The Bevatron is still undergoing a process of gradual improvement to increase both the magnitude of the beam and the reliability. The operating conditions for optimum adjustment at the present stage of development are summarized.

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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 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. 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.

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.

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The detonation of shot one at Bikini Atoll on March 1, 1954, produced a fallout of radioactive ash upon Rongelap Atoll, Marshall Islands. The distribution of the radioactive ash on the islands and in the plants and animals of the area has been studied and evaluated. During the first expedition to Rongelap Atoll on March 26, 1954, biological samples were collected and measurements made of the radiation contamination. On three additional expeditions extensive collections of material were made for this study, the last on January 25-30, 1955. The decline in radioactivity was measured in 1499 samples of fish, invertebrates, land plants, algae, birds, plankton, soil, and water from the Rongelap area. During this study particular emphasis was placed upon evaluation of the radioactivity in food used by the natives. Coconut milk collected on March 26, 1954, contained 1.03 microcuries per kilogram of wet tissue while the coconut meat had 1.16 mu c/kg. By January 25-30, 1955, the level in coconut milk had declined to 0.041 mu c/kg and the meat to 0.036 mu c/ kg. Fish muscle on March 26, 1954, averaged 2.74 mu c/kg and fish liver 204.0 mu c/kg. The decline to January 25-30 was 0.10 mu c/kg …

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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 …

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.

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 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.

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.

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.

The loading on the primary transformers which step down the 230 kv transmission voltage to a distribution voltage of 13.8 kv, at 100-B-C, 100-D-DR, 100-F, and 100-H Areas will be increased by the synchronous motors now being installed in those areas under Project CG-558. This report summarizes: The changes in electric loads (both kv and power factor) which will result when the new motors are placed in service and certain older motors are withdrawn from service. Electric loads are tabulated in section 4.0 for each area for present conditions, the planned changes and the post-CG-558 conditions. The reduction of distribution voltage during the starting of individual 4500 hp synchronous motors. Since the synchronous motors will be started across the line as induction motors, the starting current will be high, and at a low power factor. Voltage drops are calculated for the starting of a synchronous motor, with one and then with two transformer banks paralleled. The current-interrupting capacity of switchgear vs. the maximum short-circuit current which could occur with separate transformers and with two primary transformers in parallel.

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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.