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Creep Rupture in the Presence of a Fast Neutron Flux

Description: Possible mechanisms for creep rupture during irradiation are examined. Evidence that the rupture occurs by grain boundary sliding alone, or by vacancy condensation, is compared. It is observed that vacancy condensation is the more probable mechanism, and that this mechanism predicts a reduction in creep rupture life for metals exposed to a fast neutron flux (neglecting effects of radiation annealing). (T.F.H.)
Date: January 14, 1959
Creator: Gregory, D. P.
Partner: UNT Libraries Government Documents Department
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FLUX DISTRIBUTIONS AND LEAKAGE CURRENTS FOR SRE, P-16

Description: BS>Two-group, two-region criticality calculations were made for 10 and 11 ft diameter tanks. The 10 ft tank required a core radius of 102 cm and the 11 ft tank a core radius of 95 cm for criticality. In the calculations, the fluxes were assumed to go to zero at the edge oi the graphite reflector. The fast group of the two-group calculation was broken down into 3 fast groups. The leakage out of the core and reflector for the 4 energy groups is given. (M.C.G.)
Date: January 29, 1954
Creator: Balent, R.
Partner: UNT Libraries Government Documents Department
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Sodium Graphite Reactor. Quarterly Progress Report, July-September 1954

Description: Technology of the Sodium Graphite Reactor. Reactivity calculations were made to study the application of steadystate plutonium feedback techniques to the use of diffusion plant tails for reactor fuel feed material. The performance and design of a twin core SGR power plant are given. Thermal neutron flux distribution measurements are reported for a six-rod fuel cluster and for a hollow uranium rod. A power cost calculation was made for a 1000-Mw SGR Th-U/sup 233/ breeder reactor which starts up … more
Date: December 1, 1954
Creator: Siegel, S. & Inman, G.M. eds.
Partner: UNT Libraries Government Documents Department
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Separation of Iron and Cobalt on Synthetic Resin

Description: In the separation of mixtures of radioactive iron and cobalt from neutron irradiated targets and in the removal of iron from cobalt targets for cyclotron production of radioiron, it is desirable to have a method superior to extraction from isopropyl ether in efficiency and ease of manipulation. Recent studies by Moore and Kraus on the separation of cobalt and nickel and on the behavior of iron in hydrochloric acid on Dowex-l resin in relation to the selective adsorption of chloride complexes of… more
Date: August 5, 1953
Creator: Helwig, H. L.; Ashikawa, J. K.; Clokie, H. & Smith, E. R.
Partner: UNT Libraries Government Documents Department
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Measurement of lithium in target slugs by neutron transmission

Description: An instrument was developed to measure nondestructively the lithium content of target slugs for the SRP reactors. The slugs consist of cylindrical pieces of Li-Al alloy, approximately 0.8 inches in diameter and 12 inches in length, clad with aluminum. The instrument utilizes neutron transmission to determine the Li content in the range 3% to 7% Li.
Date: February 1, 1955
Creator: Dexter, A.H.
Partner: UNT Libraries Government Documents Department
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Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data

Description: From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."
Date: November 29, 1951
Creator: Shapiro, Mathew; Preiser, Stanley & Young, Gale
Partner: UNT Libraries Government Documents Department
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Boiling Reactors: A Preliminary Investigation

Description: Technical report detailing kinetic equations that have been developed for a boiling-type reactor and inherent reactor stability studies that have been made on the basis of these equations. Presents features of the proposed reactor, comparisons of circulating types, investigations of bubble-rise velocities, effects of transient conditions of vapor mass in steam chest, and bubble time delay functions yield favorable results. [From Abstract]
Date: December 12, 1951
Creator: Stein, J. M. & Kasten, P. R.
Partner: UNT Libraries Government Documents Department
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Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Description: Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
Partner: UNT Libraries Government Documents Department
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Enrichment of Uranium 236

Description: From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR react… more
Date: December 1951
Creator: Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
Partner: UNT Libraries Government Documents Department
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Physics Division Quarterly Progress Report for Period Ending March 20, 1951

Description: Technical report covering classified work of the Critical Experiments Program in the Physics Division for the period December 20, 1950 to March 20, 1951. Report outlines investigations of properties of critical assemblies composed of uranium and various reflectors and moderators, preliminary measurements of the effective energy for fission in the assembly. [From Introduction and Summary]
Date: July 2, 1951
Creator: Bernstein, S.; Snell, A. H. & Wollan, E. O.
Partner: UNT Libraries Government Documents Department
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Neutron Production by High-Energy Particles

Description: Abstract: "From neutron-yield measurements made with a MnSO4 detecting solution, the average number of neutrons produced per inelastic event is determined for a series of elements from lithium to uranium for 340-Mev protons, 190-and 315-Mev deuterons, 490-Mev He3 ions, and 90- and 160-Mev neutrons. The results are analyzed in an attempt to understand the total yield measurements for thick targets and to explain the variation of yield with the atomic number of the target."
Date: September 29, 1954
Creator: Crandall, Walter E. & Millburn, George P.
Partner: UNT Libraries Government Documents Department
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Analysis of the Interaction of 300-Mev Neutrons with Xenon

Description: Abstract: And investigation of the interactions between 300-Mev neutrons and xenon was made by means of a cloud chamber in a pulsed magnetic field of 21,700 gauss placed in the neutron beam of the 184-inch Berkeley cyclotron. Eighty-seven negative pion events and 257 other stars were analyzed. In addition an experimental check was made on the energy of the incoming neutrons. Classification, identification, and angular and energy distributions of prongs associated with all events are presented. … more
Date: October 17, 1956
Creator: Morris, Richard Herbert, 1928-
Partner: UNT Libraries Government Documents Department
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Effect of Boron Liner on Neutron Background in Cavity

Description: Introduction: "In connection with conducting neutron experiments in a pit with earth and concrete walls, it was proposed that the background flux of neutrons might be reduced by lining the walls of the pit with a neutron absorber such as boron. To determine how much liner material would be desirable and what diminution in the neutron background could be expected, the following measurements were undertaken."
Date: January 16, 1953
Creator: Benveniste, Jack
Partner: UNT Libraries Government Documents Department
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The Time-Dependent Neutron Flux for a Pulsed Subcritical Assembly

Description: Report discussing a study regarding the time-dependent neutron flux for a pulsed subcritical assembly. From abstract: "A two-group analysis has been applied to the transient behavior of the thermal flux in a subcritical assembly which has been given a short burst of fast neutrons."
Date: April 15, 1957
Creator: Fults, Stanley C.
Partner: UNT Libraries Government Documents Department
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Elastic Scattering of 14 Mev Neutrons (Theoretical Curves)

Description: Abstract: "Theoretical differential cross-sections computed from the optical model for 14 Mev neutrons are presented for a large number of nuclei. The parameters used for the calculations were selected on the basis of best fit to existing experimental data."
Date: July 1957
Creator: Bjorklund, F. & Fernbach, Sidney, 1917-1991
Partner: UNT Libraries Government Documents Department
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Elastic Scattering of 7 Mev Neutrons (Theoretical Curves)

Description: Abstract: "Theoretical differential cross-sections computed from the optical model for 7 Mev neutrons are presented for a large number of nuclei. The parameters used for the calculations were selected on the basis of best fit to existing experimental data."
Date: July 1957
Creator: Bjorklund, F. & Fernbach, Sidney, 1917-1991
Partner: UNT Libraries Government Documents Department
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Neutron Production in the Pinch Due to Instability Breakup

Description: Abstract: "The neutrons from the linear pinch in Berkeley have been shown to originate from deuteron collisions with a large net center-of-mass velocity in one direction along the axis of the pinch tube. The interpretation of this result is that the neutron production associated with the pinch is non-thermonuclear in origin. The object of this paper is to review the experimental evidence and discuss a possible source of the neutron production."
Date: May 12, 1956
Creator: Colgate, Stirling A.
Partner: UNT Libraries Government Documents Department
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Energy-Dependent Albedo

Description: From abstract: "Within the framework of age theory an expression is developed which represents the probability of a neutron being reflected with an energy loss corresponding to age, v, as a function of reflector thickness."
Date: September 20, 1954
Creator: Drummond, William E.
Partner: UNT Libraries Government Documents Department
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Measurement of Rod Strengths by Analysis of Scram Transients

Description: Summary: "Analysis of the power-level transient following the rapid insertion of a large absorber into an operating pile provides an excellent means of determining the reactivity effect of the absorber . Recent improvements in instrumentation make possible the measurement of the strength of the entire vertical safety rod system of the production units by means of this technique, and rapid calibration of the high-speed control rods by means of this technique, and rapid calibration of the high-sp… more
Date: 1952
Creator: Clark, W. A.
Partner: UNT Libraries Government Documents Department
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