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Two important problems in the investigation of reactor hazards are the chemical reactivity of various materials employed in reactor construction and the chracteristics of heat transfer under transient conditions, specifically heat transfer when driven by an exponentially increasing heat source (exp t/T). Although these problems are independent of each other, when studied in relation to reactor hazards they may occur in a closely coupled sequence. For example the onset of a dangerous chemical reactor may be due to structural failure of various reactor components under an exponentially rising heat source originating with a runaway nuclear reactor. For this reason, these two problems should eventually be studied together after an exploratory experimental survey has been made in which they are considered separately.

This document addresses questions concerning radioactive build-up in a liquid control solution recycling through the pile at the Hanford Works plant. The solution composition and method used to obtain dose rates are included.

A. M. Gaudin and collaborators have published a curve of refining costs versus ore grade in terms of dollars per pound of U308 recovered on the basis of 90% recovery.

A kinetic study of the accumulation of C{sup 14} in the intermediates of steady state photosynthesis in C{sup 14}O{sub 2} provides information regarding the sequence of reactions involved. The work described applied the radio-chromatographic technique for analysis of the labeled early products. The simultaneous carboxylation reaction resulting in malic acid as well as phosphoglycerate is demonstrated in experiments at high light intensity. A comparison of radioactivities in a number of phosphorylated sugars as a function of time reveals concurrent synthesis of fructose and sedoheptulose phosphates followed by that of ribulose phosphates and later by that of glucose phosphates. The possibility that the cleavage of C{sub 4} compounds to C{sub 2} carbon dioxide acceptors may involve C{sub 7} and C{sub 5} sugars and evidence for this mechanism is presented.

In order to obtain data for the development and design of the Purex dissolvers and to demonstrate to Manufacturing and Technical personnel the feasibility of increasing the size of dissolver cuts at BiPO{sub 4} and Redox, a dissolver production test program in a BiPO{sub 4} dissolver is requested. These tests are expected to supplement the program already initiated on the 321 Bldg. dissolver, explaining dissolver behavior to the extent that existing dissolvers can be operated under more nearly optimum conditions and that new dissolvers can be designed with accuracy.

This memorandum discusses experimental determination which was made of the sensitivity and operational characteristics of the modified effluent water beta activity monitor system which is to be utilized at C pile for slug rupture detection. The optimum operating conditions for this system were also determined. A comparison of the performance of the C pile system with that of the existing Hanford type beta system was made to establish the degree of improvement realized through system redesign; this information being of assistance to the Pile Physics slug rupture detector development program. This report discusses the performance of both beta sensitive systems and the parameters upon which improved performance depends. A two ionization-chamber mockup of the C pile system was installed in the near effluent water sample room at H pile and utilized in these studies.

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 …

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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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.

A scheme was proposed whereby the third and second uranium cycle salt wastes in the Redox plant are combined, stripped, evaporated, and then returned as scrub to the first (and possibly second) cycles as scrub, operating as a dual scrub column. It is the purpose of this report to study this proposed method of back-cycling, and to investigate other methods of reducing chemical and waste storage costs.

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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 …

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.

A project proposal is now under preparation for converting all areas to the alum and activated silica coagulation process, and modifying the present test installations to permanent facilities. The conversions will be designed to service increased water flows resulting from the reactor plant expansion program now under way. As an alternate to the installation of permanent facilities at the various areas, the possibility of hauling already prepared activated silica from those areas having excess capacity to those areas requiring large capital expenditures was suggested. The purpose of this study is to make an economic evaluation of the operating costs of hauling activated silica compared to the increased capital investment necessary to manufacture activated silica at various areas.

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Corrosion of aluminum front cap supported shielding slugs has been noted at all reactors except C Reactor which has galvanized shielding pieces. There has been a considerable amount of difficulty caused by sticking of the places. The difficulty is caused by the growth of corrosion products in the annulus around the shielding piece which affectively siezes it. As recently as June, 1953 the shielding pieces on nearly 50 per cent of a group of 40 tubes at B Reactor were corroded to the extent that a pipe wrench was required for their removal. Similar instances, to varying degrees, have occurred at all reactors except C.The purpose of this test was to evaluate the radiation affects of removing the front shielding pieces as part of a program to eliminate the sticking problem.

A new method of calculating neutron distributions in a cylinder which has appreciable absorption is described. Measurements and calculations on the small-source theory treatment of resonance absorption in U-238 are given. Experimental measurements are reported of the bucklings of lattices utilizing hollow uranium slugs. The effects of varying amounts of cooling water in a graphite-uranium lattice have been measured. A detailed mathematical fitting of experimental reactivity data has been started; some initial results are given here. Curves showing the periods of the lattice testing reactor under various conditions have been calculated in connection with a study of the nuclear safety of this reactor. A method for calculating the critical mass and an estimate (4.4 kg of-U-235) thereof is presented. A technique for measuring the conversion efficiency for U-233 production of Hanford-type lattices is being developed. In connection with the study of the temperature coefficient of reactivity, an analysis has been made of the errors in reactivity change estimates produced by errors in cross-section measurements. The dependence of Pu-240 content in product plutonium on the flux level at which irradiation takes place, which is produced by the 23-day half life of Np-239 is worked out in some detail. An experiment for …

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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.