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)

A system of symbols and identifications for processinstrumentation equipment to promote a uniformity of practice is presented. The system is for the following uses: designation and identification of instruments on flow pInns; recording specifinations, listings, requisitions, and purchase orders; indication of items on piping diagrams and other construction drawings; identification tagging of equipment; and description in technical and trade literature. (J.S.R.)

This report summarizes the series of irradiations conducted in a Hanford reactor on specimens of zirconiumclad, uranium-- zirconium fuel plates containing 3, 6, and 14 vt.% highly (93.4%) enriched uranium. More than thirty fuel plates were exposed during the test program, which extended over a period of several years. (auth)

The ultimate achievement of a research and development program at Sandia. Corporation, as at any other AFX or DOD project, is the physical design of a component or weapon system of high reliability. The design accomplishment is initially established when the basic drawings and specifications are released for production. These drawings and specifications are often based on engineering evaluations of bread- .board and early so-called & quot;gold plated prototypes. However, the design accomplishment is not completed until the item is manufactured by production tools and performs satisfactorily, meeting all the requirements specified in the engineering and manufacturing information. It is only at this stage that we have initial assurance that we may proceed with quantity production. This transition from essentially handmade prototypes to a production-tooled reliable product is a crucial one in any design development program, but it is especially as when the end product is complex and extremely high reliability is required.

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 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)

Thermnl transients with total pulse times of 3 to 28 milliseconds were simulated by direct-current electrical heating in studies of the explosions of Ag, Al, Cu, Sn, U, Zn, and Zr specimens under water and under oil at an ambient temperature of 75 d F and at atmospheric pressure. Motion pictures were taken of many of the explosions at film speeds of 7,500 to 14,500 frames/sec. A 600-foot composite reel was prepared which shows 7 representative explosions and views of the equipment. Data for 34 runs, photographs, and photomicrographs are presented and discussed with respect to burnout, heat transfer, and metal-- water reaction. (auth)

Results are reported concerning studies of hydraulic cyclones (hydroclones) for application to particle size classification of ThO/sub 2/. Tests were run with a 0.50-in. diam. hydroclone. It was shown that a single pass through this hydroclone would reduce the material greater than 10 mu from 12 wt.% to less than 1% while the mean diameter was reduced from 1.7 to 0.9 mu . When the overflow (fine) fraction was again pumped through the hydroclone, the overflow solids from the second pass were 98 wt.% less than 2 mu in diameter. The mean diameter was reduced from 0.9 mu to about 0.7 mu by the second pass. A yield of 5 to 7 wt.% of solids (to the overflow streamn) and a ratio of overflow to feed volume of 0.25-0.30 were observed during the hydroclone tests. Although this low yield is undesirable, recommendations are made that would increase the yield sufficiently to make desirable the incorporation of hydroclones in the ThO/sub 2/ production flow sheet. (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)

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.)

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)

None

The study of the kinetics of layer growth in the aluminum -- nickel system and the effect thereon of applied pressure has been continued. Additional information has been obtained about the growth of the beta phase, and a method was developed whereby the kinetics of growth of the beta phase could be investigated. The implications of Vasileff's equations which provide the solution for interdiffusion in a three-phase two-component system have been examined semi-analytically, and quantitative insight has been gained into the kdnetics of interface movement. Finally, an investigation of the kinetics of interface movement and layer growth has been begun on systems which have less complicated phase equilibrium relationships than those existing in the aluminum -- nickel system. (auth)

Data are given on: creep propenties of 15% coldworked Zircaloy-2; the liquidus in Al-U; effect of chloride on corrosion of type 304 ELC stainless steel; corrosion testing of stainless steels, Ti 75A lead, and rigid PVC as container materials for HNO/sub 3/-recovery process; viscosities of MgF/sub 2/ and MgF/sub 2/-MgO slags; phase boundaries in the U-Zr-H system; oxidation of Nb, Nb-W, and Nb-V alloys in dry air at 1000 and 1200 deg C; nonoxidizing properties of UO/sub 2/- La/sub 2/O/sub 3/ and UO/sub 2/-Sc/sub 2/O/sub 3/; study of bounding fuedamentals; hydrogen adsorotion by Nb; diffusion of H in ZrH/sub 4/; reflector controlled heterogeneous boiling reactor; pressure bonding of Zircaloy- 2-clad compartmented UO/sub 2/ fuel plates for PWR; and evaluation of UC as reactor fuel. (For preceding period see BMI-1247.) (T.R.H.)

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)

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.

The reaction between uranium dioxide and aluminum has been studied at 600 deg C and below. At 600 deg C the visible reaction occurred within a few hours, while, for example, at 500 deg C and below, the specimens had to be at temperature for several days in order to show signs of any reaction. The method of manufacture of uranium dioxide had a pronounced effect on its compatibility. Granulated and high-fired oxides showed lowest, and the steam-treated oxide showed maximum, reactivity. The fact that finer oxide powder partlcles react faster than coarse ones was according to expectations. Mallinckrodt U/sub 3/O/ sub 8/ powder of very fine particle size reacted severely with aluminum during a 1 1/2-hr test at 610 deg C. (auth)

A search of the classified and unclassified literature concerning the degradation of a tributyl phosphate (TBP)-kerosene solvent has been conducted. Chemical Abstracts, Nuclesr Science Abstracts, Abstracts of Classified Reports, and the card file of the National Lead Company of Ohio's Library were included in the search. Pertinent information is presented, in abstract form, as it applies to extractant (TBP) degradation, diluent (kerosene) degradation, and solvent clean-up techniques. (auth)

Two simplified models are discussed in order to gain insight into the problems of a flux-trap reactor. The first model consists of source of fission neutrons, embedded into D/sub 2/O, Be, BeO, or C moderator, or a moderator of zero absorption cross section. The source is assumed not to absorb amy neutrons. This model gives five to eight times the thermal flux obtainable at the center of the fluxtrap reactor. The other model is a flux-trap reactor idealized by neglectimg all absorption in the moderator. This model does not differ markedly from the D/sub 2/Omoderator case. (auth)

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.)

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)

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)

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)

A stress analysis is presented of a spherical shell subjected to a line load acting along a latitude circle in a direction normal to the plane of that circle. (auth)