This report details activities of the 200 Area for the month of August 1966.

This report details 200 Area activities for the month of July 1966.

The 12 batches were individually dissolved in Redox dissolvers. U and Pu were separated from the test solutions and purified for isotopic analyses. Results are tabulated; Am-241, Cm-242, and Np concentrations are also reported.

Pursuant to the decision of the Atomic Energy Commission to deactivate a fourth Hanford production reactor, engineering studies were initiated in regard to the water supply and distribution systems of the smaller production reactor complex. It was the intent of these studies to effect optimization of the water supply and distribution system which would result in a more effective operation and would continue to meet existing standards and requirements. It is the purpose of this report to document the results of the engineering studies and to describe the functional requirements of the overall water supply and distribution systems.

Experiments on betatron oscillation frequency, beam life times, multiturn injection, longitudinal bunching, acceleration through the transition energy, energy spread in the accelerated beam, beam stacking procedures, effects of clearing neutralizing ions away from the stacked beam, and instability of the stacked beam are reported. (D.C.W.)

This document lists all tanks which were active during each month by Waste Farm, which includes all tanks to which additions or subtractions were made. Each type of waste was indicated in each case, along with the nature of transfer and any pertinent remarks. Also reported are gallonage and inches of liquid in each tank.

The capacity of photosynthetic organisms to exhibit photo-induced electron paramagnetic resonance (EPR) signals has been known for over ten years. Subcellular units of photosynthetic materials, the quantasomes and the chromatophores, are capable of Hill Reaction activity, and also of exhibiting the light-induced EPR signals. This, coupled with the rapid rise and decay kinetics of these signals, suggests but does not prove that the unpaired electrons are involved in the initial electron transfer processes in the primary quantum conversion act. The identification of the species giving rise to these signals and their connection with processes of primary quantum conversion remains elusive even though such varied approaches as mutant strains, special growth conditions, extreme physical conditions, special metabolic inhibitors, etc. have been applied to this problem. In this communication the authors wish to report another method being used in an attempt to identify the species responsible for the unpaired electrons. Hoffman prepared a water soluble, stable free radical, di-tertiary-butylnitroxide (hereafter called DTBN), which is a 'vigorous free radical scavenger'. It shows a sharp, well resolved, symmetrical, three-line paramagnetic resonance spectrum that is relatively insensitive to the molecular environment. The chemistry of di-tertiary butylnitroxide has not been studied extensively. However, four distinct types …

Data acquired from the temperature monitoring of Columbia River during 1963 through 1965 is presented.

This document summarizes the requested study of theoretical factors influencing the expected conversion ratio of the fringe enrichment portion of an E-N loading. Exact calculation of the quantity is very complicated and will not be attempted here; however, it is possible, with simple geometric approximations, to derive relative conversion ratios. This present report summarizes the results of a study incorporating actual operating data from the present poisoned top and unpoisoned bottom fringe loadings at H Reactor. There is calculated decrease in buckled-zone (E-metal blanket) conversion ratio of 13% in the E-N loading as compared to normal fringe loadings; this loss is due to the effective reduction in pile size due to the presence of the blanket of BOLL material in the outermost lattice unit and the accompanying increase in enrichment demands. On a full pile basis, this loss represents about 5%. However, on the assumption that an atom of tritium is equivalent in value to an atom of plutonium, the BOLL material in the outermost layer augments over-all pile conversion by about 4% in the green reactor, and probably more in the ripe reactor in addition to compensating the 5% loss in the E-metal blanket. An Appendix is included as …

During April 1962, equipment in both the main Redox Building (202-S) and the Plutonium Concentration Building (233-S) vas rearranged to allow the accumulation and recovery of neptunium without interference with the production of uranium and plutonium. In order to do this, the former rework column (1S) was put into continuous service as a neptunium recovery column, the Third Plutonium Cycle was converted to a neptunium decontamination cycle, and ion-exchange equipment was installed in the 233-S Building to replace the Third Plutonium Cycle. The neptunium, once decontaminated, will be concentrated and loaded out via its own system in the 233-S Building. To check the critical mass safety of the new arrangement, a formal hazards review was made, the results of which are reported in this document.

Target elements were designed and built to fit into 1.25% U{sup 235} driver elements. These targets had an aluminum -- 0.583% lithium alloy core enriched to 63.5% in Li. The targets had a coextruded aluminum jacket as a tritium barrier and a Zircaloy jacket as a corrosion barrier to the 300 C reactor water.

This document defines the objectives, bases, and functional requirements that shall govern the preparation of design of the coolant backup system for the three remaining smaller reactors. This project will increase the reliability of the coolant backup facility at B Area by providing an independent last-ditch coolant system to B and C Reactors. The reliability of the last-ditch system for D Reactor will also be improved in that the present F and H leg of the export system will no longer be a part of the new export system. The objective of this document is to define the operational and technical requirements of the new facility and to describe the functional requirements of the proposed coolant backup system for the purpose of design.

The use of digital computational techniques in the design of a 200-Mev standing-wave proton linear accelerator for use as an injector for a 12.5 Bev FFAG accelerator is described. A field computational program that permitted evaluation (optimization) of the r-f structure cost for a given accelerator design is described, and typical results are shown. A particle dynamics program is also described (D.C.W.)

None

None

The major objective of the current program is the preparation of high energy hydroxyl-terminated polyester prepolymers from combinations of energetic diols and dicarboxylic acid chlorides. The initial work was based on the reactions of 4,4-dinitropimeloyl chloride (DNPCl) with 2,2,8,8-tetranitro-4,6-dioxa-1,9-nonanediol (DINOL) and 3(dinitrofluoro- ethoxy)-1,2-propanediol (REX-18). In an effort to develop a smooth and rapid polyester polymerization method, reactions between DNPCl and both DINOL and REX-18 have been carried out in THF containing pyridine. It was expected that the pyridine would act as an HCl acceptor, permitting room temperature polymerizations. This was indeed shown to be the case. In fact, when the glycol and DNPCl were dissolved in THF and pyridine added rapidly, a very exothermic reaction took place, with copious quantities of pyridine hydrochloride being precipitated. Slow addition of pyridine to the reaction mixture also resulted in an exotherm. In both cases, brown polymers were produced and they were very difficult to work-up. The next series of polymerizations will be carried out at 0{degrees}C in an effort to control the polymerizations more carefully and avoid color formation. The diacid chloride of 2-fluoro-2,2-dinitroethoxyfumaric acid has apparently been synthesized. Reactions of the acid with thionyl chloride at 50-60{degrees} for several days followed by …

As a continuation of studies reported in BMI-1400, fabrication characteristics, physical and mechanical properties, and corrosion behavior in NaK, sodium, and water of niobium--uranium binary alloys containing up to 60 wt.% uranium were investigated. Alloys were cast by a skull melting and consumable and nonconsumable arc-melting methods. Fabrication difficulties with alloys containing greater than 25 wt.% uranium were related to coring-type microsegregation during casting. Tensile tests indicated 0.2% offset yield strengths of 16,880, 22,370 and 28,600 psi for niobium2000 deg F. Additional tensile data were obtained for alloys from 1600 to 2400 deg F. Stresses to produce minimum creep rates of 0.001, 0.01, and 0.1%/hr at 1600, 1800, and 2000 deg F were also determined. Both tensile and creep strengths were found to be sensitive to oxygen content. All alloys appeared compatible with NaK at 1600 deg F and with sodium at 1500 deg F. In 600 deg F water, most of the alloys tested exhibited negligible weight changes after 336 days' exposure. Weight changes were greater after 140 days' exposure to 680 deg F water, but corrosion rates were considered satisfactory for a clad fuel. The thermal and electrical conductivities of niobium are lowered by the addition of uranium, …

This report addresses the distorted-wave analysis of inelastic scattering.

None

The current-revision of the Process Optimization Program contains two empirical plutonium-exposure expressions. One relates total Pu conversion to exposure and the other, Pu-240 buildup to exposure. The former was incorporated to save computer time and the latter to provide product quality data. Both of these relationships, in addition to a third which relates Pu-241 buildup to exposure, are used in PULP-3, the data generator for LP-90. EMCON-3, a 7090 computer program which determines arbitrary constants for all three empirical expressions, has been devised. It uses, as input, official conversion data and will facilitate rapid evaluation of the effect, of periodic revisions in official conversion data, changes in reactor loadings, and/or changes in product specification. This document contains a discussion of the empirical expressions, the program mechanics, and program input/output. A Fortran listing of the program logic a deck assembly diagram, and sample program output are included in the appendix to aid the reader in using and/or revising the program.

I have understood my assignment as a review of some of the work done in high-energy physics with polarized proton targets and a description of some of the special problems connected with polarized targets. Most of my report will be based on the polarized target that I am most familiar with--that constructed by Jeffries, Schultz, Shapiro, and myself. This target is no longer unique; in fact, it is now somewhat old-fashioned in some respects. Other polarized proton targets are in operation at CERN, Saclay, the Rutherford Laboratory, Argonne National Laboratory, the Soviet Union, and there is a target newly in operation at the Brookhaven Laboratory. Other targets are in operation or are in the process of design or construction at a number of other places. Unfortunately, none of these targets consists of pure hydrogen. The target material most often used is made of lanthanum magnesium nitrate, LMN. About a quarter of the weight of this crystal is water; it is the protons within the water molecules that are polarized. Hydrogen constitutes only 3 percent of the weight of the crystal. This means that scattering processes on hydrogen must be distinguished kinematically from scattering processes involving the heavy elements of the …

This report provides the experimental results of uranium chemical machining tests.

This document details activities of the Fuels Preparation Department during the month of June 1962.

This document details activities of the Fuels Preparation Department during the month of March 1962. (FI)