Data taken on radiation traverse of the Mark 1 control rod were analyzed. Future radiation levels for all SRE control and safety rods were predicted from this. The shielding necessary to ship a complete rod and that necessary to protect a person doing maintenance work on these rods were calculated. The unshielded gamma dose rate 1 cm from the surface of the most highly activated portion of the control rod was calculated to be 5.0 x 10/sup 4/ r/hr 14 days after shutdown following an extended power run of 90 days duration. (M.C.G.)

Geologic and radiometric investigations of the CuzcoAyaviri region in southern Peru were made in a search for geologic features or structures which might be favorable for the occurrence of uranium. Outcrops consist of Lower Paleozoic sedimentary and metamorphic rocks; Permian to Carboniferous volcanic flows, tuffs, breccia and agglomerate, together with sedimentary rocks; and Cretaceous and sedimentary rocks. Cretaceous to Tertiary igneous rocks are acidic intrusives and extrusive rhyolite, dacite and trachyte. Tertiary to Quaternary volcanic tuffs, breccias and agglomerates are also present. Although no anomalous radioactivity was observed, favorable geologic features for the occurrence of uranium were noted at two localities. (auth)

This report has been prepared in answer to the request from the AEC contained in the letter of October 1, 1957, from A. T. Gifford, HOO to A. B. Greninger. As requested, the report is of a summary nature and a more complete discussion of many of the points considered will be found in the references listed. The report is directed primarily at C reactor but some discussion of the other reactors is also included. A description of the proposed utilization of I E slugs in C reactor together with the associated power increase schedule is presented below. The reasons for changing to the I E element are presented together with a comparison of solid and I E slugs in the C reactor. The changes being made in C reactor under CG 600 are described. The operational characteristics of the C reactor using solid and I E elements are compared and finally the nuclear safety status of all of the Hanford reactors assuming I E loadings is reviewed.

This is the monthly report for the Hanford Laboratories Operation, September, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

This report describes the operation of the fuels preparation department for the month of September, 1957. Manufacturing employee relations, process development, plant improvements and financial operations are described.

The September, 1957 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation.

This report details activities of the irradiation department during the month of September, 1957. The report is divided into the following sections: Research and Engineering operations; Production and Reactor Operations; Facilities Engineering Operations; Employee Relations Operations; and Financial Operation.

The status of the overall schedule for design, fabrication, and installation of the component items of the PAR loop experiment in the ORR has been brought up to date and reviewed. This is the first review since the original issue of the schedule

Since the issuance of the Purex Phase II flowsheet a number of improvements have been suggested and additional information has been obtained. The purpose of this document is to summarize the more recent information and to bring the two-cycle chemical flowsheet up to date. Later changes will be similarly documented. The Phase II terminology has been dropped as the primary objective of the two-cycle conversion is economy rather than capacity. As mentioned in reference (1), the flowsheet has been designed to best use existing equipment and does not necessarily represent the optimum flowsheet for new plant construction.

The masses of the isotopes of the heaviest elements have been calculated from known decay data in the region, extended by means of decay energies calculated from closed decay-energy cycles and estimated from the systematics of alpha and beta decay energies. The absolute values of the masses are based on the mass-spectrometrically determined mass of Pb{sup 208} and a few measured neutron binding energies. The half-life systematics of alpha decay and spontaneous fission are also presented, and some predictions of the properties of as yet undiscovered nuclides are made.

None

None

None

This report covers the unclassified research progress of the Laboratory Abstracts only are given for research activities being reported concurrently in the scientific journals.

None

It is proposed that neutralized ORNL storage tank supernate waste be used as a feed for a waste processing development facility. An electrolytic cell can be installed to remove nitrate and ruthenium from the wastes prior to discharge to the soil disposal pits. This eliminates the hazards of nitrate and ruthenium in the ORNL soil disposal pits. In addition, a continuous ion exchange unit can be installed to study the isolation of fission products from a portion of the waste stream. The total waste stream can be processed by the ion exchange if desired. A six to eight inch diameter continuous ion exchange contactor is considered sufficient to remove cesium, strontium, and rare earths from 5,000 to 10,000 gallons of waste per day. The estimated installed cost of such a unit is about ,000. The labor and chemical operating cost at 100% overhead is estimated at .50 per day. Three types of electrolytic cells were considered. All of the cells remove about 90% of the ruthenium by plating on the cathode. It is expected that the degree of ruthenium removed may be increased by further laboratory development. The first cell type is the Ionics cell which converts NaNO/sub 3/ to …

The over-all design of the Argonne Low Power Reactor is presented. Detailed design data are given as well as information concerning the hydrology, seismology, and meteorology of the building site (NRTS). In addition, a description of the reactor instrumentation and control, mechanical design, heat transfer, and related physics are presented. A full description of the power plant, including the steam and electrical systems, is also given, as well as the operating procedure for both normal and emergency conditions. Over-all reac tor safety is evaluated. Diagrams and graphs are included. (J.R.D.)

The continuous dissolution of 304 stainless steel and stainless steel - UO/sub 2/ alloy in dilute aqua regia was studied with subsequent stripping of the dissolver product to remove chloride ion. The process has the advantage of producing, by means of a simple head end treatment, a solvent extract feed in a conventional nitric acid medium so that existing solvent extraction processes, materials of construction and waste disposal methods can be used. The purposes of this study were to investigate the the variables affecting the dissolution process and to obtain dissolver scale-up data, and to investigate the removal of chloride from the dissolver product and the variables affecting the stripping operation. A continuous flooded pot dissolver was used. It has the advantages of stability of operation and ease of control in comparison with column dissolvers and requires a minimum of mechanical processing prior to dissolution. Stripping of the dissolver prcduct to remove chloride ion was studied in a 4-in. diameter Pyrek bubblecap column containing 12 single babble cap plates. Continuous dissolution rates and dissolver product stainiess steel loadings were correlatsd with aqua regla feed composition, acid feed rats and surface area exposed to reaction. Profiles of chloride concentration down the …

A Darex flowsheet is presented wherein dissolution of stainiess steel- type fuel elements in dilute aqua regia, stripping of chloride from spent dissolver solution, adjustment of stripper product composition and rectification of HNO/sub 3/ --H/sub 2/O vapors are accomplished in a completely continuous relatively simple loop process. Product from the loop needs only dilution with water to be made suitable as feed for a solvent extraction processing plant. The proposed scheme differs from earlier concepts. A continuous, pot dissolver (well- mixed liquid phase) is utilized rather than a trickle type dissolver. A strip vapor slightly lower in HNO/sub 3/ concentration than the azeotrope is used. A feed adjustment tank serves not only to recover HNO/sbu 3/ --H/sub 2/O vapor, but also to dehydrate any silica present and to adjust the product composition such that upon water addition the material is ready for feed to solvent extraction. In most previous concepts, separate, batchwise feed adjustment was contemplated. (auth)

None

None

This progress report has 2 parts. Part 1 PWR Engineering covers the following topics: (1) power plant analysis and systems; (2) power plant components and component materials and tests; and (3) reactor and auxiliaries. Part 2 PWR Development covers: (1) fuel element development; (2) metallurgy of core materials; (3) materials application development; (4) chemistry development; (5) irradiation effects; and (6) reactor physics.

None

The phrase "composite control rod" is used to describe a hafnium-tipped titanium-boron control component with a titanium cladding. Blades for such cortrol rods were successfully prepared in cooperation with the Battelle Memorial Institute by a picture-frame rolling technique. The rolling packs, which are machined from type 304 stainless steel, contain slntered titanium boron and wrought hafnium core materials in a commercially pure titanium envelope. Such packs are evacuated, sealod off, and rolled at 16O0 F with a total reduction of 3/1 using 20% reduction per roll setting. Postfabrication treatments include mechanical removal of the stainless steel envelope, flat annealing, machining, and stress relief annealing. Data on the mechanical properties, corrosion performance, thermal cycling resistance, and irradiation damage resistance of composite control rod components are presented. This information strongly indicates that composite control rods will perform satisfactorily in water-coolod reactors. (aut)h