Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended power run of 90 days duration. (M.C.G.)

None

This document contains information on special filter samples of Hanford Process Effluent Gases. The filters are identified by code numbers only. Included in this paper are tables explaining the sample code numbers, sampling locations, and process conditions during sampling. Also included, is a copy of the monthly and quarterly average results for Regional Monitoring's routine stack program for the fourth quarter of 1956.

None

This document presents a summary of work and progress at the Hanford Engineer Works for December 1953. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Sciences, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

This is a progress report of the production reactors on the Hanford Reservation for the month of December 1951. 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.

This document presents a summary of work and progress at the Hanford Engineer Works for May 1954. The report is divided into sections by department. A plant wide general summary is included at the beginning of the report, after which the departmental summaries begin. The Manufacturing Department reports plant statistics, and summaries for the Metal Preparation, Reactor and Separation sections. The Engineering Department`s section summaries work for the Technical, Design, and Project Sections. Costs for the various departments are presented in the Financial Department`s summary. The Medical, Radiological Science, Utilities and General Services, Employee and Public Relations, and Community Real Estate and Services departments have sections presenting their monthly statistics, work, progress, and summaries.

Present methods for monitoring Ru{sup 103}, Ru{sup 106}, and I{sup 131} in stack gases involve sampling by filtration and scrubbing and analysis by chemical separation and counting or by gamma spectrometry. Filtered samples, which are ordinarily collected over a complete day, are analyzed for total ruthenium and iodine by gamma spectrometry and for the individual isotopes by chemical separation and counting. The present scrubber monitors the sampler gas for total activity. As an aid to Radiological Sciences evaluation of stack gas hazards and to operations control of radioactive gas emission, Methods and Instrument Development collaborated on the planning of a continuous monitoring system. This memorandum has the purpose of outlining the plan, reviewing progress since conception in October, 1953, and reporting work still to be done.

This report, dated March 22, 1954 details work procedures for the 200- West Area at HAPO. Topics discussed include emergency procedures, safety and housekeeping practices, policies and procedures, instruments and equipment located at the 622 tower, instruments and equipment located offsite, observational procedures, form entries, and card punching, and weather forecasting.

chemical Research and Development Operation was contacted by R. Nilson of Irradiation Processing Department in order to obtain an analysis from a chemical viewpoint of the worst credible accident to a full E-N reactor loading. This analysis would be used to present to the ACRS directly or would be abstracted to prepare a supplementary report. The primary purpose of this report is to present an analysis of the chemical behavior of an E-N loading in the event of the sudden loss of coolant to the entire reactor, with, however, normal operation of the control devices such that the reactor is initially driven sub-critical. We are here concerned wit the effect of a rising temperature upon the E-N load, the rise in temperature being primarily caused by the release of fission product energy.

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.

This is a progress report of the production reactors on the Hanford Reservation for the month of December 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.

The September, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation.

As a part of Project CG-775, 100-K Area Water Plant Expansion, the capacity of the 181-K river pump installations will be increased. Recommendations for the raw water requirements based on a reactor flow of 175,000 gpm were presented in document HW-55877. Since then a new fuel element has been developed for the K reactors, resulting in a lower reactor system curve. It is recommended that the design criteria for the 181-K river pumps be based on a total raw water flow of 213,000 gpm with spare pumping units and a maximum flow of 232,000 gpm for each plant.

The July, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

As the result of repeated over tolerance monitoring samples taken by H.I. Survey in Room 7 of 2228 Bldg., 200 East Area, an Industrial Hygiene study of the air contamination in this room has been made at the request of the H.I. Area Supervisor. Observations made during the preliminary survey and throughout the study indicate that the ventilation system together with the decontamination operations; slurping operation, Goldberg operation, and certain activities during bench determination of process examples, are the major contributors to contamination in the room. While it is felt that the major sources of contamination have been pointed out, there are many specific operations that have not been studies. Recommendations include: Replace the air supply grills with air diffusers, so that air will be supplied to the laboratory without drafts; Provide hoods over the decontamination sinks large enough to accommodate all manipulations involved in decontamination procedures and with sufficient exhaust ventilation that will maintain a minimum face velocity of 200fpm; Provide a hood over the slurper, larger enough to accommodate all manipulations, and ventilation to maintain a minimum of 200fpm at the hood face and any other openings; Provide an enclosure over the Goldberg such that positive exhaust ventilation …

The reliability of the K-Reactor water plants has been reviewed by Research and Engineering personnel; this study augments a brief analysis of the KW generator failures incident given in my letter of October 6, 1958. Our attention has been directed largely to ascertaining the requirements of the system, the consequences of possible component failures, giving general assessment of the primary features upon which reliability depends and identifying potential improvements which would increase reliability or moderate the consequences of a major failure. Our attention is restricted to failures which might occur as a result of equipment failure, operator error or certain natural causes such as earthquakes; we have not weighed special considerations brought on by enemy action such as sabotage, for example, in this evaluation. R. S. Bell is providing an analysis of the operating and maintenance aspects of K water plant reliability to complement this engineering study. It is concluded that the basic elements of the system lend themselves to reliable operation. The lines of defense appear adequate in depth, that is, a primary system operated with BPA power, an emergency ``backup`` system consisting of two essentially independent steam driven generators driving selected pumps, and a ``last ditch`` system providing …

None

None

The September, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

None

Uncontrolled boiling of the water in a process tube might result in serious damage to a pile. Consequently, it is desirable to maintain header pressure generally sufficient to sweep out any steam which might be formed. Since the header pressure required to remove the steam depends upon the power output of the tube, the power level of a tube or pile is limited by the pressure available. In the past, tube power limitations have been specified and interpretations thereof. Recently a through study, both theoratical and experimental, has been made to determine the validity of these limitations. The purpose of this report is to present the results of the study must make recommendations for future operations. The limits presented herein are based on tube power levels.

Record highs were set for Pu output in separations plants and for amount of U processed in Purex. UO{sub 3} production and shipments exceeded schedules. Fabrication of 200 and 250 Model assemblies is reported. Unfabricated Pu production was 8.5% short. Nitric acid recovery in Purex and Redox is reported. Prototype anion exchange system for Pu was tested in Purex. Hinged agitator arms with shear pin feature was installed in UO{sub 3} plant H calciner. Operation of continuous type Task I, II facility improved. DBBP is considered for Recuplex. Methods for Pu in product solutions agreed to within 0. 10%. Purex recycle dock shelter is complete. Other projects are reported.

The "ORACLE", Oak Ridge Automatic Computer and Logical Engine, was installed at Oak Ridge National Laboratory :in 1953 and.has been in operation since that time. This manual describes the machine's design, the number systems it uses, and its basic operations.