"A comparison of the grafting of a 2:1 molar mixture of methacrylic acid and styrene to both polypropylene film and fabric using CO60 source and electron accelerator as sources of ionizing radiation is made on the basis of mutual or simultaneous grafting and post-irradiation grafting.

Tests were conducted to obtain data on the dynamic response of the Reactor Plant to various startup rod withdrawal transients. Results were compared with those obtained in simulator studies. (auth)

The object of this experiment was to extrude normal uranium hollow billets to I and E `O` size tubing with reduced extruded O.D. and also to evaluate the use of pressed salt follower blocks. Pressed salt (NaCl) follower blocks under various conditions of pre-heat temperature were compared with the standard graphite at 800 F. Even though some yield reduction results, it was concluded that pressed salt follower blocks at 300 F represent a substantial cost reduction due to the extreme price differential of the two perishable items. Extruded O.D.`s of .020 inch and .040 inch less than the standard (nominal) 1.50 inch represent no gain in yield due to the sharp increase in machined slug rejects for O.D. defects.

An investigntion was conducted to determine flow distribution characteristics within the core and determine any relative shift in flow between the seed and the four blanket regions. The highest average flow measured throngh the blanket regions, for each loop arrangement, was established, however the flow in other regions was not consistent enough to establish a pattern. (J.R.D.)

An investigntion was conducted to determine the reactor coolant mixing charactsristics of the inlet plenum chamber. It was found that mixing in the inlet plenum was slight, and flow from a given loop is corfined mainly to its quadrant of the core. There appears to be no significant change in the flow rate through the fuel assemblies monitored with the reactor coolant introduced at various temperatures and the reactor coolant pump on either fast or slow speed. (J.R.D.)

A literature survey and experimental results from investigations of aluminum corrosion under both static and dynamic test conditions are presented. Static corrosion tests were made on 8001, 8001 + 2.5% Mg and X2219 clad with M400 aluminum alloys. Dynamic corrosion tests were made only on the 8001 alloy. These tests were performed in three identical dynamic corrosion test loops. Initial tests in each loop were made to investigate corrosion behavior in high purity water at high temperatures and high flow velocities. Reproducibility tests were also carried out. An evaluation was made of aluminum-surface-area-to- watervolume-ratio effects on corrosion resistance. Prefilmed sample tests in which test specimens were prefilmed at two different temperatures in a static autoclave prior to the dynamic tests were also made. Results indicated that the corrosion rates of the 8001 aluminum alloy were too high for an economical design of the reactor core. A considerable amount of uncertainty was found to exist in the corrosion literature, as well as in the experimental data, regarding effects of various test parameters on corrosion behavior of this alloy. Time limitations for application to the Pathfinder reactor prohibited further investigation of this material. Consequently, a recommendation of the 8001 aluminum alloy as …

A test was conducted to determine the performance of the auxiliary govennor of the turbine-generator unit in instantaneous electrical load losses. The effect of the transient induced by such a loss of load on the Reactor Plant was also of interest. Results indicated proper governor operation, and favorable Reactor Plant response. (J.R.D.)

Work was begun to determine the physical properties of mica-filled diallyl phthalate. Both the impact and tensile strength values compared favorably wlth asbestos-filled DAP formulatlons. The tensile values compared with the upper limit tensile strength values for asbestos-filled formulations. Adiprene-ferric acetyl acetonate-polyol systems were developed as adhesives and their properties studied. Sources of kilogram quantities of Th/sup 2//sup 3//sup 0/ were investigated. The samples were analyzed by a direct CeF/sub 3/ precipitation procedurc or by a tributyl phosphate-cerium procedure. The half- life of Ra/sup 2//sup 2//sup 3/ was found to be 11.3700 plus or minus 0.0065 days. Differential thermal analyses were made of lanthanum and praseodymium metals. Three preilminary determinations of the density of molten cerium were made by the vacuum pycnometer method. An average value of 6.58 was obtained. Leaching tests in water and in 0.1N HCl were continued on fibers of an experimental glass containing 10 wt.%n plutonium oxide. (M.C.G.)

Calibration testing was conducted to determine the direction and magnitude of drift in core thermocouples, primary loop and pressunizer resistance thermometers. and the resistance thermometers in the secondary side of the boilers. Because of operational conditions, only those sensing elements in coolant loops A and C could be evaluated. An analysis of data from A and C loops is included. (J.R.D.)

This article describes a test procedure for a liquid high explosive. The liquid to be tested is NTN, a mixture of nitromethane, tetranitomethane, and 1-nitropropane in 52, 33.3, and 14.7 weight per cent. The test is to study the sensitivity of the explosive to shock by firing it in projectiles from a M1A1 155mm howlitzer, with a charge such that it will not exceed 16,500 g`s acceleration.

The study which has been carried out under Contract AT(30-1)2477 has as its objective the review of all work which has been done on the application of radionuclear techniques to research in water resources and supply, the evaluation of this work, and the suggestions of specific experiments which must be performed if these applications are to be extended.

A critical experiment program is carried out in a configuration similar to the BONUS reactor. The results give information concerning: the effects of different boilersuperheater geometries; the reactivity changes associated with superheater voiding or flooding; power regulation between the boiler and superheater regions; epithermal transmission probabilities for B-stainless steel and Cd control rods; the power flattening characteristics; and void simulation properties. The calculational methods used in the study predict the measured reactivity and power distribution to within the limits of experimental accuracy. (T.F.H.)

None

A test was conducted to datermie the pressurizer relief valves leak rate prior to, immediately after, and twenty four hours after flushing. The leak rates were found to be ralatively constant. (J.R.D.)

Prior to operation of the SER at temperature and power and with NaK coolant present, a series of measurements were performed in the neighborhood of room temperature and at powers of 1 watt or less. These measurements were designed to establish the characteristics of the system under controlled conditions and to determine safe operating procedures. Measurements were made to determine critical mass in various reflector configurations, control drum and safety element worth, flux mappings in the reactor and importance mappings external to the reactor, reactivity coefficients of various materials, and kinetic parameters. The most important conclusion drawn is that the system as designed hns the necessary reactivity and control for its anticipated operation. Full feasibility determinations must necessarily wait upon the outcome of experiments at power and temperature. (auth)

Strain-fatigue tests were conducted on two reactor-grade aluminum-base alloys and a sintered aluminum product at 80 to 900 deg F. The materials are used in reactor components, and one of the aluminum alloys has a potential for use in experimental models. Results of the tests indicate that strain-fatigue behavior at room temperature for the materials was similar to that of other ductile materials. The aluminum-alloy specimens at 600 deg F yielded results of limited value owing to the instability of the specimens. At 900 deg F the sintered aluminum product exhibited a significant loss of ductility with a cyclic life 16% of that at 600 deg F. (auth)

Suggested fabrication procedures for Zircaloy-2 sheet, plate, rod, and bar are presented. The procedures are based on the physical and mechanical metallurgy of Zircaloy-2 and are designed to produce material with a minimum amount of preferred orientation, anisotropy of mechanical properties, and intermetallic stringers. The recommended procedures cover ingot soaking, fabrication, heat treatment, finish, workmanship, identification, and inspection. A brief discussion of the physical and mechanical metallurgy of Zircaloy-2 is presented. (auth)

Tests were carried out to determine if there was sufficient excess reactivity present in the core to override a pesk xenon transient and to obtain data for rod worth calculations. Upon completion of 1565.4 EFPH of plant operation of Core I, Seed 2, there was sufficient reactivity to override the peak xenon transient imposed by a rapid shutdown from an average reactor power level of 102.65%. The override occurred 8 hr and 46 min after shutdown with Group I control rods withdrawn to 69 in. and Group II control rods controlling, withdrawn to 44.75 in. Rod Group III and Group IV were fully inserted. (M.C.G.)

A test was conducted to determine if sufficient excess reactivity exists in the core to override a peak xenon transient, and to obtain data for rod worth calculations. After completlon of 224.7 EFPH of plant operation with Core 1, seed 2 (5053.9 EFPH total Core I operation), there was sufficient reactivity to override the peak xenon transient imposed by a rapid station shutdown from an avernge reactor power level of 105.24%. Data on rod worth and other test results are included. (J.R.D.)

Thorough examination of the clad surfaces and end closures of the two brazed elements gave no evidence of exposed uranium. This examination included visual scrutiny in the Radiometallurgy Examination Facility, followed by dissection and metallographic study of suspected zones. Thus, it is concluded that the emission of radioactive material was probably due to a jacket or closure leak in one or more of the other experimental elements, included in the same tube, whose investigation is beyond.the scope of the present study. Metallographic examination revealed voids and unbonded areas in the closure region. Also, erosion and clad thinning was observed where the braze blended into the fusion weld. As a result of these observations, corrective action was taken to improve the quality of the brazed closure.

Reaction between gaseous nitrogen dioxide and gaseous uranium hexafluoride results in the formation of the nitrylium salt NO/sub 2/UF/sub 6/. Under similar conditions no reaction occurs between nitrogen dioxide and molybdenum and tungsten hexafluorides. Reaction between nitrosyl and nitryl fluorides and the three hexafluorides results in solid compounds of the composition NO/sub x/F x MF/sub 6/, where x is 1 or 2 and M represents Mo, W, or U. Reaction between gaseous or liquid nitrosyl chloride and molybdenum and uranium hexafluorides results in the formation of the nitrosylium salts NOMoF/sub 6/ and NOUF/sub 6/ and chlorine. Tungsten hexafluoride was found not to react with nitrosyl chloride. The conditions and stoichiometry of the reactions are described. The nitrylium salt, NO/sub 2/UF/sub 6/, is characterized, and some of its physical and chemical properties are described. The NO/sub x/F x MF/sub 6/ compounds are characterized, and some physical properties are described. Evidence for the presence of NO/sup +/ and MF/sup -//sub 7/ ions in these compounds is given. The nitrosylium salts, NOMoF/sub 6/ and NOUF/sub 6/, were characterized previously. (auth)

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Construction and effect of Article 5382d of Vernon's Civil Statutes.

Measurements of the interfacial tension between water and tributyl phosphate solutions were made for application to the analysis of Marengoni effect in solvent extraction. A 24 hr flame calcination run to product Th02 particles yielded 40% as product and 54% collected from the furnace walls and from a coarse particle trap. The elution rates of uranyl ion from Dowex 21K using sodium nitrate could be approximated by assuming apparent diffusion coefficients of 1.67 x 10^-7 and 1.18 x 10 ^-7 cm^2/sec, respectively for 960µ and 820µ resn while the corresponding apparent coefficients using sodium chloride were 1. 78 x 10^-7 and 1.27 x 1-^-7 cm^2/sec. The reacting surface of ThO2 Universal Match Co. pellets was determined as a function of fraction dissolved. The lead scews and companion nuts from both the multipurpose saw and dejacketing machine were coated with a baked on lubricant. In Zirflex decladding studies using 4.5 M NH4F - 0.5 M NH4NO3, the average dissolution rate of Zircaloy-2 was decreased only 10% when the overhead condensate was withdrawn and 1.0 M NH4OH was added to maintain the volume.

Bare and zirconium-clad uranium-10 wt% molybdenum specimens were irradiated in NaK-filled capsules in the MTR. Irradiation conditions varied to include central-core temperatures ranging from 300 to over 1200 deg F, fuel burnups ranging from 0.36 to over 3.0 total at.% and fission rates in the range of 0.35 to 1.9 x 10/sup 14/ fissions/(sec)(cm/sup 3/) of alloy. Other parameters studied included the effects of heat treatment, changes in composition, different fabrication techniques, and changes in cladding thickness on the behavior of the fuel alloy. The objective of the irradiations was to determine the behavior of the fuel alloy under conditions approaching as closely as possible those to be encountered in the Enrico Fermi Atomic Power Plant as they were known at the time. The results indicated that the volume of the fuel alloy would increase conservatively at a rate of about 3.0% per at.% burnup as long as the critical temperature of 1000 to 1100 deg F was not exceeded and the gamma phase of the alloy did not transform during irradiation. If the critical temperature was exceeded, the alloy swelled until rupture or complete disintegration occurred. The occurrence of transformation during irradiation was noted at burnups in the range …