradiated metal in buckets by radiation activity measurements.

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Budget figures are given for N-reactor department, irradiation processing department, chemical processing department, and Hanford laboratories.

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This document describes a deviation from the "Test Program and Procedures for the 710 Critical Experiment Reactor Control Drum Mockup Experiment," TM-64-3-706, which was made in accordance with ITS Standard Practice J80-81 on September 14, 1964. The deviation did not involve a significant change in the safety of the operation.

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Studies initiated at Hanford in 1961 for the purpose of developing an alternate cladding process for I&D fuel elements for the eight existing production reactors indicated that the hot die sizing diffusion bonding process offered the greatest incentive. Hot die sizing was the most attractive with respect to improved fuel quality and potential reduction in fuel element unit cost when compared to the existing AlSi brazing process. Initial development work consisted of determining optimum process parameters for producing good diffusion bonds on the inner and outer lateral surfaces during sizing. This report summarizes the results of a series of end bonding variables tests designed for producing good diffusion bonds on the ends of hot die sized fuel elements.

A summary of HAPO activities is given to include separate sections on the N-Reactor and other current production reactors. Specific programs and fuel performance for current production reactor fuels is discussed. Also, the production status, fuel performance, development program and process technology for N-Reactor fuels is presented.

This is the monthly report for the Hanford Laboratories Operation, January 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

This is the monthly report for the Hanford Laboratories Operation, July 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

This report discusses comments received on the previous report on internal graphite moderator forces (HW-79120); sleeve test channel inspection; and BDF reactor distortion.

The loss of flow is considered as far as the flow to the inlet hydraulic connector, inlet plugging and water shutoff time. A mockup revealed no vibration of the fuel element bundles and at the low temperatures present there should be no problem of corrosion. Efforts to assure safety with plutonium in the fuel elements are noted. (GHH)

This document details activities of the irradiation processing department during the month of December, 1963. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

This document details activities of the Irradiation Processing Department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

This document details activities of the irradiation processing department during the month of November, 1964. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; and Financial Operation.

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

Supplement A, Production Test IP-544-A authorized the irradiation of 1.6 per cent enriched single tube elements in KER-1 and -2 and specified certain limitations on the operating conditions for the elements. The test required that specific operating conditions and trip settings for particular loadings would be approved by the managers of Testing, Process, and Reactor Development and Process Technology Subsections prior to charging. The purpose of this document is to provide the process the tube loading, operating limits, and water shutoff times for a charge of eight 12-inch 1.6 per cent enriched single tube elements in KER-1 and -2.

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This report details volumes of radioactive liquid wastes disposed of at Hanford for the month of August, 1964.

The Hanford graphite-moderated reactors have an enclosed gas circulation system to maintain control of the composition of gas atmosphere in the graphite stack. This investigation was undertaken to answer several questions concerning the generation and release of Carbon-14 in the operation of these graphite moderated reactors. The principle question was: Will an increase in the nitrogen content of the reactor atmosphere increase the release of Carbon-14 sufficiently to create a health hazard. Other questions were: (1) What are the main sources and the main release routes. (2) How much does carbon-14 build up in the graphite in the reactor stack. and (3) Is the total release of carbon-14 to the atmosphere sufficient to enhance the /sup 14/C levels in the vegetation surrounding the reactors.

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