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Description: Gamma radiolysis of thymine solutions was investigated over a wide pH range using ultraviolet absorption spectra and two-dimensional paper chromatography combined with radioautography. The results show that as the pH is increased, the spectrum change for a given dose decreases, G(H/sub 2/O/sub 2/) increases, and G(organic peroxides) decreases. Sevrral compounds were isolated from irradiated neutral or acidic solutions of thymine, while in strongly alkaline solutions, only hydroxymethyl uracil was found in appreciable amounts. It is concluded that radiolysis of un-ionized thymine (in acidic solution) proceeds by addition to the double bond, while in ionized thymine (in alkaline solution), the methyl hydrogens are more reactive. (D.L.C.)
Date: October 31, 1964
Creator: ,; Tsukamoto, W T; Ward, J F; Julca, J R & Holmes, D E


Description: gram are to test nuclear superheating concepts and to advance the technology of boiling-water-reactor design by performing experiments which will improve the understanding of factors limiting the stability of boiling reactors at high power densities. The reactor vessel is a cylinder with ellipsoidal heads, made of carbon steel clad internally with stainless steel. Each of the three cores is 24 in. high and has an effective diameter of 39 in. (W.D.M.)
Date: February 1, 1960
Creator: 1960, Feb.

ORGDP Container Test and Development Program Fire Tests of UF6-Filled Cylinders

Description: Fire tests of bare, UF{sub 6}-filled shipping cylinders were conducted at the ORGDP Rifle Range during October 1965 as part of the AEC-ORO Container Test and Development Program presently under way at the ORGDP. The multi purpose effort was to determine if the cylinders would hydrostatically or explosively rupture; the time available for fire fighting before either incident occurred; and the degree of contamination as related to the type of UF{sub 6} release, wind velocity, and terrain. In addition to the cylinder fire tests, other tests were made for further evaluation of the fire-resistant BOX foam plastic. These included a newly designed shipping drum for 5-in.-diam cylinders, and 15B-type wood shipping boxes for small containers. In one case, the latter contained a UF{sub 6}-filled Harshaw cylinder. The test times ranged from 45 to 95 min. In no instance did temperatures exceed 200 F These tests are discussed under Part B. Our Nuclear Engineering Department was responsible for site preparation and the test program. The Safety and Health Physics Departments Mr. A. F. Becher, head, provided primary assistance in the conductance of the tests and was additionally responsible for the environmental monitoring and sampling. Personnel of the Plant Shift Operations and Security, Fabrication and Maintenance, and Technical Divisions provided further support in the various operations. Mr. J. E. Wescott of the AEC-ORO and Mr. J. W. Edwards, ORGDP, were in charge of the motion and still photography. Two each of the following types of cylinders were tested: 3.5 in. diam x 7.5 in. Monel Harshaw, 5.0 in, diam x 30 in. Monel, and 8 in. diam x 48 in. nickel. Fill limits were 5, 55, and 250 lb of UF{sub 6} respectively, at an enrichment level of 0.22%. The larger cylinders were tested individually, with and without their metal valve covers. ...
Date: January 12, 1966
Creator: A.J., Mallett

External-Fuel Thermionic Reactors

Description: The concept of the external-fuel thermionic converter, in which the fuel surrounds an inner emitter annulus, is introduced and the major advantages of its use in a thermionic reactor are discussed. In-core reactors, ranging from 15-ekW to megawatts, can be designed based on external-fuel converter modules of fixed emitter and collector dimensions. Sizes and weights of typical reactors in this power range are shown.
Date: May 1, 1968
Creator: Abbate, M. J.; Eisen, C. L.; Raab, B. & Schock, Alfred

Three-Dimensional Inviscid Flow About Supersonic Blunt Cones at Angle of Attack - III: Coupled Subsonic and Supersonic Programs for Inviscid Three-Dimensional Flow

Description: The three-dimensional ideal gas flow in the shock layer of a blunted supersonic cone at an angle of attack is calculated using two asymptotic solutions. The first solution calculates the steady state flow in the subsonic nose region by obtaining a time-dependent solution of the hyperbolic equations using numerical techniques. Internal, nonboundary points are calculated using a Lax-Wendroff numerical type technique. Boundary points, shock and body surface, are computed using a time-dependent method of characteristics. When a steady state solution is reached the flow properties on a surface of constant {theta}, (where the Mach number is everywhere > 1) are used for initial data for the afterbody solution. The afterbody solution, using polar coordinates (r, {theta}, {phi}) assumes at r{sub 0} an arbitrary set of initial conditions provided by the nose region solution and computes the downstream flow as a function of {theta}, {phi}, and r until an asymptotic state independent of r develops. The interior mesh points are again calculated using a Lax- Wendroff type technique and the boundary points by a method of characteristics. This report covers the coupling of the time-dependent and radius (r) dependent solutions. Instructions are given for the operation of the resulting Fortran code. The type of input data required is detailed and sample output is provided. Output data is given in two sets of coordinates. One is wind orientated; the other set is given in body orientated coordinates; The analytical transformation from one coordinate system to the other is given.
Date: September 1, 1968
Creator: Abbett, M. J. & Fort, R.

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.


Description: Boron-impregnated polyethylene tape was irradiated in the Engineering Test Reactor Critical Facility to study the effect of boron as a burnable poison in reactor fuel. Isotopic analysis of the boron was performed with a conventional CEC Model 21-103 mass spectrometer. The tape was distilled off and the residual boron was converted to trimethyl borate. The reaction mixture was analyzed without separation. Good precision was obtained with samples containing less than 0.5 mg. boron. Features of the mass spectrum of trimethyl borate are discussed. Other applications of the method are suggested. (auth)
Date: January 28, 1960
Creator: Abernathey, R.M.

Filling and Emptying System, Cannelton Main Lock, Ohio River, and Generalized Tests of Sidewall Port Systems for 110- by 1200-ft Locks: Hydraulic Model Investigation

Description: Report providing the results of a hydraulic model investigation of the Cannelton Lock proposed for construction on the Ohio River. It includes detailed information about the tests and suggested dimensions and features of the final lock.
Date: February 1966
Creator: Ables, Jackson H. & Boyd, M. B.

Filling and Emptying Systems, Low-Lift Locks, Arkansas River Project: Hydraulic Model Investigation

Description: Results of a hydraulic model investigation based on locks in the Arkansas River before the construction of additional locks. "Model studies of the filling and emptying system proposed for use at the low-lift locks in the Arkansas project were conducted to confirm the adequacy of the original design hydraulic system, and to develop, if needed, improvements in the system" (p. 2).
Date: November 1966
Creator: Ables, Jackson H. & Boyd, M. B.


Description: Drosophila melanogaster adults are irradiated and then mated to flies containing genetic markers and/or crossover suppressors in all chromosomes. Appropriate genetic schemes are followed to obtain balanced stocks of entire treated genomes. Each chromosome of each genome is observed for visibles, lethals, detrimentals and sterility factors. Tests are made for translocations involving any combination of chromosomes. All chromosomes of each genome are examined cytologically for possible deficiencies, inversions, transpositions, etc. and to determine the break points of the translocations. It is believed that a study such as this will give us a far better idea of the overall magnitude of radiation-induced genetic damage and a better insight into the nature of this damage, expecially the inter­-relationships between the different kinds of genetic alterations, than has heretofore been possible with studies of selected types of damage in selected chromosomes or loci.
Date: July 28, 1968
Creator: Abrahamson, Seymour


Description: A survey of the character and magnitude of hazards involved in processing liquid metal bonded fuels was made and the scope of a preliminary experimental program outlined. Processing of SRE and CPPD fuels by mechanical decladding followed by controlled reaction of the collected methods. Simdlarly, shearing of PRDC fuel and controlled exposure of the Na in the severed portions to water appears more desfrable than chethical dissolution of the metallic cladding. (auth)
Date: August 14, 1961
Creator: Adams, J.B.