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Calculation of the Doppler Coefficient Plutonium-Oxide-Fueled Fast Reactors

Description: Report issued by the APDA over studies conducted on Doppler coefficient fast reactors. Calculations, methods, and results of the studies are presented. This report includes tables, and illustrations.
Date: November 1, 1963
Creator: Fischer, E. A.
Partner: UNT Libraries Government Documents Department
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Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 2: 1963

Description: Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: November 30, 1963
Creator: Auleta, J. J.
Partner: UNT Libraries Government Documents Department
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Effect of 1200ºF Sodium on Austenitic and Ferritic Steels Progress Report: Topical Report No. 2

Description: This is the first topical report from November 1963 detailing progress made in the test facility design and operation procedures, details in the continuing test program studying the effects of air, helium and sodium on stainless steel types, and test program specifics.
Date: November 1963
Creator: Andrews, R. C.; Barker, K. R. & Werner, R. C.
Partner: UNT Libraries Government Documents Department
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Development of Fueled Graphite Containing Pyrolytic-Carbon Coated Carbide Particles for Nonpurged, Gas-Cooled Reactor Systems

Description: Abstract: Progress is reported in several areas of development of fueled graphite containing coated particles for nonurged gas-cooled reactor systems. The sol-gel process has been modified for making spherical particles of both thorium-uranium carbide and thorium-uranium oxide suitable for coating. Equipment has been assembled and methods have been developed for deposition of pyrolytic-carbon coating under well-controlled conditions. Damage to coated particles during fabrication into a graphi… more
Date: November 1963
Creator: Carlsen, F. L., Jr.; Bomar, E. S. & Harms, W. O.
Partner: UNT Libraries Government Documents Department
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A Proposal for the Mc2 Isochronous Cyclotron: A General Purpose High-Intensity 810-MeV Proton Accelerator

Description: Abstract: "The Oak Ridge National Laboratory proposes to build an isochronous eight-sector proton cyclotron to provide an extracted beam in excess of 100 A at 810 MeV. The primary proton beam and the secondary meson and neutron beams will be used to investigate nuclear structure, and the interactions between elementary particles. Biomedical and Space-oriented research programs are also planned. Shielded research areas and an extensive beam transport and analysis system are provided. Theoretical… more
Date: November 1, 1963
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Recent Developments in the Physics and Safety of Large Fast Power Reactors

Description: Technical report discussing three principal areas: (1) some recent cross section measurements and their effect on fast reactor calculations; (2) the question of Doppler and sodium void reactivity effects in large fast power reactors and the conflicts inherent in simultaneous optimization of performance, breeding, and safety characteristics; (3) the matter of hybrid fuel cycles.
Date: November 1963
Creator: Okrent, David
Partner: UNT Libraries Government Documents Department
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Destructive Examination of a SNAP Heat Source

Description: A detailed examination was made of one of three plutonium-238 fueled SNAP 3 heat sources which was shipped from Mound Laboratory in May 1961 and returned in May 1963,. Examination of source included radiography, calorimetry, dimensional inspection, radiation measurements, internal pressure measurements, metallographic examinations of the containers, and recovery and impurity analysis of the plutonium fuel. Results showed that the inner tantalum container of the source failed at the weld, allowi… more
Date: November 25, 1963
Creator: Wyder, W. C.; Powers, J. A. & Vallee, R. E.
Partner: UNT Libraries Government Documents Department
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Activation of electrical machinery. Supplement 1. [Preliminary evaluation; not applicable to ground tests]

Description: The following analysis of the induced radioactivity in SNAP-50/SPUR electrical machinery having a high cobalt content is submitted. Induced radioactivity in the flight vehicle will contribute negligibly to allowable radiation levels. This is especially so due to the low neutron to gamma ratio of assumed radiation damage tolerances to semiconductors. A calculation to estimate the order of magnitude of induced radioactivity in cobalt is attached. The calculation is based on a best guess of the ne… more
Date: November 15, 1963
Creator: Smolen, J.R.
Partner: UNT Libraries Government Documents Department
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Feed system performance, NE8010E

Description: No Description Available.
Date: November 14, 1963
Creator: Cemi, S.
Partner: UNT Libraries Government Documents Department
open access

Eddy current tester

Description: No Description Available.
Date: November 11, 1963
Partner: UNT Libraries Government Documents Department
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Control Drum Actuator Checker

Description: The Control Drum Actuator Checker is used to verify the operation of the hydraulic control drum actuators before they are installed on the reactor. It provides for local checkout after installation. It provides for local checkout after installation. It also provides for pre-installation hydraulic leak and pneumatic seal test on individual actuator assemblies.
Date: November 15, 1963
Partner: UNT Libraries Government Documents Department
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Summary report, Flexible VSR`s and VSR channel sleeve development programs

Description: (VSR = vertical safety rod.) This report summarizes results of development programs which have evaluated vertical rod channel sleeving materials and provided flexible vertical rods, acceptable for both interim use before rod channel sleeving, and for subsequent use in sleeved channels. B{sub 4}C is the rod material; graphite and Al oxide are among the sleeve materials.
Date: November 15, 1963
Creator: Kempf, F. J.
Partner: UNT Libraries Government Documents Department
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The reactivity evaluation of PITA-IP22 demonstration load, Supp. 3

Description: PITA-IP22, SUPP II has pointed out that distinct processing advantages may be realized by simplifying the E-N core by minimizing the number of different kinds of charges and the number of target slugs per charge. In an effort to experimentally verify the theoretical effects of converting to a simplified loading, a 102-tube test section, consisting of three 5.0 inch Li-Al target elements per tube was recently charged in H Reactor, under authority of the PITA supplement. The purpose of this docum… more
Date: November 18, 1963
Creator: Essig, T. H.
Partner: UNT Libraries Government Documents Department
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Reactor Physics monthly technical report, October 1963

Description: Progress is reported for the month of October, 1963 in the following research and development activities: Lattice parameter and spectral index experiments; T{sup 3} and Np{sup 237} production rates for a highly enriched fuel loading; graphite heat generation; technical bases; physics study of single tube fuel element; thirty-six tube special 1.25 w/o fuel test loading; and code development FLEX 3.
Date: November 1, 1963
Creator: Nichols, P. F.
Partner: UNT Libraries Government Documents Department
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Development status and incentives for the hot die sizing process

Description: The development status and incentives for the hot the sizing process for reactor production fuels is reviewed and updated and economic justification for the process for four different case studies presented. Based on whether the end bonding step can be eliminated, payout periods of 1.2 to 1.7 years can be realized if the present AlSi process (two-shift, five-day week) is converted to hot die sizing for all reactors. For K-Reactor operation only, Payouts of 1.5 to 2.2 years can be realized by co… more
Date: November 20, 1963
Creator: Blanton, W. A.
Partner: UNT Libraries Government Documents Department
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Fabrication process test evaluation: Shipping, HI-74-SL

Description: The test parts were canned on October 7, 1962 and October 8, 1963. Only six parts, all radiographic rejects, were used for the test instead of 12 parts as originally planned. The original test called for using one very porous and one relatively non-porous sand cast aluminum insert in each container. Shipping experience has shown no significant effect of porosity of inserts on corrosion severity of parts shipped in them. All inserts used were full contour support inserts. Each test part was cann… more
Date: November 8, 1963
Creator: Barber, A. E.
Partner: UNT Libraries Government Documents Department
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