This project has as its purpose the evaluation of argon flash candle components and factors which affect candle light output. This will be done by measuring the intensity of the light output simultaneously as a function of wave length and time.

Data from sieve analyses of HMX and HMX recovered from LX-04-1 has been compiled for correlation to quality parameters. Particle size distributions on HMX received from LRL have been completed along with other HMX lots specified by them. Sieve analysis of recrystallized PETN was obtained using the now normal procedure for HMX. A statistical investigation of production LX-04-1 examined the dependence of density, elongation, and ultimate tensile strength on particle size distributions ({Pi}) and Viton content. The {Pi} was found to correlate well with density, increases in fines decreasing density. An experimental to determine the effect of binder solvent on HMX {Pi} during removal of Viton from pressed LX-04-1 was performed. This study has indicated no drastic effect on the distribution by the length of time the binder solvent is on the material. HMX and recrystallized PETN surface area measurements obtained form the Perkin-Elmer sorptometer are tabulated in this report. Recrystallized PETN has been examined under the microscope and counts made on the number of crystals with given shape. A frequency distribution was calculated for each group present in a 1 mm{sup 2} area. Experiments to determine the extent of grinding or reduction of particle size of HMX agitated in …

Several samples of HMX to be used in LX-04-1 were particle sized and reported in this report. Most of the lots sized were very similar, with the major differences in the lots being at 2{micro}. Several counts in ``Rainbow`` Lot 26B of LX-04-1, made to obtain a color and weight distribution in several samples, and also a color count made in each sieve on a granulation analysis, show each color to be equally distributed; i.e., {approx} one-third of each color, green, yellow and white LX-04-1 granules, was present in the sample. Photographs and particle size curves of recrystallized PETN used in LX-02-1 are presented. These data were obtained by examining the original PETN used in a lot of LX-02-1, then performing several milling operations and recovering the PETN from the binder for another examination. The majority of the PETN appears to be crushed or broken in the first six passes on the three-roll mill with smaller changes taking place in the two-roll mill. The final {Pi} shows most of the PETN to be concentrated in the 4 to 8{micro} region. Photographs of two production lots of LX-02-1 subjected to a milling operation are also included. A description of the procedure …

A heat aging study in which tensile specimens (aluminum-to-aluminum and aluminum-to-LX-04-1 with Aerobond H-7) were heated to 165 F and aged up to three months has been completed. Aerobond H-7 showed no signs of deterioration when treated in this manner. Butyl glycidyl ether and benzene were tested as diluents for Aerobond H-7; butyl glycidyl ether is an effective diluent but benzene appeared to promote an exotherm. Water permeabilities were remeasured for Adiprene, Aerobond H-7, and Estane to resolve the questionable data gathered earlier. Kel-F, Perm-A-Lon, and Aerobond H-7 are by far the most impermeable to water. The disc extrudability test was run on the new lot of LX-02-1, A-335, both milled and unmilled materials.

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This project consists of (1) essentially routine experimentation, including evaluation of detonation velocity, gap sensitivity testing, and drop weight-impact machine testing; and (2) an experimental program whose goal is the development of high precision one and two-dimensional hydrodynamic data for use in establishing empirical detonation product equations of state.

Emphasis was placed this quarter on the manufacture of extrudable explosives. This included the recrystallization of PETN which was used to manufacture two batches of LX-02-1 and one batch of RX-02-AK. The materials were examined for composition, extrudability and burning via detonation velocity. Also, a Sunburst and Sunray were performed on the first batch of LX-02 made. Results were all satisfactory except for detonation velocity; some of the channels were yielding somewhat erratic results which could be due either to the test or incomplete mixing. The recrystallization of PETN progressed satisfactorily and the final crystals as viewed under the microscope had the expected appearance.

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This project is the development of plane wave explosive lenses better than currently available baratol lenses in simultaneity. An additional objective is to minimize pressure differences across the output plane.

This paper contains the minutes of a meeting on Columbia River contamination at Richland, Washington, held on July 16, 1964. The US Public Health Service sponsored the meeting and representatives from the following organizations were present: Washington State Pollution Control, Washington State Department of Health, Richlands Operations Office, AEC Headquarters, and General Electric Company. The meeting dealt with reducing the amount of effluent contributed to the Columbia River, the amount of reduction achievable, the costs involved and the status of technical feasibility studies. This document was declassified on January 26, 1994.

This work is for the development of testing methods and determination of physical properties of H.E. formulations. An eight-cycle bulk compliance test on LX-04-1 produced a gain in density of 0.017 gm/cc from an average starting-density of 1.858 gm/cc, net gain of .810 gm/cc after one month storage. A group of tensile specimens were tested on three test machines in three locations (Baldwin at LRL, Instrom in Pantex Engineering and Tinius Olsen in Pantex Development), using specimens from a single pressing. The tests showed that these machines are able to produce similar results and are not extremely operator sensitive. It has been determined that LX-04-1 will not flow well enough at a loading of 50 psi to produce orientation grooves for pents. A tabulation of density, tensile strength, strain at ultimate stress, granule size and HMX particle size has been compiled for evaluating the several powder lots of LX-04-1 which have been used. Density and tensile strength appear to be better when PBX 9404 is pressed in the 300-ton (ram) press than it was for the same lot of material which was pressed in the 20-inch hydrostatic press.

This monthly report details activities of the N-Reactor Research and Engineering Department during the month of December 1964.

The C-1 Loop is a small in-reactor water loop located in the 105-C Building. The loop was originally designed and constructed for nonfueled testing of the effects of reactor radiation on sample corrosion, crud deposition, and coolant radiolysis. The loop was modified in 1964 to permit the irradiation of aluminum-clad fuel elements and subsequently used for about eight months for the in-reactor testing of aluminum-clad, plutonium-aluminum fuel assemblies at high coolant temperatures and pressures. The facility is currently inactive but is available for the performance of special testing. Prior to nuclear operation of the C-1 Loop the mechanical equipment was carefully checked and the backup coolant system was experimentally verified to perform as designed. A safety analysis was also made with results summarized briefly in Reference and in more detail in the production test which authorized nuclear operation of the C-1 Facility. This report updates those earlier documents with improved descriptions of the C-1 Loop and its operation including analyses of postulated accidents.

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Objective of the KE reactor test is to determine the hydriding corrosion rate of Zircaloy-2 at high temperature in a damp helium atmosphere, and to determine the outgassing rate of tritium generated in a lithium-aluminum alloy. The irradiation capsule design, operating conditions, etc. are discussed.

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Discussed topics on current reactor production fuels include: uranium core production data, uranium specifications, induction heat treating, fuel performance, residual stress measurements, AlSi process development, thoria program, and self-support program. The N-reactor fuels production is discussed. And concerning N-Reactor fuels development, process development and irradiation experience are discussed.

A modification program is now in progress at the C and K Reactors consisting of an extensive renovation of the graphite channels in the vertical safety rod ststems. The present VSR channels are being enlarged by a graphite coring operation and channel sleeves will be installed in the larger channels. One problem associated with the coring operation is the danger of damaging top thermal shield cooling tubes located close to the VSR channels to such an extent that these tubes will have to be removed from service. If such a condition should exist at one or a number of locations in the top shield of the reactors after reactor startup, the question remains -- what would the resulting temperatures be of the various components of the top shields? This study was initiated to determine temperature distributions in the top shield complex at the C and K Reactors for various top thermal shield coolant system conditions. Since the top thermal shield cooling system at C Reactor is different than those at the K Reactors, the study was conducted separately for the two different systems.

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For the test detailed in this report, the charge consisted of three NIEL fuel elements, two lithium-aluminum target elements, and front and rear crud probe train assemblies containing four ceramic fueled crud probes as authorized by PT IP-601. The objectives of these tests were to evaluate the crud forming characteristics of loop coolant containing ammonium hydroxide for pH control by operating at conditions generally regarded to induce high crud concentrations and to provide lithium-aluminum samples which may be used to determine production and extraction information.

The purpose of this test was to demonstrate and characterize the simultaneous generation of plutonium and tritium. The data charged was February 10, 1964 at 12:00 noon. The fuel elements were thirteen 26.1 inch co-product test assemblies. The fuel was exposed for a total of 2,828 hours and at run conditions for 2,288 hours. The date discharged was June 7, 1964. Goal exposure was met.

This report describes the development qualification and application of brazing process that eliminates the gold plating operation and the supplementary inlay brazing operation without effecting any of he several constraints that the application places on any seal brazing process developed.

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