The schedule for the installation of the PAR slurry loop experiment in the ·South Facility af the ORR has been reviewed and revised. Changed design philosophy to include maintainability of the loop auxiliaries required extension of the main construction period to the end of,June, with a three month period ending in September, for test and run in during which construction will be completed.

The conceptual design of a 100 Mw(e) nuclear power plant is described. The plant utilized a sodium-cooled graphite-moderated reactor with stainless- steel clad. slightiy enriched UO/sub 2/ fuel. The reactor is provided with three main coolant circuits, and the steam cycle has three stages of regenerative heating. The plant control system allows automatic operation over the range of 20 to 100% load, or manual operation at all loads. The site, reactor, sodium systems, reactor auxiliaries, fuel handling, instrumentation, turbine-generator, buildings. and safety measures are described. Engineering drawings are included. (W.D.M.)

An outline of the major problems which have appeared in reliability research at Sandia Corporation is presented and generalizations based on this experience are discussed. (J.R.D.)

A helix constructed of plutonium was made to test the Doppler temperature effect in ZPR-III. The helix. 1 in. in diameter and 6 1/4 in. long. contained 240 g of deltaphase plutonium alloy encapsulated in titanium tubing. rour piutonium rods were extruded, joined together, and pushed into a titanium tube. This tube was swaged tightly over the piutonium rod. and the assembly was wound into a coil. Electrical leads to the coil were made by swaging copper tubing over the ends of the coil. The helix was tested by cycling about 500 times between 50 and 190 deg C. The coil was heated with a current of 130 amperes and cooled with a blast of chilled helium. Several helices of uranium were cycled during the same tests. Despite the severity of the thermal cycles. the helices were undamaged. (auth)

The niobium-uranium alloy is dissolved in hydrofluoric nitric acids and the fluoride removed by fuming sulfuric acid. The niobium is hydrolyzed in an acid-sulfur dioxide medium and converted to niobic oxide by ignition at 900 deg C. The method covers the determination of niobium in niobium-uranium alloys having a niobium content of 8 to 12%. Metals which hydrolyze readily in dilute acid solutions interfere with the determination. (auth)

Studies were made to determine the stress equations necessary for the design and analysis of the OMR Core Vessel Support Structure. A parameter study of these equations applicable to the present core vessel design was also made. (W.L.H.)

This report covers studies of the excretion and retention of 'tracer' and toxic doses of the 11.2-day Ra{sup 223} isotope, its acute toxicity (organ weight changes, gross and microscopic pathology, and Fe{sup 59} utilization by the bone marrow), and long-term histopathological changes and alterations in the hemogram.

Clad plate-type fuel elements containing U--5 wt.% Zr--1.5 wt.% Nb alloy cores integrally clad on all surfaces with Zircaloy-2 were developed for the Experimental Boiling Water Reactor (EBWR). These plates were prepared by roll bonding assembled components inside steel jackets at 850 deg C with 50% reduction in thickness to effect sound diffusion bonds at all component sufraces. To obtain reproducible sound bonds, uranium alloy core and cladding components were clean and free from surface contamination, such as inclusions, oxides, or other foreign material; contamination of mating surfaces was avoided during welding operations; all bonding surfaces were sealed to prevent contamination from outgassing of the steel jacket during heating and rolling; billets were designed with a differential thermal expansion allowance for the core relative to the cladding; and all assembled billet components were evacuated and sealed by welding in vacuum. Integrally rollbonded end closures were obtained by orienting billet end plugs so that the prior hot-working anisotropy of Zircaloy2 would increase their lateral spread and facilitate the Zircaloy-2 end to Zircaloy-2 side bonds during rolling. Investigations were made of alternate methods of bonding fuel shapes and the use of alternate core alloys in flat plates. Roll bonding in shaped pass …

A 1585 hr run was completed on the 400A-1 pump with a 0.4 m UC/sub 2/SO/ sub 4/ fuel solution as the pumped fluid, during which it was attempted to operate with gas bubbles in the solution. The gas content ranged from 0.56 ml/gm of solution to 1.189 mi/gm of solution and the gas other than CO/sub 2/, which was assumed to he nitrogen, varied from 0.39 ml/gm of solution to 0.966 ml/gm of solution. Because of uncertainties in the CO/sub 2/ solubility it cannot be stated conclusively that the liquid was or was not saturated. However, the loss of metal at a number of places due to corrosion and/or gas bubble erosion makes it advisable not to operate a pump of this exact design at or near gas saturation. The 1585 hr above are the last of 13185 hrs maintenance free operation. A general examination of the pump dlsclosed severe corrosion and softening of the Stellite 12 overlay on the 347 stainless steel thrust bearing shoes. The thermal barrier seal weld had cracked and there was noticeable corrosion in the region betwoeen the thermaI barrier gasket and metallic O'' ring seal. (auth)

Fuel-salt volumes external to the core of a molten-salt reactor are calculated for a system in which the fuel salt circulates through the core and primary exchanger by free convection. In the calculation of these volumes, the exchanger heights above the core top range from 5 to 20 ft. Coolants considered for the primary exchanger are a second molten salt and helium. External fuel holdup is found to be the same with either coolant. Two sets of terminal temperatures are selected for the helium. The first combination permits steam generation at 850 psia, 900 deg F. The second set is selected for a closed gas turbine cycle with an 1100 deg F turbine inlet temperature. Specific power (thermal kw/kg 235) is found to be about 900 Mv/kg, based on initial, clean conditions and a 60 Mw (thermal) output. A specific power of 1275 kw/kg is estimated for a forced convection system of the same rating. (auth)

The results of tests to determine the actual coolant flow through various core channels in the Oak Ridge Research Reactor are plotted, tabulated, and discussed. (M.H.R.)

Metullographic examinations of representative reactor components and coupons from HRP in-pile loop L-2-l7 are reported. The loop operated for a total of 1l36.8 hours at 300 deg C in beam hole HB-2 of the LITR. The results are discussed and tabulated. Photographs are also included. (J.R.D.)

During the examination of the pins from in-pile autoclave L6Z-114 it was noted that each of the doublenotched pins exhibited areas of increased corrosion while the exact duplicate single-notched pins did not. The two pairs of Zircaloy- 2 pins were identical in structure and thus the noted differencs in corrosive attack cannot be attributed to this factor. In the Zr-1.5% Sn--15% Nb pins the corrosive attack did not seem dependent on the slight variation in structure of the pins. (W. L.H.)

Some approximate values of the concentrations of the chlorine ion and the mean activity coefficients of HCl in Dowex 50, as functions of the mean activity of HCl are given. The KCl uptake by anion-exchange resins, Dowex 1 and 2, is plotted. Ion-exchange phase properties of HCl were determined from freezing point measurements. The thermodynamic acid dissociation constants of HClO/sub 4/, HCl, HNO/sub 3/, HBr, and HGaCl/sub 4/ in water-saturated bis(2- chloroethyl) ether, were obtained from couductometric measurements. The distribution behavior of InBr/sub 3/ and IuCl/sub 3/ in HBr and HCl was studied. Information is given on the extraction of Zn and Ag from chloride solutions by dioctylamine salts. Ion exchange equilibria between hexammino-cobalt(III) and chloro-pentammino-cobalt(In ions in respect to La ions in Dowex 50 NaR are plotted. Typical radiochemical activation analyses for K in geologic materials are tabulated. The postulated nuclear level scheme and the calculiated and experimental positron decay following ( gamma ,n) activation of Br/sup 79/ are shown for Br/sup 78/. Cumulative fission yields in the deuteron fission of U/sup 235/ are tabulated. Cosmic ray data obtained with a new highcounting rate meson monitor are plotted. The equipment used and data obtained in a search for long- …

A program is described for computing a quantity, Q, proportional to the neutron scalar flux, in an infinite heterogeneous slab system. The system is generated by a two-region unit cell. Q is the average track length per unit length, in a given interval, arising from the neutron traffic established by a spatially distributed monenergetic source. The program is coded for the IBM 704 computer. (auth)

A conceptual design is presented for the HRE-3 core and blanket pressurization systems. In general, the systems are similar to the preliminary designs previously described. Flowsheets, conceptual sketches, and specification = for the major components are included. Estimation oi the D/sub 2/ concentration in the blanket is treated in detail. The design appears to be safe with regards to the d/sub 2/ explosion hazard. (auth)

In laboratory scale experiments dilution of a Darex dissolver product from the integral dissolution of Yankee Atomic fuel specimens with at least an equal volume of 15.8M HNO/sub 3/, followed by distillation, produced a solvent extraction feed containing less than 50 ppm of chloride. Properly designed chloride stripping and nitric acid rectification columns are capable of conserving acids for recycle to the dissolver and chloride removal still. In initial experiments about 87% of the nitric acid and 36% of the hydrochloric acid were recovered. (auth)

In a series of 600 cutaneous burns in swine produced by radiant thermal energy at 0.5 and 5.0 sec exposure time, the relationship of thc surface appearance and the depth of damage of bare skin and subfabric burns was investigated. The fabrics used were a black and a gray sateen weighing 8 to 9 oz/ yd/sup 2/. It was found that there is no significant difference in the 1+ burns whether produced on bare skin or beneath fabric, either at 0.5 or 5.0 sec exposure. However, the 2+ subfabric burns average about 0.1 mm deeper in dermal damage than thc same grade barn of bare skin. Nevertheless, the protection afforded by fabric is found to be nearly the same whether the burns were judged by surface appearance or microscopically by depth of damage. (auth)

A series of im-pile fuel sample irradiation experiments was initiated to obtaim radiation damage information on fuel material combinations applicable to Foreign Reactor Program Fuel Elements where U/sup 235/ enrichment is limited to 20%. The series of expcriments will be divided into several phases, each being based on the materials combination employed. This report describes Phase I of the program which consists of determining the integrity and suitability of a 48 wt.% U--3 wt.% Si-49 wt.% Al alloy as a fuel for Foreign Reactor Fuel Elements. (auth)

The gamma and beta activity of the proposed HRE-3 slurry for blanket operation at 10 Mw has been estimated. The sources of activity were found to be fission-product decay and Pa/sup 233/ decay. The estimated gamma activity of the slurry is plotted, showing the Pa/sup 233/ gammas, four energy groups of fission products, and the total gamma activity for a nearly infinite irradiation time. For the same conditions, the estimated beta activity of the slurry is plotted, showing the Pa/sup 233/ betas, the fission product decay betas, and the total beta activity. (auth)

A summary is presented of available information on the nature of H embrittlement in Ti, its control, and effects on other Ti properties. Most data also apply to Zr. Types of embrittlement are discussed, along with H sources and effects on mechanical properties. Also, the effects of H on forming heat treatment, and joining are discussed as well as Ti production and processing and methods of H removal. Finally, H in-service pickup is considered, and methods for establishing the extent of this reaction are discussed. (J.R.D.)

A cost breakdown is given for stainless steel vs. zirconium in the Yankee Power Reactor. Zirconlum Production capacity is given for the U.S. along with zirconium priees. (W.L.H.)

None

A commercial light-weight portable bandsaw was fitted with a grip to permit it to be maneuvered remotely in a hot cell by means of a General Mills manipulator The bandsaw was supported in various positions to make cuts on typical pieces. Photographs show the saw in operation. (auth)