Techniques involving the use of high-intensity short-duration light pulses have been applied t o the study of the kinetics of photoconductivity in films of metal-free phthalocyanine. These experiments, in conjunction with measurements of steady-state photoconductivity, are consistent with the following scheme. The principal route for the formation of charge carriers is via the first excited singlet state, although the lowest triplet state can, t o some extent, contribute to charge - carrier production. The mobility of the carriers is low and is concentration-dependent, being lower at higher carrier concentration. The decay of the photocurrent is the result of a diffusion-limited bimolecular recombination, with a capture radius of approximately one molecular diameter. The experiments indicate that carriers produced thermally in the dark do not interact with light-produced carriers.

The addition of ortho-chloranil to the surface of films of metal-free phthalocyanine has been found (a) to increase the dark conductivity of such films by as much as 10{sup 7}, (b) to increase the steady-state photoconductivity by as much as 10{sup 5}, and (c) to result in the formation of unpaired electrons whose concentration decreases reversibly as a result of illumination. These systems exhibit a light-induced polarization, the phthalocyanine layer becoming more positive with respect t o the ortho-chloranil layer. Kinetic studies demonstrate that, upon illumination, a single process (time constant = 40 seconds) results in the increase in conductivity, the decrease in unpaired spins, and the increase in polarization. The results are consistent with the following scheme. An electron transfer from phthalocyanine to ortho-chloranil occurs in the dark at room temperature, producing holes in the phthalocyanine layer and ortho-chloranil negative ion radicals (high conductivity, ESR signal). Illumination results in the transfer of an electron from an excited phthalocyanine molecule to the ortho-chloranil negative ion, producing further phthalocyanine holes and ortho-chloranil double-negative ion (increase in conductivity, increase in polarization, decrease in ESR signal). By equating spin concentration with charge - carrier concentration (phthalocyanine holes) it is possible to calculate a …

This monthly document details activities of the Hanford Operations Office during the month of July 1959. (FI)

Several decisions regarding basic project philosophy must be made in order to proceed with scope design and the preparation of equipment procurement specifcations. The purpose of this document is to present as much pertinent data as possible to allow the project representatives to become familiar with the problems involved. A meeting of Representatives is planned for the near future after receipt of project authorization to discuss the scope of this project and its relationship to CG-775. Emergency flow requirements of the K reactors for planned future power levels is approximately 32,000 gpm within 68 sec. A detailed study of the existing high-pressure cross-tie line reveals that a duplicate cross-tie line and five low lift pump operation would be required to provide this flow. The existing emergency generation capacity is not adequate to supply five low lift pumps and all other necessary emergency electrical loads. A possible solution to adequate emergency flows is to connect the proposed steam turbine pump directly to the risers and to consider the turbine pump as the last ditch system. If it is determined that this does not meet the criteria of separate systems, then an alternate solution must be found.

Typical transient temperature curves for the reactor outlet coolant have been obtained for the cooldown period. Additional curves showing the relationship of several variables on the required heat exchanger area were obtained.

The objective of the test detailed in this report is to irradiate self-supported fuel elements under conditions of severity comparable in these expected for future loadings of this geometry, to attempt to determine the resistance to corrosion of cooled cladding, the effect of supports on cladding corrosion and coolant flow patterns, and the relative resistance to ``hot-spot`` type attack and rupture of ``projection`` fuel elements and rib supported elements. This test will authorize irradiation of four columns of self-supported and four columns of rib-supported I and E, 1.47% enriched fuel elements until two ruptures are sustained in each group on type demonstrates a significant factor of improvement in rupture resistance over the other.

Figures have and can be generated that indicate a higher charge-discharge rate if required before 105-N will be comparable with existing reactors. Also, these figures show an apparent operating cost incentive to increase the charge-discharge rates proposed for 105-N. Although these figures may be true by themselves, other figures developed from the same information and stated on a basis that affords a true comparison, show that the proposed rates for 105-N are compatible with those in existing reactors. However, the accomplishments of existing reactors should be considered as a guide only and not as Criteria since the design basis has already been established for Project CAI-816. An average charge-discharge rate has been proposed for 105-N that is compatible with the two main ground rules of the Project. Namely, the capital cost limitation and the plant factor. This rate of 8 tubes/hr. is one that appears to be reasonable from the charge-discharge design aspects and there is a good possibility that it can be increased with operational experience.

This document describes in detail the calculations that are basic to the xenon problem. While much of this work appears elsewhere, herein an attempt has been made to bring it together and make it as understandable as possible. The principle purpose of this document is to calculate the equilibrium xenon poisoning for the I and E geometry fuel element and compare the results to the equilibrium xenon poisoning for the solid geometry fuel element. Further objectives are to provide an understandable reference for those with interest in the basic xenon formulation, and to serve as a training guide for new personnel.

An evaluation was made of the use of NaK as the primary coolant for the SNAP-2 system. Pumping-power limitations based on the mercury Rankine cycle are analyzed. Problems pertinent to any design-specification modifications are reviewed.

The 234-5 Building ventilation exhaust is continuously sampled for the purpose of estimating the amount of radioactive (alpha emitting) material discharged to the atmosphere. Although a record is kept of the gross amount of radioactive material discharged, few data are available concerning the size and kind of active particles in the exhaust air. Knowledge of the particle size permits: (1) an estimate of the validity of samples drawn through the sampling system, (2) a better knowledge of what the active particle ground deposition pattern might be, and (3) may provide information relating to filter performance. The kind of radioactive material discharged is important in determining relative health hazards. The object of this work was to determine the size and kind of radioactive particles in the 234-5 Building ventilation exhaust. A secondary objective was to review present routine sampling of the stream with particular regard to the particulates to be sampled.

The Palmolive program is directed toward the recovery of neptunium-237 and production of plutonium-238. The neptunium is recovered during the chemical processing of irradiated uranium and is purified and fabricated into target elements. The target elements are irradiated to produce plutonium-238 by neutron capture of neptunium-237 and are processed to provide plutonium for shipment to the final customer and neptunium for recycle within the system. This report summarizes a preliminary engineering study of the technical and economic factors involved in installing long-term Palmolive manufacturing facilities at Hanford to meet the reduced production goals. Prime emphasis is placed on the process technology and plant equipment requirements for fabricating and reprocessing neptunium target elements on a production basis. The relationships of these phases of the target cycle to the recovery and purification of virgin neptunium in the Purex Plant and irradiation of target elements in the Hanford reactors are reviewed in the light of the reduced plutonium-238 demands.

The specifications given in this document cover the processing of E-Metal. E-Metal is defined as natural uranium which has been enriched with U-235 to a concentration of 0.95 percent. The higher U-235 content makes the E-Metal more reactive than either natural or irradiated natural uranium. This difference in reactivity places a definite limit on the amount of massive metal that can be charged to the present Redox dissolvers. Once the slugs have been dissolved, the processing of E-Metal is essentially the same as the processing of natural uranium. Thus, except for the dissolver charge size, the following specifications reflect few actual changes in numerical limits. One change that needs to be recognized is that the amount of U-235 plus plutonium in the metal solution is much closer to the maximum {open_quotes}always safe{close_quotes} ratio than with irradiated natural uranium. Once the E-Metal uranium has been separated from its accompanying plutonium, no critical mass of uranium can be assembled because the enrichment is below the minimum critical.

Sufficient changes in the original projection fuel testing schedule have occurred to make the original schedules confusing. It is the intent of this document to revise an up-date those schedules so as to be a more realistic guide for associated development programs.

This document has been written in part to answer questions concerning the feasibility and advisability of ``quickie`` discharge of ruptures at C Reactor. Justification of full pile operational charge-discharge (OC-D) is based in part on outage savings resulting from improved, rupture removal. Since a portion of the rupture removals might be accomplished within the scram recovery time (quickie) it is necessary to consider recovery time as a function of anticipated future power levels. In addition to answering the questions mentioned above, it was felt worthwhile at this time to discuss equilibrium control problems associated with OC-D which have been apparent during operation of prototype equipment, and on the basis of this information to consider reactor control with full pile OC-D.

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The self-diffusion coefficient or uranium was measured at four temperatures in the gamma phase. The data are fitted by an Arrhenius-tyoe equation D = 2.33 x well with previously reported results. The value of D/sub o/ is lower than that predicted by Zener's theory, and the activation energy is much less than the value expected from various empirical codelations. (auth)

The effects on variations of Al content, heat treatment, and basic slip mechanism upon the room-temperature ductility of Fe-Al alloys of are being determined. (W.L.H.)

An evaluation of the temperature excursion and its possible consequences arising from loss of coolant from the Plutonium Recycle Test Reactor (PRTR) was made for four different postulated ruptures in the primary heavy water coolant system. As a basis for the evaluation, a series of computations was made. These were based on incremental heat and mass balances for sections of Zircaloy-clad UO/ sub 2/and Pu- Al fuel elements. Solutions to each problem defined by the postulated break size and its location were defined by finitedifference approximatioms performed by an IBM 653 machine digital computer. The four postulated ruptures were: (1) a complete parting of the 14-in.-diameter outlet pipe near the upper ring header so that coolant would be lost from both broken ends; (2) a rapture equivalent to a 14-in.-diameter hole in the primaryloop piping adjacent to the upper ring header; (1) a complete parting of a 1 3/4-in. upper jumper; and (4) a complete parting of a 1 3/4-in. bottom jumper. The Pu-Al elements represent the most critical component; melting of these elements would begin about 219 seconds after the rapture occurred if emergency backup light water coolant were not available to the system. It was found that the …

A lecture delivered at Sandia Corp., Albuquerque, N. Mex., June 18, 1958. A discussion of information exchange theory is presented. Semantics in communications are examined, and the use of symbols in thinking and presentaion are discussed in some detail. (J.R.D.)

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The preliminary process design of a PRFR pilot leaching plant, the proposed location of which is in Cell B of Building 3026 at ORNL, is considered. Chemical, physical, and nuclear parameters are investigated to assure safe leaching operations. Nitric acid solvents are used for leaching the uranium and/ or thorium from the sheared spent fuel elements, and the dissolved fuel is sent through a shielded pipeline to the extraction plant for further processing. Recommended materials of construction are 304L stainless steel and 3O9SCb stainless steel, and maintenance is by direct procedures. (auth)

8 5 F 5 ; 9 6 9 7 4 / 1 < =15% cold-worked Zircaloy-2 at 290, 345, and 400 deg C is being continued. Research to identify factors affecting irradiation-induced volume changes in graphite by means of sink- float density measurements was oontinued. The program to simulate conditions after a postulated loss-of coolant incident within the PRTR was completed. Lapsed-time motion pictures are being made through a windowed autoclave of the corrosive action of high-temperature water on defected Zircaloy2 U specimens. Progress on the development of an isotopic-exchange leak-detection systems is summarized. A program to develop a thermal-neutron-flux munitoring system for the Hanford reactors is reported. A project is being conducted to determine the temperature and approximate composition of the ternary eutectic in the Al--U--Ni alloys. A feasibility study to determine if Ca coatings can be successfully put on Ni by arc-spraying methods is reported. Work was continued on the valence effects of oxide additions (CaO and La/sub 2/O/sub 3/) to UO/sub 2/. An investigation is being made of the effects of combined high pressure and temperature on UO/sub 2/. Postirradiation data are presented on fueled specimens of ZrH/sub 1.65/--2 wt.% U. An evaluation of the effect of …

Since 1952 eight nuclear explosions have been fired underground at the Atomic Energy Commission's Nevada Test Site. The explosions have varied in energy release from 55 tons to 19,000 tons of TNT equivalent and were carried out at depths varying from shallow burial to produce cratering to those depths at which no visible effects appeared on the surface. The major experimental data from these explosions, as well as the phenomenology of the deeper shots, are summarized hero. (auth)

with thorium oxide slurry at 1500 psi and 280 C to determine the effects of vane inlet and exit geometries on impeller wear, the wear rate of aluminum oxide bearings in this size pump, and the operating characteristics of the loop. The thoria, a 1600 fired oxide, had a mean particle size of approximately 2 mu . Average circulating slurry concentration was approximately 450 grams of thorium per kilogram of water and average flow rate was approximately 300 gpm. Attack on the titanium impeller surfaces was so slight that no effects of the various vane configurations could be deternained. No measurable bearing wear, either thrust or radial, occurred during the run. Loop operation was deficient in two respects; there was a tendency for thorium oxide to leave the circulating stream and collect in the pressurizer, and the purge- producing capacity was limited. Changing to a pressurizer having full loop flow through the lower end, similar to that of the 200A loop, should eliminate the accumulation tendency. (auth)