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Fuel element performance

Description: For some time, it has been considered that cycling natural uranium fuel elements through the {alpha}-{beta} transformation point (approx. 662 C) is a contributing factor in split type ruptures. This hypothesis is based upon the fact that the transition temperature, a one percent increase in volume occurs. It is reasoned that as the uranium hardens under irradiation, it becomes progressively less able to adjust to the severe stresses imposed by the volume change as the material cycles through th… more
Date: December 31, 1957
Creator: Hagie, L. T.
Partner: UNT Libraries Government Documents Department
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The Free Radical from Perinaphthene

Description: The electron spin resonance spectrum of the perinaphthene free radical is reported and a discussion of electron spin density in this radical is given.
Date: January 31, 1957
Creator: Sogo, Power B.; Nakazaki, Masao & Calvin, Melvin
Partner: UNT Libraries Government Documents Department
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BNL Unclassified Research Quarterly Report: April-June 1956

Description: This report covers the unclassified research progress of the Laboratory Abstracts only are given for research activities being reported concurrently in the scientific journals.
Date: October 31, 1957
Partner: UNT Libraries Government Documents Department
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Zirconium Hazards Research. Summary Report No. 3655 for September 1, 1956 to August 31, 1957

Description: The sensitivity characteristics of a variety of Zr samples such as sponge, scrap, powder and process materials were studicd. Of particular interest was the determination of the relative seasitivity of these materials to such stimuli as impact, friction, electrostatic discharge, and heat. A study of the zirconium--water reaction at relatively low temperature was initiated. In general, scrap and sponge were relatively insensitive to impact. Only one proeess material, the distillation residue, exh… more
Date: August 31, 1957
Creator: Herickes, J.A.; Richardson, P.A.; Weiss, M. & Gelernter, G.
Partner: UNT Libraries Government Documents Department
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Pressurized Water Reactor Program Technical Progress Report for the Period July 15, 1954 to August 26, 1954

Description: This progress report has 2 parts. Part 1 PWR Engineering covers the following topics: (1) power plant analysis and systems; (2) power plant components and component materials and tests; and (3) reactor and auxiliaries. Part 2 PWR Development covers: (1) fuel element development; (2) metallurgy of core materials; (3) materials application development; (4) chemistry development; (5) irradiation effects; and (6) reactor physics.
Date: October 31, 1957
Partner: UNT Libraries Government Documents Department
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Solution Corrosion Group Quarterly Report for the Period Ending July 31, 1957

Description: The second All-Ti loop, 1OOA loop H, was placed in operation for more than 400 hr with UO/sub 2/SO/sub 4/ solution at 250 deg C and -- 1000 psi. A fourth test of the mockup of the Zircaloy-2--stainless steel transition joint used in the HRT reactor vessel was completed. The joint and bellows functioned properly and were leaktight. The series of long-term runs at 200, 250, and 300 deg C with solution proposed for use in the HRT was concluded. Stainless steel and Ti stress specimens exposed durin… more
Date: July 31, 1957
Creator: Griess, J. C.; Savage, H. C.; English, J. L.; Ulrich, W. C.; Buxton, S. R.; Neumann, P. D. et al.
Partner: UNT Libraries Government Documents Department
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Carbon Steel in High Temperature Water

Description: Resistance of carbon steel to corrosion in oxygenated high-temperatmre (250 deg C) water was unexpectedly good at high oxygen concentration. Pertinent literature, critically examined, and toroid experiments indicated that at low oxygen concentration attack did increase with concentration, but as oxygen concentration was sufficiently increased, more protective films were formed on the metal. Some corrosion factors in the cation of carbon steel to nuclear reactor systems are discussed. (auth)
Date: January 31, 1957
Creator: Moore, G.E.
Partner: UNT Libraries Government Documents Department
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Transient Heat Transfer in Reactor Coolant Channels

Description: An analysis is presented of the transient behavior of a generalized cooiant channel neglecting temperature dependent reactivity changes. The analysis is applicable to forced convection cooling of heterogeneous reactor fuel elements or electrically heated simulation thereof. Derivations are given for cases of variation of coolant inlet temperature and of heat generation. An approximation is also developed applicable to thin fuel elements. From this, solutions are obtained for cases-of impulsive,… more
Date: October 31, 1957
Creator: Stein, R. P.
Partner: UNT Libraries Government Documents Department
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A CALCULATION OF THE GAMMA-RAY SPECTRUM OF THE BULK SHIELDING REACTOR

Description: A calculation was performed to determine the highenergy portion of the gamma-ray flux at the surfacc of the uranium-aluminum BSF reactor. The flux was considered to consist entirely of the uncollided flux plus the Comptonscattered flux. The four sources of primary gamma rays included in the calculation were prompt fission gamma rays, capture gamma rays from aluminum, capture gamma rays from uranium, and fission-product decay gamma rays. These sources were divided into four energy groups. Althou… more
Date: July 31, 1957
Creator: deSaussure, G.
Partner: UNT Libraries Government Documents Department
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Shield Weights

Description: Shield weights were calculated for a number of fast reactors having desirable engineering characteristics using the Shield Optimization code. On the basis of these calculations, a Design Fast Reactor was chosen. This reactor, henceforth known as the PWAR-9, has a 12.75 inch core O.R. with a 2 inch Ni reflector. The reactor-shield weight and weight components for a supersonic mission, 2 man crew compartment, are given in table 1. The rpesent shield design uses U and LiR as shielding materials on… more
Date: July 31, 1957
Creator: Woodsum, H.C. & Rost, E.S.
Partner: UNT Libraries Government Documents Department
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NEUTRON AND PHOTON TRANSPORT: PLANE, CYLINDER, SPHERE (DIGITAL COMPUTER PROGRAMS)

Description: Digital comnputer Program S constructs neutron and proton transport theory solutions having plane, cylindrical, or spherical symmetry. Lattice detail in geometry, energy, and momentum-angles is flexibleAnisotropic scattering- transfer is neglected. For aircraft nuclear propulsion applications, the initial version of the program developed as the Los Alamos SNG Neutron Code has been generalized to include the effects of time-delayed neutron or photon production and to provide the flux adjoint. Th… more
Date: July 31, 1957
Creator: Duane, B.H.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Report for January, February, and March 1957

Description: Advanced Water Reactor Program. The second fuel loading for the EBWR is planned as ThO/sub 2/--UO/sub 2/. Some properties of ThO/sub 2/-- UO/sub 2/ systems are presented. Fast Power Breeder Reactor Program. The development of casting techniques for EBR-1, Mark III extrusion billet cores are described. The investigation of methods for the remote refabrication of irradiated reactor fuels was undertaken with the objective of designing, constructing, and testing techniques and equipment for the ref… more
Date: March 31, 1957
Partner: UNT Libraries Government Documents Department
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