The results of the fall-out monitoring program at fixed stations more than 200 miles from the test site following the series of atomic tests in Nevada during the spring of 1952 are shown in a series of maps. Trajectories of debris from the individual bursts are given, together with a discussion of meteorological phenomena associated with the transport of atomic debris.

Failures of standard fuel element jackets (1245 aluminum alloy) after relatively short Hanford reactor exposures are occurring at high reactor power levels. Metallographic examination of fuel element jackets from short exposure ruptures shows the cause of failure to be rapid intergranular corrosion. This type of attack has been reproduced in laboratory tests by exposure to water at temperatures above 200 C, or to steam at temperatures higher than 300 C. Flow disruptions due to misalignment of the fuel elements within the reactor process tube, worn tube ribs, etc., are believed to cause the high local jacket temperatures necessary for the occurrence of intergranular corrosion.

The objective of the production test described in this report is to provide the authority and mechanism to remove process tubes from the piles for inspection. The test is intended to provide a more positive tube inspection program than was previously provided under production test number 105-9-P, ``Corrosion of Slugs and Tubes``, document number 7-3928.

Fragments of radioactive materials were deposited in the Redox area during August, 1953. By radiation monitoring, the location, physical properties, and dosage were determined. The cause was assumed to be the buildup of ammonium nitrate containing ruthenium on the filters of the Redox stack. The amount of occupational exposure, and the reasons why this incident happened were also discussed.

This report details initial results of a large scale accountability test program which was recently carried out in the Redox Facility. The test, as originally planned which was to consist of the complete processing (no inventory-clean plant basis) of about 55 tons of selected metal in conjunction with an extensive analytical, sampling, and volume measurement program. With the exception of two incidents, the processing requirements (minimum inventory and measurement of all material) necessary to the success of the test, were met. The two incidents which increase the uncertainties associated with some of the material balance values obtained were: the discharge of an estimated 700 pounds of uranium to the floor in a transfer from F-5 to F-4 due tot he improper installation of the F-5 to F-4 transfer line (jumper) and the discovery of a large accumulation of plutonium ({approximately} 15 kg) in the L-2 stripping tower after completion of the test run.

The intent of this study is to establish more completely the justifications for constructing a decontamination plant as outlined in Budget Item B 5720, ``Containmented Equipment Renovation Shop,`` FY 1957, Plant and Equipment Projects. In particular, the economic incentives have been explored. The question or idea has been investigated of assigning a dollar value to engineering information which might be obtained from examining contaminated equipment which has failed from unknown causes. Heretofore it has not been possible to examine such equipment because suitable decontamination facilities have not been available. An effort has been made to uncover all possible uses for the proposed facility in order that the estimated capital and operating costs might be evaluated in terms of all the functions which the proposed plant might perform.

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This is a progress report of the production reactors on the Hanford Reservation for the month of January 1954. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes the accomplishments and employee relations for that month.

This document presents a summary of work and progress at the Hanford Engineer Works for December 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 summarizes 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.

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A major problem in the development of a pressurized water reactor coolant system for the NPS is the rupture performance of the fuel elements. As water temperatures are increased to 300 C, uranium corrosion rates increase rapidly. Swelling of the uranium fuel by corrosion could cause the process tube to burst or reduce the tube cooling water flow below acceptable limits. The desirability of slow cooling of the water to avoid thermal shocks to the reactor piping after a rupture is detected further complicates discharge and decontamination problems as fuel will continue to corrode with attendant fuel element damage during the cooling period. Coextruded uranium-zircaloy-2 clad fuel elements are scheduled for use in the NPR. The rupture behavior of this type fuel material after heat treatment was studied in ELMO-4, an out-of-reactor recirculating water loop. Several types of initial defects were studied. Fuel materials with five different heat treatment histories and with different types of defects were tested to determine their rupture behaviors. The five conditions were (1) as-extruded material as received from Nuclear Metals, Inc., (2) beta heat-treated and water quenched, (3) beta heat-treated and air-cooled, (4) beta heat-treated, isothermally treated at 600 C and air-cooled, and (5) beta …

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This document presents a summary of work and progress at the Hanford Engineer Works for September 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 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.

Construction of proposed facilities to be operated under Technical Division supervision for research with plutonium is discussed. An attempt is made in this memorandum to visualize the research program for such a facility for the next five years, to aid in determining whether the cost of providing such facilities is justified.

It is the objective of this study to investigate preliminary expansion program requirements for process water, as supplied by 190 Building equipment; from the point of view of practical pumping, flywheel and pump suction head requirements. These requirements are to be determined at this time in such a form and accuracy as to be useful in refined estimating for budget study purposes. In order to obtain the objectives of this study at this time it has been decided to consider five different conditions of process water flow to a reactor. These conditions are flow to the reactor under summer conditions of operation in gallons per minute with a corresponding top of riser pressure in pounds per square inch: 85,000 gal/min, 580 psi; 100,000 gal/min, 480 psi; 130,000 gal/min, 280 psi; 150,000 gal/min, 280 psi; and 150,000 gal/min, 150 psi.

This letter transmits the data from the 189-D Hydraulics Laboratory flow test on three CG-482 rear pigtails. The tests were run with a standard B, D, Dr and F rear nozzle and rear Parker fitting over the range of flows and temperatures anticipated for early CG-558 operation. The data from the test are given. All three pigtails gave essentially identical results. For comparison the results of previous tests with present rear pigtails are also plotted.

This document details activities of the Fuels Preparation Department during the month of April 1959. (FI)

Hot press canning of internally and externally cooled fuel elements has been developed to a point where the process is feasible. Complete specifications have been written for the process covering component, dies and punches, furnace construction, nickel plating, component cleaning, component assembly, sizing, hot pressing and inspection. Drawings covering each major item are included.

It has been noted on occasion that the side rupture rate at lower exposure is higher than one would expect in order to be consistent with the mathematical model (Weibull curve) used describe the rupture data. This has apparently been due to a few ruptures occurring at exposures lower than one would anticipate on the basis of the model. Restricting themselves to fuel elements irradiated under similar conditions of power and temperature, it is difficult to assert that these ruptures are anomalous with respect to the model used since there are so few ruptures involved. For this reason, some means of combining data was called for in order to see whether or not at least some of these low exposure ruptures were inconsistent with the model, and, if so, to revise the model in order to better describe side rupture performance. In this report, the results of an analysis of side failure data for failures covered in a previous report are given. Also included is a discussion of possible implications derived from recognition of the existence of this revised model.

In early July 1958, it appeared that Columbia River temperatures at HAPO would be near 24--50{degree}C by the end of August. River temperatures were averaging 40 to 50{degree}C above 1957 figures and were 3{degree} to 4{degree} above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent. The large storage of cold water behind Grand Coulee Dam, normally untapped, was a source of possible relief. A plan for use was proposed for the peak high temperature period and agreed to by the Bureau of Reclamation.

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The in-line monitoring instruments installed in the Redox plant in the late 1950s consisted of six gamma monitors, a single channel gamma spectrometer, an alpha monitor, and a neutron counter. A gamma monitor on the steam condensate outlet line and a uranium monitor on the 2DFS stream were to be added at a later date. The first section of this information manual describes the in-line gamma monitors and gives operating instructions for them. The second section covers the alpha monitor, and the third section the neutron counter. Sections on the uranium monitor and the steam header gamma monitor were to be added at a later date.

Reactor operating conditions are formally established to conserve pile life. A major part of the 2000 Research and Development effort is oriented to develop fundamental information required to properly establish these limiting operating conditions. This report reviews the current condition of reactor components believed important to continued productive life of the reactors and discusses the current status of technologies important in estimating the future productive life of the reactor complex. These evaluations are conducted continuously and this report is one of a series of status reports.

The temperatures of the Columbia River was reduced 1 to 30 Centigrade with beneficial effects at HAPO. It is reasonable to expect that future benefits may be possible. It is desirable that the temperature of the river be controlled each year to the maximum extent possible. Instrumentation improvements requested to effect optimum savings. Records of river temperatures and flows should continue to be maintained by IPD as a necessary part of temperature optimization. Where possible, the coincident use of the river cooling technique should be made for the benefit of anadromous fish.