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Effects of gamma-ray irradiation on M1 propellant

Description: Samples of M1 single-base propellant were exposed to 10{sup 5}, 10{sup 6}, and 10{sup 7}r of Co{sup 60} gamma rays. Burning rates were determined over a pressure range of 600 to 2600 psi at -40{degrees}, 21{degrees}, and 71{degrees}C. A statistical study indicated no significant change in the burning rate and a small but statistically significant increase (6%) in the exponential factor n after the 10{sup 7}r dose. Visible deterioration resulted, as the color changed from yellow to dark brown and the surface became uneven. In view of these marked visible effects, the slight change in burning rate is surprising. One sample exposed to 5 {times} 10{sup 8}r showed severe blistering, swelling, and contraction, and embrittlement causing fracture. Nitrogen Taliani tests conducted at 110{degrees}C indicated that the decomposition rate is decreased by exposure to 10{sup 5}r, is decreased less by 10{sup 6}r, and remains unchanged after 10{sup 7}r exposure. Chemical analysis showed that the percentage of 2-nitrodiphenylamine increases with dose by a factor of 7 at 10{sup 7}r, while, at the same time, the nitrogen content of the nitrocellulose decreases with increasing dose. This indicates that a substantial part of the nitrocellulose decomposition product had reacted with the diphenylamine stabilizer. It is remarkable that propellant strands obviously modified by exposure to 10{sup 7}r showed little or no change in burning rate.
Date: April 1, 1964
Creator: Abel, J.E.; Mapes, J.E. & Levy, P.W.
Partner: UNT Libraries Government Documents Department
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N-Reactor co-product target element rupture detection study

Description: At present there seem to be some uncertainties concerning the needs of rupture detection for the co-producer programs Also in question is the method by which ruptures of the target elements should be detected and located. The purpose of this report is to discuss the waste and hazard control of tritium (H{sup 3}) (the product of the co-producer program), which will determine rupture detection needs, and to discuss methods by which rupture detection and location may be accomplished. The scope of the report considers first, adaptation of the present rupture monitoring system, and second, monitoring systems using H{sup 3} analyzers, together with the costs and time required to develop and use each method of rupture detection.
Date: April 27, 1964
Creator: Allred, D. O.
Partner: UNT Libraries Government Documents Department
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Southwest Retort, Volume 16, Number 8, April 1964

Description: This publication of the Dallas-Fort Worth Section of the American Chemical Society includes information about research, prominent scientist, organizational business, and various other stories of interest to the community. Published monthly during long academic semesters.
Date: April 1964
Creator: American Chemical Society. Dallas/Fort Worth Section.
Partner: UNT Libraries
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HANDBOOK OF SHIELDING REQUIREMENTS AND RADIATION CHARACTERISTICS OF ISOTOPIC POWER SOURCES FOR TERRESTRIAL, MARINE, AND SPACE APPLICATIONS

Description: The radiation intensities from shielded and unshielded sources fabricated from seventeen isotopes that show promise for use in isotopic power or radiation applications were calculated. Source sizes in the range of 100 to 20,000 thermal watts were evaluated. All shielded sources were assumed to be attenuated by Fe, Pb, and U; and in those cases where the source also emitted neutrons, neutron and gamma attenuation through water was determined. The isotopes studied and their physical form are as follows: /sup 60/Co (metal), /sup 85/Kr (liquefied gas), /sup 90/Sr (oxide and titanate), Zr-/sup 95/Nb (oxide), / sup 106/Ru (metal), /sup 137/Cs (glass), /sup 144/Ce (ox ide), /sup 147/Pm (oxide), /sup 170/Tm and /sup 171/Tm (both as oxides), /sup 204/Tl (metal), /sup 210/Po (metal matrix with void space for gas collection), /sup 232/U (oxide), /sup 228/Th (oxide matrix with void space for gas collection), /sup 238/Pu (oxide), /sup 242/Cm (oxide matrix with void space for gas collection), and / sup 244/Cm (oxide). The use of the graphical results to calculate separation distance, shield thickness, and shield weight is demonstrated. (auth)
Date: April 1, 1964
Creator: Arnold, E.D.
Partner: UNT Libraries Government Documents Department
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Ichiban: The Dosimetry Program for Nuclear Bomb Survivors of Hiroshima and Nagasaki - A Status Report as of April 1, 1964

Description: From Abstract: "The approach to the problem has been as fundamental as possible with emphasis on quantitative measurements and calculations of the energy, angular, and spatial distributions of weapons radiations in an air-over-ground geometry. Spatial distributions of dose in various shields, including Japanese dwellings, have been measured. Techniques have been developed in Japan for verifying the location of survivors and accurately describing their shielding environments."
Date: April 1964
Creator: Auxier, J. A.
Partner: UNT Libraries Government Documents Department
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Production Test IP-550-I, Supplement A routine monitoring for moderator oxidation rates

Description: The objective of this supplement to Production Test IP-550-I is to include the K reactors in the program for routinely monitoring graphite oxidation rates. This supplement does not initiate a new program; it continues one which has been in existence for some time. Oxidation of the reactor graphite weakens its structural capacity. At some degree of oxidation, sufficient loss of strength will occur to significantly affect the ability to maintain and operate the reactors. For this reason it is necessary to control and to monitor the rates of oxidation in realtor. It is difficult to accomplish the latter in a truly representative fashion. A number of methods of obtaining information on this subject must be used; one of these is to expose small samples to the reactor atmosphere under operating conditions and then determine the average rate at which the samples have changed weight. This method has been employed in one fashion or the other for some time. Until June, 1962, the program was authorized by Production Test 105-532-E; from June, 1962, until January 26, 1964, the program was authorized by PITA IP-20-I{sup 4} at the K reactors.
Date: April 29, 1964
Creator: Baars, R. E.
Partner: UNT Libraries Government Documents Department
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Environmental Radiation Measurements in the Southeastern, Central and Western United States, 1962-1963

Description: Report describing the use of a 5" x 3" NaI(Tl) detector and a high pressure ionization chamber to obtain gamma ray spectra and total gamma dose rates at approximately 100 locations during the course of several survey trips in the southeastern, central, and western United States. Reasonably precise elements of the dose rates are made using the pulse height spectra and relatively simple methods of analysis. Total terrestrial dose rates as well as the partial dose rates from the uranium-238 series, thorium-232 series, potassium-40, zirconium-niobium-95, and rhodium-106 are tabulated for each location.
Date: April 1964
Creator: Beck, Harold L.; Condon, William J. & Lowder, Wayne M.
Partner: UNT Libraries Government Documents Department
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