Concentrations of fission products in the fuel and in the coolant stream of a generalized reactor power plant employing unclad fuel material were calculated using actual fission-product chains and wide ranges of assumed values of escape rate from the fuel and removal rate from the coolant stream. The calculations were made on an IBM 704 digital computer. Some typical results are displayed in the form of graphs to illustrate the effects of the variables. As data on escape rates from fuel and removal rates from coolant become available, the tables and graphs developed by this study can be used to estimate the fissionproduct concentration in the coolant stream, which would in turn furnish a basis for determining the degree of coolant purification required to maintain the circulating activity below a given level. (auth)

The study of the formation mechanism of free radicals in polymeric materials was continued. Emphasis was placed on an examination of the effect of structural factors on the efficiency of free-radical site formation in acrylate polymers. Site measurements as a function of dose were made for polymethacrylamide and repeated for polymethacrylic acid. The volatile products from the irradiation of polyacrylic acid. polymethacrylic acid, poly-ter- butylmethacrylate. and polycyclohexyl methacrylate were measured quantitatively by mass spectrometry and vapor-phase chromatography. Grafting studies were initiated using polymethylmethacrylate as base polymer and vinylpyrrolidone as graft monomer. (auth)

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An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development eIforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, ldaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes. Bulk densities of 0.8 g/cc were increased to 2.9 g/cc by selective use of fluxes and cold compacting techniques. This means that power densities of up to.001 w/cc will …

The purpose of this Process Improvement Transition Authorization (PITA) is to authorize full pile loading bumper fuel elements in the fringe zone will be reviewed and, if desirable, recommendations to curtail fringe loading may be made based on economic considerations.

An accurate, simplified expression relating Pu conversion to exposure, was found which could be substituted for the lengthy subroutine used to calculate conversions in the Process Optimization Program.

On the 1600--2400 shift, May 12, 1961, the delayed neutron monitor on KER Loop 1 gave a high coolant activity signal indicating a possible fuel element failure in this loop. KE Reactor was shut down immediately thereafter. This report is being written to summarize the events pertinent to the KE Reactor scram and to discuss the results and significance of data from the analyses of coolant samples taken from the KER Loop-1 System.

A brazed end closure is currently being used on prototypical NPR fuel elements. The production closure will use a braze alloy composed of 5% Be + 95% Zry-2 to braze the Zircaloy-2 cap to the jacket and to the metallic uranium core. A similar MTR test, a GEH-4-57, 58, used a braze alloy of the composition 4% Be + 12% Fe + 84% Zry-2 which melts at a lower temperature. In this previous test, element GEH-4-57 failed through a cladding defect located at the base of the braze heat affected zone. Because of this failure it would be desirable to subject a fuel element, which had been subjected to more severe brazing conditions, to the same conditions as GEH-4-57, 58. For this reason the thermal conditions of this test essentially match those of GEH-4-57, 58. This irradiation test consists of two identical fuel elements. The fuel material is normal metallic uranium, Zircaloy-2 clad of the tubular geometry, NPR inner size. The fuel was coextruded at Hanford by General Electric`s Fuels Preparation Department. Each element is 10.8 inches in length with flat Zircaloy-2 end caps brazed to the jacket and uranium core with the 5 Be + 95 Zry-2 brazing alloy, …

It is the purpose of this document to provide assistance to the Manufacturing Section personnel in determining their future operating plans. In general, the inter-relationship of such engineering parameters as projected flow rates, reactor orificing pattern, fuel element performance, and process limits have been considered. Based on these engineering parameters and related process economics, suggested reactor ``Operating Plans`` are graphically presented in this document. It is emphasized that these plans do not reflect operational considerations which may modify the desirability of the indicated power level increase nor has allowance been made for major projects, major maintenance outages, etc. Many factors which only manufacturing personnel are capable of evaluating may make it desirable to operate above or below these operating plants. These plans are designed to present reasonably achievable but perhaps optimistic power levels together with process limits which will be approached or will possibly limit reactor power levels unless limit revisions can be effected. It should be noted that the engineering parameters and basic assumptions which have been factored into these plans are subject to continual re-evaluation and revision. In a strict sense, these plans are out-dated even as they are published. However, their value will lie primarily in illustrating …

The effects of two contained H. E. explosions in volcanic tuff were examined by mining directly into the explosion sites. Ore explosion (516 lb of TNT) increased its initial shot chamber volume of about 9 cu ft by a factor of sbout 5 and produced in addition some 126 cu ft of broken rock. Around this explosion, only natural joints in one direction were filled with carbon to a maximum distance of 42 ft, and no new fractures in other directions were developed. The other explosion (973 lb of TNT) expanded its 17 cu ft chamber to 10 times this initial volume and led to rock breakage, mostly by subsequent roof collapse, of 345 cu ft. Because this shot vented on firing, very little of the carbon-carrying gases entered joints, and fractures caused by the explosion are almost absent. The features characteristic of these two explosions were compared to an earlier 1000-lb explosion in salt in which, by contrast, numerous radial carbon-filled cracks were produced, and the less expanded chambers survived without collapse. For the explosions in tuff it was concluded that joints exercised a primary role in locating the surfaces of fracture failure, early venting inhibits development of carbon-marked …

The effect of temperature on the yield strength of the polycrystalline hexagonal Ag--Al intermetallic phase was investigated over the temperature range 77 to 775 deg K. It was found that the curve for yield stress vs temperature for both polycrystalline Ag--33 at.% Al specimens that were heavily cold-worked prior to deformation and those that were recrystallized prior to deformation was parallel to that for prismatic slip in single crystals. Increase of the percent Al in the specimens resulted in an abrupt decrease in the ductility at a composition of about 37 at.% Al. This decrease in ductility was attributed to precipitates in the grain boundaries. (auth)

The Idaho Chemical Processing Plant did not operate on fuel recovery during the period since numerous repairs and modifications were being made to the extraction and U concentration equipment, Ba/sup 140/ production continued on schedule; substantial decontamination of the RaLa facility was achieved and desirable replacement or repair of in-cell equipment was accomplished in the interval between two successive runs. Aqueous Zr fuel processing studies continued with the obje tive of adapting the HF process to continuous dissolution a complexing in order to increase the capacity of the ICPP process while using as much existing equipment as possible to minimize costs. Dissolution rates for Zircaloy-2 in 10M(bar) fluoride dissolver solution proved to be adequate for continuous dissolution (as high as 79 mg cm/sup -2/ min/sup -1/) in an acid range which resulted in both controlled gas evolution and stable dissolver solutions. Preliminary results indicate the possibility of blending Zr raffinates from this process with larger volumes of Al raffinates to achieve stable waste solutions and avoid the necessity of constructing additional special alloy tanks for Zr waste. Supplemental studies on the sodium formate process for head end precipitation of Zr snd fluoride are reported, as well as results of corrosion …

In order to retain the hermetic feature of the sodium flow controller, magnetic flux linkage of a permanent magnet coupling is used to transmit the torque produced by the operator through the pressure wall. Magnetic calculations, manufacture, and testing of this magnet coupling are described. (M.C.G.)

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ABS>The preparation of germanium hydrides, by the dropwise addition of al alkaline solution of hydroborate and germanate to aqueous acid, was studied systematically. As much as 70% of the germanium in solution could be converted to germane, Digermane, trigermane, and a polymeric germane were also obtained, and the infrared absorption spectra of gaseous trigermane and of polymeric germane were recorded. (auth)

Thermodynamic data for liquid and gaseous water were compiled and extended to limits of pressure and temperature imposed by Hugoniot, adiabat, and Thomas-Fermi model considerations. The internal energy variation is discussed. (auth)

An evaluation was given of the possible hazards to consumers from radioisotope residues in consumer products. A laboratory demonstration was given of the use of Mn/sup 54/ to facilitate removal of manganese from process feed water. lt was found in the hazards evaluation that the "worst case" of radiation exposure from residual radioisotopes in steel gives a radiation exposure somewhat less than the maximum allowable dose levels for occupational exposure. Initial study indicates that for actual cases, the radiation exposures to be expected from radioisotope residues in steel products would ordinarily be small compared to natural background. An exception to this generalization might be found when a longer lived isotope like Mn/sup 54/ was present. Preliminary results of the laboratory demonstnation of using Mn/sup 54/ to monitor the removal of manganese from feed water indicated that the method may allow a considerable improvement in accuracy of process control. The study of the mechanism of formation of free radicals in polymeric materials was continued. Emphasis was placed on examination of the effect of structural factors on the efficiency of free-radical site formation in acrylate polymers. The investigation was extended to include an examination of the effect on free-radical formation of the …

The response of a lithium-drifted solid state detector was measured for protons and found to be linear up to the highest energy observed, 13.2 Mev. The resolution observed for these protons is 0.81% with a bias of 500 volts and 0.65% with a bias of 250 volts. (auth)

In the Hotcake experiments, PBX-9404 was subjected to various temperature spikes from 202 degrees Centigrade to 268 degrees Centigrade to determine conditions which would result in ignition of the explosive. since that time, measurements have been made of decomposition rates of PBX-9404, LX03, LX04, and pure HMX, at temperatures from about 240 degrees Centigrade to 270 degrees Centigrade. These data have been combined to provide a more accurate definition of the thermal stability of high explosives based on HMX. A set of values of decomposition rates and heats of decomposition has been obtained which is consistent with all previous Hotcake experiments, and will allow predictions of the results of similar experiments with PBX-9404, LX03, and LX04. Computations were made with the Hangfire program on the IBM 7090.