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Activities discussed in this report are as follows: shielding studies; xenon generator; assay of xenon sample counting techniques; crystal diffraction neutron spectrometer; C{sup 12} cross sections measurements; magnetic spectrometer; scintillation spectroscopy; improved pile structure; criticality for the untamped 16 inch spherical reactor; exponential experiments; large scale pile structure; and operational pile physics.

Present thinking and planning appears to be developing from the following factors as concern the 13.8 KV temporary construction power limit. 1. It is understood that the present intent is to supply 100-N operating requirements from a single stub source in the 230 KV loop. 2. The original thoughts were to obtain construction power over a 13.8 KV line from 151-D substation. 3. Construction load requirements are now less than originally planned since steam has been substituted for electrical drive of primary loop pumps and 5500 hp motor tests are no longer necessary. 4. An extreme emergency backup source for the K plants has always been of concern, although minimized in recent planning. It is desirable to review the temporary construction line requirements from a future operating viewpoint to determine if the line could be useful to the operating plants after completion of construction. It is highly desirable to provide T.C. power source from K plants rather than 151-D and then leave the line and breakers in place for future maintenance assistance and as extreme emergency backup to K plants.

After the present solid slugs are replaced with the new I&E elements` in the 105-B reactor, the friction loss for the reactor cooling water will be decreased with a resulting opportunity for increase in flow through the reactor. The amount that this flow could be increased is limited by the capacity of the B water plant as well as the reactor itself. It is possible that there will be a shortage of filtered water at 183-B during the critical periods of each year. To overcome this possible shortage of water it has been proposed to construct a thirty inch tie line from the 183-C reservoir to the 183-B clear-well to supply filtered water to 183-B by gravity flow from 183-C. This report presents justification and the scope of this project.

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This document summarizes activities of the Hanford Atomic Products Operation during 1955.

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The action and emission spectra of the delayed light emission from Chlorella, Nostoc, and spinach chloroplasts have been measured. The action spectra for Chlorella and for spinach chloroplasts are quite similar to the absorption spectra of these materials. The action spectrum for Nostoc, on the other hand, shows a relatively low activity for chlorophyll and carotenoids and a high activity for phycocyanin. The emission spectra of these materials demonstrates that the luminescence is the result of a transition between the first excited singlet state and the ground state of chlorophyll. Low-temperature studies suggest that the triplet state of chlorophyll is not involved at all in the luminescence of spinach chloroplasts. There is some indication that part of the light emitted from Nostoc is due to a phycocyanin transition.

In the reference letter and later letters the author made recommendations pertaining to the programs of AEC National Laboratories and other AEC contractors in direct support of the Savannah River project during FY-1956. He believes that these recommendations should now be revised in view of schedule changes ad in the light of accumulated experience. The estimated cost of the programs recommended earlier totaled $2,083,000 for FY-1956. The estimated cost of programs currently recommended total $2,048,000 for FY-1956. The programs mentioned in succeeding paragraphs are concerned mainly with the development of processes for producing extended surface fuel elements and, to a lesser extent, with the development of separations processes. The author considers these particular supporting programs important to the rapid and successful achievement of development objectives at the Savannah River Plant and accordingly recommend that the Commission sustain them. Two of the programs, specifically the work by Sylvania and by Horizons to develop processes for reducing thorium oxide to metal, are not now associated with meeting future production objectives at the Savannah River Plant. The author believes that these programs should be brought to an orderly conclusion, as previously planned, to avoid any loss of the art developed to date.

The Al-rich corner of the ternary alloy system Al-- Th-U has been investigated by thermal and microscopic The creep properties of annealed Zircaloy- 2, Zircaloy3, and 15% cold-worked Zircaloy-2 at elevated temperatures were determined. The metallurgical bond formed between electropolished U and Zr cladding by hydrostatic pressing is being evaluated. Oxidation data are given for Nb and Nb alloys in dry air at various temperatures. A study of the phase relationships which occur between the please delete the above abstract===================== analyses to determine an area of low-melting alloys that could be used as a liquid metal fuel in U/sup 233/ breeder reactors. A phase diagram of this Al-rich corner of the system has been proposed. The data indicate that the binary eutectic valleys from the Al-- U and Al--Th systems meet at a point in the neighborhood of the composition of 76 wt.% Al, 18 wt.% Th, and 6 wt.% U to give a ternary eutectic which solidifies at 630 deg C. Although microstructures indicate two different primary phases as required, a third binary valley leading to this ternary eutectic has not been established. Results of the investigation show that there is a rather wide range of compositions of U …

The objective of this report is to review the performance of the Redox air-filtration facilities and to present recommendations, resulting from this survey, which could improve the ventilation systems of future Separations Plants. 4 refs., 3 figs., 2 tabs.

A technique based on a determinaiion of the differential counting rate exhibited by the 184-kev gamma radiation associated with the decay of U/sup 235/ was developed for the determination of the U/sup 235/ content in Argonne Low Power Reactor fuel element core blanks. The Argonne Low Power Reactor core blanks were an aluminum-highly enriched uranium alloy containing 17.5 weight per cent uranium (approximately 4 g U/sup 235/) having the following dimensions: length, 6.875 inches, width, 3.31 inches, and thickness, 0.200 inch. The gamma- ray spectrum emitied by uranium is rather complex. Using a scintillation spectrometer and scanning the spectrum, the energy is found to be concentrated primarily in two regions, at 184 and 90 kev. The 184-kev gamma rays result primarily from the decay of U/sup 235/ The gammas in the 90-kev region result from the U/sup 235/ decay and daughter products of U/sup 238/ and U/sup 235/. Using a pulse-height analyzer, it is possibie to select the desired radiation emitted from the source and determine the counting rate for a given source. In this work the 184-kev gamma radiation was counted to determine the amount of U/ sup 235/ present in the individual core blanks. (auth)

An archaeological field study was conducted along the Green River in the areas of Little Hole and Browns Park in Utah and Colorado. The purpose of the study was to measure the potential for hydropower operations at Flaming Gorge Dam to directly or indirectly affect archaeological sites in the study area. Thirty-four known sites were relocated, and six new sites were recorded. Information was collected at each site regarding location, description, geomorphic setting, sedimentary context, vegetation, slope, distance from river, elevation above river level, and site condition. Matching the hydrologic projections of river level and sediment load with the geomorphic and sedimentary context at specific site locations indicated that eight sites were in areas with a high potential for erosion.

The expected maximum contamination of the HNPF cold traps and primary sodium pumps was determined along with the maximum dose rates from these components during removal and shipping. Suitable shielding for casks to be used in the removal operation and for shipping these components away from the reactor site is specified. Access to an unshielded cold trap is limited by high dose rates, i.e., 100 mr/hr at 120 ft, after 180 days decay time. A handling cask providing a radial shield of 3 in. of lead will provide adequate personnel protection for the removal operation, if 180 days decay time is allowed before the trap is removed. An additional 2.4 in. of lead is required for offsite shipment of the cask. This additional shielding can be added after the trap is removed from the reactor building. Dose rates from the cold trap after the shield plug is removed from the access hole are shown. If direct line-ofsight exposure is avoided, dose rates to personnel will be below 100 mr/hr at any position, and below 10 mr/hr at distances greater than 20 ft from the access hole. Dose rates from the cask during its travel away from the hole, will be …

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In connection with the antiproton investigation at the Bevatron we planned and carried out a photographic-emulsion exposure in a magnetically selected beam of negative particles. The magnetic system was identical to the first half (one deflecting magnet and one magnetic lens) of the system used in the antiproton experiment of Chamberlain, Segre, Wiegand, and Ypsilantis. The selected particles left the copper target in the forward direction with momentum 1.09 Bev/c.

The possible means of removing aluminum jackets from uranium slugs were considered before Hanford start-up in 1944, and have been considered at other sites for processing other types of slugs. The sodium hydroxide-sodium nitrate dissolution, which served well for Bismuth Phosphate plant operation was accepted for use in the Redox plant. The other means of jacket removal, namely, dissolving the jacket in nitric acid with the aid of mercury as a catalyst, has been adapted for use at Arco and offers certain possible advantages for Redox Plant operation. The primary purpose of this document is three-fold: To report exploratory experimental work performed to date in the Process Chemistry laboratories on the study of the dissolving reaction and the properties of the resultant feed solution; to present a summary of the status of related work at other sites and by other groups at the site, as determined from a survey of the available literature references; to outline questions yet to be answered before the process may be used in the Redox Plant and a program to be followed to answer these questions.

The status of various projects undertaken to assist other scientists at ANL is reviewed. (T.R.H.)

The purpose of this report is to present the derivation of equations useful as a guide for prediction of the critical flow point in orifice assemblies.

This report talks about Argonne 7.7- Meter Bent Crystal Ganna- Ray Spectrometer