This report addresses two inspection systems that have been constructed which use strain gage pressure transducers to pick up changes in static pressure due to change in the hole diameter.

The purpose of this report is to provide a brief written description of the facilities existing at Hanford for research and development in the fields of heat transfer and hydraulics.

A probe for measurement of the space between fuel plates in high-burnup MTR-type fuel elements by eddycurrent techniques is described/su The sensing section is supported near the end of a flattened stainless steel tube into which a rectangular hole was cut to receive it/su The sensing section consists essentially of two slightly bowed springs, the midsections of which protrude slightly above the upper and lower surfaces of the flattened tube. Each spring- carries a section of a ball bearing as the contact point/su It is these two slightly bowed springs that serve as expanding calipers sensing variations in the spacing between adjacent plates. Essentially the rest of the probe is a long handle to permit probing and a conduit for the electrical leads. A two-wire shielded cable is firmly attached to the unflattened end of the probe and then attached to a modified Wheatstone bridge, from which the output is fed into a chart recorder. (M.C.G.)

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From abstract: "Bis(di-n-hexylphosphinyl)methane, HDPM, [(C6H13)2P(O)]2CH2, has been studied as an extractant for a variety of metals. HDPM was evaluated as an extractant for uranium(VI) and compared with tri-n-octylphosphine oxide, TOPO, (C8H13)3PO. In nonpolar solvents, HDPM forms a polymeric-like substance with compounds of uranium(VI). Viscosity measurements indicate that the molecular weight of this polymeric-like substance is about 100 times greater than the corresponding complex with TOPO. Polymer formation occurs only when nonpolar solvents are used as diluents for HDPM and is easily avoided by using polar solvents such as 1,2-aichlorobenzene. HDPM forms 1:1 and 2:1 complexes with uranium(VI) nitrate. Equilibrium constants for these complexes as well as that for the 2:1 TOPO complex were calculated and it was shown that the over-all constant is at least ten times larger for the HDPM complex than for the TOPO complex. The effect of concentration of various mineral acids, extractant concentration, temperature, and diluents on the extraction of uranium are discussed."

The following report is one of a series of quarterly reports following the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between January 1 to March 31, 1961.

The failure mechanics of high exposure, in-reactor coextruded fuel rods are quite different from those of defected unirradiated rods. The appearance and corrosion behavior of the high-exposure in-reactor failures suggests that the strength of the coextruded Zircaloy-2 to uranium bond has deteriorated. Notch-fracture tests, in which the strength of the Zircaloy-2 clad to uranium bond is evaluated in a qualitative manner, suggests that the bond strength has not deteriorated to the degree indicated by the failure behavior. It is believed that the irradiation induced property changes of the uranium fuel and not a deterioration of the character of the bond are responsible for the difference in irradiated and unirradiated failure behavior.

Abstract: "This quarterly report, ARF 1194-10, covers the work performed in the time period December 15, 1961 to March 14, 1962, on Contract No. AT(11-1)-578. In this period, Phase II, the detailed evaluation of various fields of radioisotope research, has been extended. Preliminary results on the use of radioisotopes in the industrial applications, apparatus and techniques, and metallurgy categories are presented. These preliminary studies indicate the quantity of research, growth rates, and specialized areas of interest in various countries of the world. More detailed evaluations of these categories will be presented in the final report."

The dynamic (gas saturation) method was used to determine upper and lower limits for the dissociation pressure of the complex formed when MoF/sub 6/ is absorbed by NaF. The limits were 0.4 to 4.6 mm Hg at 100 deg C and 8.4 to 27 mm Hg at 150 deg C. A lower limit, 64 mm Hg, was determined at 200 deg C. As a check on the method the dissociation pressure of the complex UF/sub 6/ - (NaF)/ sub 3/ was determined at 100, 200, and 240 deg C. The measured values were in satisfactory agreement with accepted values of dissociation pressure for this compound. (auth)

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The purpose of this report is to formally document interim power level recommendations for the old reactors consistent with the current tube replacement program. These recommendations were informally presented to Processing Operations by Process Engineering.

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A total of 68 Swiss albino mice of either sex were thy; mectoraized at the following time intervals after birth: 22 during day one, 21 during day two, 17 on day four and 8 on day eight. Sixty-one nonoperated litter-rnates served as controls. All mice were given primary andtigenic stimulation with adsorbed tetanus toxoids when four weeks of age. Three weeks later a booster injection of fluid tetanus tokoid was given. With these time intervals thymectomized mice showed only slightly impaired primary responses but severely repressed secondary responses as compared to nonoperated litter-mates. This uncommon finding is difficult to explain at present and results are discussed with regard to other reports on the effect of postnatal thymectoniy on immune responses. Special emphasis is placed on the unknown effect of postthymectomy wasting syndrome. (auth)

The power calculator at C Reactor and the process pump flowmeters at 190-C use orifice plates as primary sensing elements. These orifices were designed for considerably less flow and at the present higher flows, the reactor riser pressure is appreciably reduced as the result of the inefficiency of the orifices. Only a portion of the differential pressure across an orifice is recovered. The amount is dependent upon the ratio of the orifice diameter to pipe diameter. The permanent loss across these two orifices is 16 psi. The permanent pressure loss resulting from properly sized venturi elements would be 1.6 psi, for a resultant decrease in system pumping resistance of 14 to 15 psi. This would permit higher process water flow and reactor power levels.

From foreword: The purpose of this conceptual design is to outline criteria for the selection and development of a reactor plant with a fossil fuel fired superheater, a conventional generator plant and auxilary systems constituting a complete operating unit capable of producing a gross electrical power output of 22,000 kw.

A survey was made to select the construction materials for the SDR-1 reactor core vessel and grid plates. Hastelloy C was selected for the reactor vessel, top grid plate, and bottom grid plate. Inconel X was selected for the core hold-down springs. (C.J.G.)

The solution photochemistry of chlorophyll and chlorophyll analogs is described. Many cases of electron transfer to or from the porphyrin macrocycle have been found, but in no case has any very large degree of energy storage been achieved. Because of the very rapid back-reaction for products with a {Delta}F of approximately -30 kcal, some solid state models in which such an energy storage might be achieved are described and their possible relation to the natural photosynthetic apparatus is given. We can see that while the solid state model (phthalocyanine) allows an approach from a somewhat different point of view, the net result is the same as what was sought, but so far not found, when we looked at the solution chemistry of chlorophyll (and chlorophyll model substances), namely, the transfer of an electron, or hydrogen atom, from the excited porphyrin to an electron acceptor at a high reduction level which can be used to reduce the ultimate carbon dioxide reducers, followed by the donation of an electron ultimately from water to the remaining radical ion, or lattice, which produces the net results of the transfer of the hydrogen from water to carbon dioxide.

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The attached pages show the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials. For further description of column headings and the current discharge goal exposure plan the reader is referred elsewhere.

This document shows the status of production test control tube loadings (at Hanford) in reactor process tubes containing significant amounts of SS materials. This information is entirely numerical and is presented in the form of computer printouts. For additional information on the column headings and the current discharge goal plan, refer to document DUN-1048.

Using a simplified model, calculations were made of the possible effects of voids upon the power density in ORR loop experiments. It is concluded that the power density may be markedly increased if voids and channels are plugged with moderator material such as graphite or beryllium. (auth)

The fuel value of U/sup 233/ was calculated for five thermal reactors (Dresden. Yankee, Carolinas-Vlrginia, Hallam, GCR-II). Relative to a U/sup 235/ value of per gram, pure U/sup 233/ had a value that varied from .2 to .2 per gram. U/sup 233/ contained in once- and twice-recycle uranium from an initial U/sup 233/-Th cycle had a value slightly in excess of the value of pure U/ sup 233.. The value of U/sup 233/ in recycle uranium from an initial U/sup 235/- Th cycle was less than that for pure U/sup 233/ and decreased with each succeeding cycle. (auth)

This report consists summary of major federal consumer protection laws.

This report provides brief summary of the main provisions of the principal Federal consumer protection laws enacted from 1906 to 1968.