In the separation of mixtures of radioactive iron and cobalt from neutron irradiated targets and in the removal of iron from cobalt targets for cyclotron production of radioiron, it is desirable to have a method superior to extraction from isopropyl ether in efficiency and ease of manipulation. Recent studies by Moore and Kraus on the separation of cobalt and nickel and on the behavior of iron in hydrochloric acid on Dowex-l resin in relation to the selective adsorption of chloride complexes of these elements have suggested the use of resin for the separation of iron and cobalt.

On January 12, 1953, an explosion occurred in the Savannah River pilot plant which has been used since November, 1951 by du Pont personnel to train operators and to test equipment for their new Purex production plant. The explosion occurred in an evaporator in which a uranyl nitrate solution containing some organics was being concentrated to a high degree to remove nitric acid. This memorandum reviews the facts surrounding the incident as obtained from the official Preliminary Technical Report'', and by talking to du Pont personnel. These facts are interpreted as fast as possible and the current design for the Hanford Purex production plant is re-evaluated in the light of these data.

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At the present time, production commitments require that each of the two dissolvers used at the Redox Plant be charged with 4.95 tons of irradiated metal every other day. After the aluminum jackets are removed from the slugs, the uranium is dissolved in three ``outs`` of 1.65 tons each. Because meteorological conditions often limit the time when the radioactive dissolver off gases may be emitted without contamination of the surrounding area, the dissolving requirements are frequently too great to maintain the required dissolver charging schedule. Unless the dissolving time cycles (or the meteorological limitations) can be reduced to assure that charging every other day can be maintained, phase 2 rates cannot be met even after activation of the third (spare) dissolver. As a means of reducing the dissolver time cycle and enabling the charging of each dissolver on alternate days throughout the year, a proposal was submitted that each dissolver charge be dissolved in two cuts of 2.475 tons each. This report presents the results of the plant test to determine the operational feasibility and relative merits of this proposal. Moreover, the information obtained may be used on a supplemental basis for the design of the Purex Plant dissolvers. 3 …

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The program of the Pile Graphite Studies Unit for the past two years has been directed toward relaxed graphite specifications. The main emphasis in these studies has been on the feasibility of higher permissible maximum graphite temperatures and higher percentages of helium in the gas systems. The success of this program is evidenced by the potential pile power levels permitted by present process specifications. The present graphite Process Specifications will not permit heat generation associated with tube powers above 800 KW at, B{sub 9} D{sub 9} and F Piles. Therefore, further relaxation is necessary if tube powers of 1000--1200 KW anticipated after completion of the water plant expansion program are to be realized. In extending the present program to permit these anticipated tube powers, production tests authorizing full pile tests for raising permissible maximum graphite temperatures and increasing the percentage of helium are necessary. A production test authorizing the operation of D Pile at sufficient constant power level to attain graphite temperatures of 460--500 C with 60{plus_minus}5 percent helium has been agreed upon and is now circulating for final approval. A production test has been prepared to evaluate graphite burnout, rates at maximum temperature of 600 C with localized regions …

Twenty charges each of low hydrogen dingot fuel and standard ingot fuel elements were irradiated at DR-reactor. Distortion data from 22 tubes are analyzed in this document. The dingot fuel elements are prone to greater tube filling capacity (TFC) and greater daimeter growths at both center and ends of the fuel elements (the growths at center are larger than at ends). The difference between average warp values for the two types of fuel elements is not statistically significant, indicating that the greater TFC values shown by th dingot fuel elements are due to their larger diameter growths at the slug center rather than to larger warp values.

Modifications to the 100-K water plant will be made, under Project CG-775, to increase total process water flow rates to 175,000 gpm or greater. Included in the modifications will be the installation of new pump impellers for the primary and secondary process water pumps located in the 190-K Buildings.

The purpose of this report is to present the conclusions and recommendations obtained during the course of the CPD Control Study and the conceptual framework upon which they are based. Primary emphasis has been given to the control of product materials. In order to logically present the background for the definition and delineation of an appropriate CPD Control System, Section III of this report discusses a control system in the following manner; (1) the description of the control system information requirements, (2) the definition of the conceptual framework of product material control, (3) the discussion of the interrelationships of production scheduling, process control and accountability and (4) the methods for the effective utilization of control system information. Section IV utilizes this conceptual framework in order to enable a logical presentation of a proposed product material control system for the CPD. A summary of conclusions and recommendations is included in Section II. The Appendices consist of discussions of specific analysis conducted during the study. Other related reports that have been issued during the course of the study are included in the references.

Changes in pile operating parameters, such as fuel exposure, paver, and reactivity gain upon water loss affect the potential reactivity of the operating, pile and, therefore, the amount of enrichment required to operate under the desired conditions. Similarly a change in ECT (through enrichment location) changes the amount of enrichment.needed to maintain a constant reactivity. Many of the factors which influence the operating reactivity have quite different effects upon the reactivity of the dry pile with the ball 3X system inserted; therefore, changes in operating parameters may cause sizeable changes in requirements for supplementary control to maintain sub-criticality in the dry pile. It is the purpose of this document to summarize these trends in disaster control requirements for the K piles. The trends are presented as graphs of supplementary control requirements against a single varying parameter. All other parameters are held fixed as specified on each graph. The fuel element (central orifice zone) for all examples is the K-2 slug. In general, the slopes of these curves are only slightly dependent upon the specific values assigned the fixed parameters, although the magnitude of the control requirements may be quite dependent on these values. Unless otherwise noted any dependence of the …

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This document discusses high radiation levels which are being encountered in the reactor discharge areas during outages. Rear face dosage rates in B, D, F, DR and H Reactors now average 100 mr per hour. These high radiation rates seriously jeopardize desirable projects which require extensive work on the rear face of these reactors. Evidence has been obtained which indicates that a large source of the radiation is on the interior of the rear face piping and can be removed by chemical solutions. Reference one presents data which indicates that up to 85 per cent of the gamma activity is caused by the contaminated film deposited inside the rear face piping. Reference two discusses the results of chromic acid removal of process tube corrosion products. Reference three more fully describes the possible advantages of purging a reactor with chromic acid and concludes a chromic acid purge should remove the film without adverse effects on reactor structural materials or process tube loadings.

The object of the production test described in this report is to obtain full pile high temperature graphite burn-out data. In addition, the test will supply valuable data on the postulated influence of neutron temperature on plutonium purity.

On the 0000--0800 shift, September 30, 1959, the delayed neutron monitor on KER Loop 3 gave a high coolant activity signal. Events occurred rapidly that tended to substantiate the possibility of a fuel element failure in this loop. KE reactor was shut down immediately thereafter. This report is being written to summarize the sequence of events prior to and those following the KE reactor scram and to discuss the results and significance of data from analyses on coolant and coupon samples taken from KER Loop 3.

In the production of plutonium in a reactor, plutonium-238, 240, and 241 are formed as well as Pu{sup 239}. It is well known that the specific alpha activity of the plutonium varies as the percentages of these isotopes are changed. Kinderman, et al have worked out the relationship between isotopic content and MWD/ton exposure. Their findings are reported in this document.

It is recommended that the Design Committee approve the installation of a refrigeration system in the 105-C gas circulation system for removal of moisture from the reactor following a process tube leak as was previously approved by the C-431 Project Committed. Engineering studies show that this refrigeration system is necessary to provide sufficient water removal capacity in order that the water absorbing capacity of the system furnished by the silica gel towers will not be a limit to the rate at which a reactor can be rehabilitated following a serious leak.

Separan is a now water plant coagulant chemical which was submitted to the Process Sub-Section for evaluation in late 1954. Beaker tents were run which showed the material to be potentially valuable in modern water filter plants, but thorough evaluation was impossible because proper testing facilities were not available. Since August 1955, Process Sub-Section has operated an experimental filter plant which has shown promise as an evaluation tool. Consequently, as the facility appeared to be adequate for testing Separan, a trial run was made. The results have been so promising that an interim report was thought desirable. The results of our primary tests follow.

The attached unclassified article was prepared for publication in Civil Engineering. It describes construction techniques and equipment used in processing, prepacking, and grouting heavy aggregates used in the construction of the K-reactors.

The objective of this test is to permit irradiation of projection fuel elements to evaluate jacket corrosion in areas of projection, to examine the effect of well-aligned fuel elements on hot-spot incidence, and to evaluate problems associated with projection slug usage in ribbed process tubes.

This is a listing of the classified periodic and series reports originated at the Hanford Atomic Products Operation for the period 1943 to June, 1953, and of similar reports received from the Hanford Operations Office. This listing also traces the continuity of reports that have undergone title changes during this period. This has been done by cross referencing to titles previously or subsequently used. The primary grouping of these reports is according to the intervals at which they were issued, e.g., weekly, monthly, annually, etc. Within each group, the reports are arranged alphabetically by title; for each individual title a note at the right hand margin gives the inclusive dates for the period during which reports of that title were issued. Those not shown with closing date are being issued currently. Specific document numbers for each title are found in the catalogs of the 700 Area and 300 Area Classified Files. The list is intended primarily to assist Classified Files in locating periodic reports requested by Plant personnel. However, it is also hoped that it may emphasize to authors the need for retaining an established title for a periodic report. Unnecessary changes of title every few months for the same …