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A Fuel Reprocessing Plant for Fast Ceramic Reactors

Description: A study was made of the adaptation of the HAPO anion exchange process to the reprocessing of Fast Ceramic Reactor (FCR) fuel using the Idaho Small Plant Concept. It is shown that the anion exchange flowsheet meets the reprocessing objectives of the FCR case and can be adequately accommodated in the Small Plant Concept. Capacities of up to 1550 Md(e) are feasible in the Small Plant and unit reprocessing costs range from 0.14 to 0.28 mills/kwh depending on the number of reactors to be processed. … more
Date: February 1, 1962
Creator: Alter, H. W.
Partner: UNT Libraries Government Documents Department
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STAINLESS STEEL WASTES. III. LABORATORY STUDIES OF THE RATE OF REMOVAL OF STAINLESS STEEL IONS BY MERCURY CATHODE ELECTROLYSIS

Description: ABS> The removal rates of iron, nickel, and chromium from synthetic stainless steel waste solutions during electrolysis over a mercury cathode were studied. The loading capacity of the mercury for the stainless steel metals was estimated on the basis of laboratory experiments to be about two% by weight. The laboratory data indicated that, at an electrode potential of --1.80 voits vs S.C.E., 85 ampere-hours per liter of waste removed essentially all of the stainless steel ions from a sulfuric ac… more
Date: February 12, 1962
Creator: Anderson, D. R. & Rhodes, D. W.
Partner: UNT Libraries Government Documents Department
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THE DISTORTED-WAVE THEORY OF DIRECT NUCLEAR REACTIONS. I. "ZERO-RANGE" FORMALISM WITHOUT SPIN-ORBIT COUPLING, AND THE CODE SALLY

Description: The distorted-wave theory of direct nuclear reactions is presented in a unified manner, in which the effects of assuming various reaction mechanisms and nuclear models appear only in certain radial form factors. The zero-range approximation is used, and spin-orbit coupling is neglected in the distorted waves. Formulas are given for transition amplitudes, cross sections, and polarizations. A description is given of the IBM-704 computer code SALLY that is based on these formulas. (auth)
Date: February 1, 1962
Creator: Bassel, R.H.; Drisko, R.M. & Satchler, G.R.
Partner: UNT Libraries Government Documents Department
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Numerical results of PT IP-412-AI, B and C reactors export system test

Description: The purpose of this document is to present the numerical results of a production test of the last ditch water backup system performed at B and C reactors on December 15, 1961. The main purpose of the production test was to determine more accurately the capacity of the export system for supplying flow to a dual reactor area under several simulated emergency conditions where BPA power to all areas has been interrupted and the steam supply to one old area has been lost. In addition, the flow capac… more
Date: February 20, 1962
Creator: Benson, J. L.
Partner: UNT Libraries Government Documents Department
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Progress Report on Neutron Radiography

Description: BS> The potential advantages of neutron radiography as an inspection method are discussed along with a historical review and discussions of neutron sources and detectors. The results of the current investigation of neutron-image detectors are discussed in regard to photographic speed, relative neutron-gamma response, and resolution comparisons. Two neutron-image detecting methods are discussed. In one, the direct-exposure method, both the converter screens and the film are exposed to the neutro… more
Date: February 1, 1962
Creator: Berger, H. & McGonnagle, W.J.
Partner: UNT Libraries Government Documents Department
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Secondary Missiles Generated by Nuclear-Produced Blast Waves

Description: The generation of secondary missiles by blast waves was investigated in Operation Plumbbob for three nuclear detonations with estimated yields of 11, 38, and 44.5 kt. A trapping technique was used to determine the impact velocities for 17,524 missiles (stones, glass fragments, spheres, and military debris or steel fragments) which occurred in open areas, houses, and an underground shelter with an open entryway. The equivalent ideal-wave peak overpressures computed from measured blast data for t… more
Date: February 1, 1962
Creator: Bowen, I. G.; Franklin, M. E.; Fletcher, E. R. & Albright, R. W.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Chemical Development Section C Progress Report for October-December 1961

Description: Recovery of Th (and U) from Granitic Rock. Recovery of Th by acid leaching ten addltlonal granite samples (36 to 82 ppm Th) from the Conway formation in N. H. ranged from about 50 to 85%, and averaged about 70%, Study of the effect of grind size on the recovery of Th from Conway and Plkes Peak granites showed no significant differences in the range minus 20 to minus 200 mesh. The Th concentration in a sized Conway granite sample was found to be much greater in the fine than in the coarse fracti… more
Date: February 21, 1962
Creator: Brown, K.B.
Partner: UNT Libraries Government Documents Department
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Conceptual Design for a 75 MWE Mixed Spectrum Superheating Reactor Power Plant

Description: The design, performance, and cost information on the nuclear portion of the Mixed Spectrum Superheater power plant are emphasized. The research and development programs required to ensure plant feasibility are also presented. The nuclear steam supply system, reactor auxiliary systems, radiation control systems, control and instrumentation, special test instrumentation, plant operation and maintenance, steam cycle, turbine plant, general service systems, preliminary safeguards considerations, ex… more
Date: February 25, 1962
Creator: Brynsvold, G. V.; Hikido, K.; Reynolds, A. B. & Riley, D. R.
Partner: UNT Libraries Government Documents Department
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Summary of geology for two potential underground test sites in basaltic rocks, Nevada Test Site. Technical Letter: NTS-15

Description: The geologic map of the Paiute Ridge (Papoose Lake SW) 7 1/2-minute quadrangle shows an area of about 4 square miles on the east side of Yucca Flat that is underlain by basaltic rocks. These rocks are estimated to be as much as 1,000 feet in places and occur as a capping on a small mesa and as lopoliths, igneous masses that in cross section are saucer-shaped. This area was further studied to determine the geologic features of the basaltic rocks in order to evaluate the potential use of this are… more
Date: February 7, 1962
Creator: Byers, F.M. Jr. & Hazlewood, R.M.
Partner: UNT Libraries Government Documents Department
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CRITICALITY EXCURSION OF NOVEMBER 10, 1961

Description: A criticality excursion occurred at the Oak Ridge Critical Experiments Laboratory on November l0, l961 as enriched uranium metal, neutron reflected and moderated by hydrogen, was being assembled. It is estimated that the energy yield was between 10/sup 15/ and 10/sup 16/ fissions. There was no personnel exposure or property damage. Fission product contamination, both airborne and contained in the metal, decayed sufficiently overnight to allow unhindered continuation of the experiment. The excur… more
Date: February 13, 1962
Creator: Callihan, D.
Partner: UNT Libraries Government Documents Department
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High-Temperature Vapor-Filled Thermionic Converter

Description: Progress Development of a high temperature, vaporfilled thermionic converter for application with a nuclear reactor for space-vehicle electrical power generation is reported. Problems associated with the design and opera tion of a thermionic converter employing a UC-ZrC emitter, a cesium plasma for space charge neutralization, and a high-temperature collector are described. Emitter fabrication techniques are also described. A test cell employing a cylindrical UC-ZrC emitter, which was pressure … more
Date: February 15, 1962
Creator: Campbell, A. E.; Carpenter, F. D.; Dunlay, J. B. & Pidd, R. W.
Partner: UNT Libraries Government Documents Department
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Summary status report internal corrosion of ribbed aluminum process tubes

Description: The increasing incidence of leaking process tubes, and the approaching end of the useful life of process tubes in the C and K Reactors, have focused attention upon the various sources of aluminum process tube leaks. Further, the replacement of large numbers of process tubes with new ones, also of aluminum, will require continued attention to these sources to make efficient use of the new tubes. One of the sources of process tube leaks is the corrosion that attacks the interior surface of the pr… more
Date: February 19, 1962
Creator: Carlson, P. A.; Curtiss, D. H.; Miller, N. R. & Van Wormer, F. W.
Partner: UNT Libraries Government Documents Department
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Thermal design of SNAP reactors

Description: No Description Available.
Date: February 1, 1962
Creator: Cohn, P.D.
Partner: UNT Libraries Government Documents Department
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Efficiency of Multiple Traversal Targets

Description: The efficiency of multiple traversal targets is defined as the probability that a proton dies by making a nuclear collision in the target rather than by hitting the limit of the synchrotron aperture. The efficiencies of Be, Al, Cu, and Pb targets are shown for 15 and 30-Bev protons in the Brooknaven AGS. Beryllium was found to be the most efficient. (M.C.G.)
Date: February 1, 1962
Creator: Courant, E. D.
Partner: UNT Libraries Government Documents Department
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ISOPERIMETRIC AND OTHER INEQUALITIES IN THE THEORY OF NEUTRON TRANSPORT, II

Description: In a prevlous paper, some inequalities occurring in the one-veloclty theory of neutron transport with lsotropic scattering were derived. Some of the previous results are generalized to the case of linearly anisotropic scattering. (auth)
Date: February 27, 1962
Creator: Dresner, L.
Partner: UNT Libraries Government Documents Department
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Kinetic Experiments on Water Boilers-"A" Core Report-Part 2. Analysis of Results

Description: The status of the analytic portion of the KEWB program at the time of completion of the spherical core experiments is summarized. Three computer programs were developed for use in this analytic effort. The first reassembles and smooths three decades of reactor power data read separately from oscillogram records of reactor excursions. It then computes the logarithmic derivative of the power, energy release, fuel solution temperature, and temperature compensated reactivity. The second program uti… more
Date: February 1962
Creator: Dunenfeld, M.
Partner: UNT Libraries Government Documents Department
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KER loop fuel testing program and schedule, CY 1962

Description: The interests of several departments at Hanford are involved in the planning, execution and evaluation of the results of the KER loop testing effort in support of the NPR fuel program. The varied interests and activities of the participating groups must be well-integrated if effective use of our limited testing capability is to be made. The purpose of this report is to help achieve this integration by summarizing the current thinking on the goals of the NPR fuel testing program and by presentin… more
Date: February 14, 1962
Creator: Evans, T.W. & Kratzer, W.K.
Partner: UNT Libraries Government Documents Department
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Studies of Nuclear Resonant Absorption of Gamma Rays. Quarterly Report No. 4 Covering Period June 1, 1961 to August 31, 1961

Description: The effect of polarizing mngnetic field intensity on the nuclear resonant absorption was studied by varying the field strength at a 1-mc Co/sup 57/ source from 0 to 1000 gauss while keeping the absorber between the poles of a magnet having a fixed field of 800 gauss. The rates of resonance absorption change with field intensity were greatest in the region of 300 to 1000 gauss, and the% nuclear resonant absorption for 1000-gauss fields was 8.5 and 26% for perpendicular and parallel fields, respe… more
Date: February 23, 1962
Creator: Ezop, J. J.
Partner: UNT Libraries Government Documents Department
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Gcr-Orr Loop No. 2 Filter Tests. Part Ii

Description: Tests of Cambridge absolute filters, Model Sl-071, specified for use in the GCR-ORR Loop No. 2 as full-flow, primary coolant fiiters were completed. kD.O.P/ (dioctylphthalate) efficiency tests were performed on three filters in the as-received condition, on two filters following canning and thermal cycling, and on one of the canned fiIters following bsking out. None of the three units met the design criteria of 99.97% efficiency for removal of 0.3 micron particles in the as-received condition. … more
Date: February 19, 1962
Creator: Flint, F. A. & Smith, A. M.
Partner: UNT Libraries Government Documents Department
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EQUIPOISE-3: A TWO DIMENSIONAL, TWO-GROUP, NEUTRON DIFFUSION CODE FOR THE IBM-7090 COMPUTER

Description: EQUIPOISE-3 is an IBM-7090 FORTRAN programmed code for the solution of two-group, two-dimensional, neutron diffusion equations. A maximum of 2l00 mesh points may be used, and the code will solve problems in either rectangular or cylindrical geometry. Logarithmic derivative boundary conditions are allowed, and removal of neutrons from both groups is permitted. Adjoint fluxes with the associated fluxadjoint flux regional integrals may be calculated automatically if desired. A constant buckling, g… more
Date: February 21, 1962
Creator: Fowler, T.B. & Tobias, M.L.
Partner: UNT Libraries Government Documents Department
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Stress Corrosion of Type 304 Stainless Steel in Simulated Superheat Reactor Environments. [Part] 1. Informal Aec Research and Develoment Report 568-Tio-2

Description: A fuel jacket failure that occurred in May 1961 in the Type 304 stainless steel clad fuel element exposed in the Vallecitos Boiling Water Reactor superheated steam loop (SADE) was attributed to chloride stress corrosion cracking. In order to better understand the failure, a test program was carried out to try to reproduce the rapid stress corrosion attack in the simulated superheat reactor environment of the CL-1 superheat facility. The methods of corrosion testing under heat transfer condition… more
Date: February 26, 1962
Creator: Gaul, G. G.; Pearl, W. L. & Siegler, M.
Partner: UNT Libraries Government Documents Department
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