A method is developed for the calculation of the effect of Doppler broadening of the absorption of the neutrons by a resonance absorber. Numerical values are given for the correction factors required in the interpretation of transmission experiments and self-indication experiments and for the self-shielding factors for slabs, spheres, cylinders, and homogeneous mixtures. (auth)

This report is about the study of mechanism of carbon dioxide fixation by the non-sulfur purple bacterium, Rhodopseudomonas, capsulatus.

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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.

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The primary purpose of this report is to set forth the reasons why the Task II hydrogen fluoride gas delivery system is unable to supply sufficient quantities of the gas to the process at all times and to make recommendations on how to correct this problem. However, it is also a secondary purpose of this report to make general recommendations on all phases of the gas delivery system where it is felt that an improvement can be made in either the design or operation of the system.

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The following topics were discussed in this report: pressurization of the rear face for existing reactors; loss of steam in existing reactors; in-pile boiling in the 105-KER recirculation facilities; feasibility report for special study reactor plant; shielding requirements of the special study reactor plant; sulfuric acid addition to 100-K; radiation from activated iron in a recirculating system; ion exchanger activity from Fe corrosion; thermal shock-KER loop; shielding of tube bundles; adjustment of raw water pH; and Zircaloy fuel element jackets.

From the startup of the TBP Plant until late in September, 1954, when in-line scavenging operations were begun, the wastes from the TBP Plant had been stored after neutralization and concentration in underground storage tanks. Some of this TBP waste has been given a secondary concentration in the waste concentration facilities (first cycle waste evaporators) at the tank farms. Studies by the chemistry Unit have indicated that a further reduction in the volume of waste permanently stored is possible by scavenging these wastes. In this document, a chemical flowsheet is presented for use as a design basis of facilities which will permit scavenging of these stored wastes.

Project CG-588 authorized the design and construction of dissolver and waste neutralizer off-gas scrubbers to remove the ammonia given off during coating removal and waste neutralization steps of the Redox operation. It has always been recognized that the nitrogen oxides in the dissolver off-gases, resulting from the dissolution of bare uranium slugs, could also be absorbed in water under proper conditions to give re-useable nitric acid. Consequently it appeared feasible to provide facilities which would combine these ammonia removal and nitric acid recovery operations. The purpose of this report is to present a scope design for the economical recovery of nitric acid from the Redox dissolver off-gases in addition to the removal of ammonia. It is recognized that acceptance of this scope for project execution would make unnecessary the ammonia scrubbers for the dissolver off-gases of Project CG-588. 8 refs.

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Current H.A.P.O. planning has scheduled significant increases in low-NGS irradiated fuel production for the near future. This action, coupled with the imminent activation of the K-Reactor areas, will result in a uranium production rate which exceeds the anticipated capacities of the Purex, Redox and T Plant separations facilities. Additional separations capacity is scheduled to be provided by reactivating B Plant. However, a number of other separations processing schemes -- which will provide additional capacity -- are being evaluated for their economic and operating attractiveness as compared to combined BiPO4-TBP plant operation. The BPX process described in this memorandum is one such process. It is a modification of the TBX Scheme III of HW-32691. BPX was first proposed by the Manufacturing Department in HW-32908. The pertinent flowsheet details of the BPX process are provided and a discussion elaborates on the novel features of the flowsheet and also lists process items of general technical interest.

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Reactor Programs. The design of the Boiling Experimental Reactor is described. The Borax-1 reactor was intentionally destroyed by suddenly adding 4% excess reactivity. Design of the Borax-II reactor is described. It will be used for studies of transient behavior and steadystate operation as a steam producer. A preliminary design configuration has been established in EBR-II employing central, inner, and outer blankets. Fuel geometries including a smaller pin-type element are being investigated. Supporting Design, Research, and Development. The accuracy of diffusion theory for fast reactors was investigated. Water corrosion tests have been performed on high-U alloys, Zr- and Ti-base alloys, and Ni-plated Al plates. Thermal cycling tests were performed on fuel rods and pin-type fuel elements. Results are reported on tests on a current conductor connection for a high-temperature d-c electromagnetic pump, on Na valves with conventional packing, and on a rod-gripper test facility for the EBR-II. A vacuum cup sampler for high-temperature Na and NaK systems is described. Lifting and loading mechanisms for the IBR-II working model are described. (T.R.H.)

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In the dry chemistry process of the Metal Fabrication Building, plutonium oxalate as received from the Isolation Building is converted to plutonium tetrafluoride and the fluoride is then reduced to the metal. This document discusses the oxalate-fluoride conversion which involves oxidation of the oxalate and subsequent fluorination of the oxide, utilizing anhydrous HF gas. Batch operation is practiced. The standard batch for the period covered by this report was 400 g Pu.

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