An analysis of outstanding problems still presenting difficulty with respect to understanding the quantumconversion process in photosynthesis is presented. Considerations of how some of these difficulties may be overcome are included. The dynamic process of energy conversion is considered in terms of photon absorption, electronic energy transfer, trapping in long-lived excited states, primary oxidants and reductants, and the electron transport chain leading to products representing stored chemical potential. The physical structure of the apparatus accomplishing this energy conversion is sought in the framework of the concept of the photosynthetic unit. The nature of this unit--its size, composition, arrangement and orientation of components, internal electrical and polarizability properties, and assembly and aggregation in the chloroplast--and the problems related to its determination are essential considerations in the overall approach to the understanding of the mechanism of energy conversion. (auth)

A total of twenty papers and one roundtable discussion were presented. Separate abstracts were prepared for eighteen of the papers. The papers for which no abstracts were prepared are concerned with impact energy sorption by large shipping casks, design of a Pu and enriched U shipping container, and the roundtable discussion on regulatory standards. (J.R.D.)

A nondestructive method was developed for measuring the spacings at the ends of fuel rods in completed SNAP fuel elements. A precisely aligned radiographic technique is employed to form an undistorted image on extra fine grain radiographic film. The end gap is then measured with a 20 x measuring microscope. The radiographic technique, alignment gages, and film reading methods are described for measuring gaps at the blend end and blind end of the fuel elements. The accuracy of measurements at the blend end ranges from plus or minus 0.0005 in. for spacings up to 0.010 in. to plus or minus 0.002 in. for spacings above 0.025 in. The accuracy at the blind end is about one-half that at the blend end. (auth)

Results of chemical and radiochemical analyses of Clinch River water, animal life, and sediments are presented for the period May to October 1961. Surface-water hydrology included establishment and operation of gaging stations and stream-flow studies. (R.J.S.)

A noncanonical transformation of the boson creation and annihilation operators is performed in order to obtain a Hamiltonian which can be treated by the standard methods of field-theoretic perturbation theory. The standard results of Belyaev (with a slight modification) are rederived by this technique. (auth)

Several 300 series stainless steels were corrosion tested in raffinate storage tanks made of the same materials. After exposure to the rafflnate solutions for periods of up to seven years, maximum penetration rates of 0.1 mil/ yr were noted. (auth)

None

A total of twenty-eight papers was presented at the meeting. Nine of these papers were previously abstracted in NSA. Separate abstracts were prepared for nineteen papers. (J.R.D.)

An analysis dealing with view factors is presented in an investigation of the overall interchange factors for heat radiation. Examples concerning the EGCR and the Peach Bottom Reactor are included. (J.R.D.)

The effects of various parameters on the transport propenties of dissociating gaseous mixtures were studied. In order to take advantage of the increase in thermal conductivity and specific heat due to the dissociation, the heat of dissociation must be large,'' the molecular weight and molecular volume must be small, and both associated and dissociated molecules must be present in appreciable amounts at reasonable temperatures. Very few dissociation reactions meet all of these requirements. In order to illustrate the effects of dissociation on many properties, estimates were made for the thermal conductivity, specific heat, specific volume, and viscosity of helium-- aluminum chloride and helium--fluorine mixtures as a function of temperature at various pressures and compositions. The maxima in the thermal conductivity and specific heat curves, which are due to the heat of dissociation, can be varied over a wide range of temperatures by controlling the pressure and helium concertration. The dissociation produces a greater than linear increase in specific volume with increasing temperature. According to the calculations, a helium-- fluorine mixture has a thermal conductivity and specific heat which can be as much as a factor of two greater than the corresponding values for pure helium, while the viscosity of the …

None

Two type-AUC graphite fuel elements loaded by solution impregnation to an average concentration of 0.115 g/cc of 93.13% enriched U converted to UC and UC/sub 2/ were irradiated at temperatures of about 1500 deg C to a 10.2% maximum burnup, corresponding to an irradiation level of 219 kwh/cc or 2.45 x 10/sup 19/ fissions/cc of fuel element. Post-irradiation measurements of the elements showed dimensional changes of -4.3 and -4.8% with the grain, and --0.8 to -2.5% across the grain. Weight losses were 3.2 and 5.1% for the individual elements with approximately 11% of the total U being lost from the elements. With-the- grain thermal conductivity at nominal room temperature was reduced by a factor of approximates 7 and electrical conductivities by factors of 3.4 to 8.3, also at room temperature. Impact strength appeared to be somewhat improved by irradiation. Migration of U within the element was detected by radiographic density observations but not evaluated quantitatively. As anticipated, fission product release was high. (auth)

Activities in a program to assemble and test jacketed fuel rods and multi-rod fuel rod assemblies for EBR-II are reported. Other work is reported on evaluation of the manufacturing techniques proposed for the EBR-II cycle in a sustained operation and on remotely operable equipment under production conditions. Data on fabrication and assembly of fuel rods and assemblies are included. A total of 10,781 fully inspected fuel rods were fabricated for EBR-II core by processes adaptable to remote operation. (J.R.D.)

Progress is reported in MSRE design, engineering analysis, component development, metallurgy, in-pile tests, chemistry, fuel processing and in thermophysical properties of salt mixtures. (J.R.D.)

The results of a study of the installation and operational characteristics of a SNAP reactor system integrated with a manned space station are presented. The reference system selected was an 11 kw(e) version of a SNAP 2 system employing multiple power conversion units coupled to a single reactor source. Of prime importance is the reactor radiation shield required for the manned system and the use of design features which minimize the shield weight. The weight of the radiation shield is highly dependent upon the geometrical configuration of the space station and the reactor since shadow'' shielding of the manned compartments is required for minimum weight systems. The installation and shielding requirements of the 11 kw(e) system were considered for two types of space station configurations; one was a 10 ft dia cylindrical station with a reactor separation distance of 50 ft and the other a 150 ft dia toroidal station with the reactor located in the hub. The weight of the power system installed in the cylindrical space station was about 9000 lb of which 6000 lb was required for shielding. The weight of the system for a toroidal station was approximates 25,000 lbs of which 20,000 lbs was required …

Urania-neodymia compositions were sintered in air and in hydrogen. The compositions were studied by chemical, x ray, and differential thermal analyses. Solid solutions formed readily in air-sintered compositions in the range from 20 to 60 m/o Nd/sub 2/O/sub 3/. Solid solutions formed slowly and incompletely, up to 1650 deg C, in hydrogen-sintered compositions. There was good correlation between the differential thermal analyses and the chemical and x ray analyses. (auth)

The He atmosphere system in Argonne's Facility 350 is described in detail. The system is straightforward, employing drying and carbon towers for the removal of moisture, oxygen, and other impurities. The bulk of the 15,000 ft/ sup 3/ of He atmosphere is continuously recirculated at nearly atmospheric pressure. Purification is accomplished at 140 psig on a portion of the gas that is passed through the drying tower at room temperature and the carbon towers at -- 46 deg C (--50 deg F). The operation is continuous, requiring a minimum of maintenance and operational manpower. The He atmosphere is supplied to the glove- boxes with impurity levels below 3,000 ppm nitrogen, 1,000 ppm oxygen, and 50 ppm moisture. Such purity levels prevent oxidation and combustion of the Pu materials being processed. Experimental data concerning the adsorption of oxygen from He by activated carbon over a range of temperature and pressure conditions are reported. (auth)

This report, from the Chemical Processing Department at HAPO for November 1962, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations, facilities engineering; research; employee relations; and weapons manufacturing operation.

This brief report (December, 1962) discusses the effect of effluents from the Hanford Production reactors on the water temperature of the Columbia River.

Complete parition functions for non-rigid rotators are obtained for the linear, spherical top, and symmetric top cases, From these are derived expression giving the corrections to the thermodynamic functions due to centrifugal distortion as functions of the rotational distortion constants D. Numerical examples are given for HCN, methane, and ammonia.

This document details activities of the Fuels Preparation Department during the month of November 1962.

None

Decontamination of a high-temperature pressurizedwater reactor core- coolant recirculation system following a fuel element cladding failure requires the dissolution of uranium oxides + uranium metal. An oxalic--peroxide-peracetic solution was developed which was found to be superior to other solutions for this task. The solution composition is: oxalic acid, 2.3 g/l: sodium oxalate, 32.0 g/ l; hydrogen peroxide, 15.0 g/l; 8-quinolinol, 1.0 g/l; and 40% peracetic acid, 12.5 g/l. 8-Quinolinol suppresses the decomposition of H/sub 2/O/sub 2/ in steel vessels. Corrosion data indicate that, of all the structural materials tested, only brass and brass alloys are corronded to any extent by this solution. This solution was used in the decontamination of the Plutonium Recycle Test Reactor. (D.L.C.)

Aqueous zirconium fuel processing studies, directed at adapting the hydrofluoric acid process to continuous dissolution-complexing in order to increase the capacity of the ICPP process, resulted in two successful approaches to the complexing-feed adjustment step. Continuous in-line adjustment (conversion of uranium(IV) to uranium(VI) necessary for extraction) was accomplished in one minute or less at approximately 90 deg C; surges of dissolver product from the operating dissolver up to 1.9 times the flow sheet rate did not inhibit the oxidation of the uranium at this temperature. Batchwise mixing in air of dissolver product solution with complexer solution oxidized the uranium within two minutes at 23 deg C or higher. Further studies of continuous zirconium dissolution indicated that precipitation of uranium at the acid inlet can be a problem, probably because of local concentration gradients of free HF, which result in conditions of low uranium solubility. Control of dissolver acid composition by electrical conductance measurement appeared possible due to the linear relationship of conductance with acid concentration. Aluminum alloy dissolution rates in nitric acid were found to vary significantly, depending on the type and amount of alloying agent. Silicon, nickel, and copper in the alloy significantly decreased the dissolution rate. Batch dissolution …