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Comparison of Gaseous Waste Handling Systems for PL-3

Description: Gaseous waste handling systems are compared for direct and indirect boiling water and pressurized water reactors for PL-3 application. Areas that are common to the various concepts are not discussed since they do not enter into a comparison study. The major differences present are in the handling of active gases released to or held in the primary system coolant. These gases which could be present, their possibIe release from the system, and the necessary processing requirements are discussed in… more
Date: February 28, 1962
Creator: Noble, J. H. & Duke, E. E.
Partner: UNT Libraries Government Documents Department
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DEVELOPMENT OF FREEZE VALVE FOR USE IN THE MSRE

Description: Three types of frozen-seal valves'' were tested for possible use in the MSRE. The seal was melted by direct resistance heat, by induction heat, and by clamp-on Calrod heat. The frozen seal was made in a preformed restriction section of a standard piece of pipe by a cooling-gas jet stream directed at the restriction. All three valves performed satisfactorily through 100 test cycles. The Calrodheated valve was selected for MSRE use on the basis of simplicity of design and of operation. Two of the… more
Date: February 28, 1962
Creator: Richardson, M.
Partner: UNT Libraries Government Documents Department
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Startup and Initial Testing of SM-1 Core II With Special Components

Description: The loading operation for SM-1 Core II is described. Results of startup physics measurements (Test A-300 (Series) and fission product iodine monitoring in the primary coolant are given. The SM-1 Core II initial loading progressed satisfactorily, fulfilling the predictions of the zero power experiment performed at the Alco Criticality Facility. The initial cold clean five rod bank position was 6.53 in.; the initial hot, no xenon, five rod bank position was 9.62 in.; the initial hot, equilibrium … more
Date: February 28, 1962
Creator: Moote, F. G. & Schrader, E. W.
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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NIGHTMARE-AN IBM 7090 CODE FOR THE CALCULATION OF GAMMA HEATING IN CYLINDRICAL GEOMETRY

Description: The NIGHTMARE program calculates the gamma-dose rate at any point in or near a reactor by means of the NDA buildup-factor method. The source distributton is obtained from a two-group, two-dimensional diffusion code (EQUIPOISE-2). Seven gamma-energy groups are used. As many as nine different concentric cylindrical regions may be considered, but only radial variation of attenuation and buildup properties is permdtted. Two schemes of estimating buildup factors through a succession of materials are… more
Date: February 26, 1962
Creator: Tobias, M.L.; Vondy, D.R. & Lietzke, M.P.
Partner: UNT Libraries Government Documents Department
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Prerequisite requirements for higher graphite temperature limits and/or nitrogen atmosphere at all reactors

Description: The graphite temperature limits specified in the process standards-are being closely approached or have limited power levels at B, D, DR, and reactors. An increase of approximately 50--100 C in graphite temperature limits at these reactors would permit year-around operation on bulk outlet temperature limits. There has been considerable recent interest in extending to all reactors the use of nitrogen as a reactor gas constituent. With present graphite temperature limits, significant benefit from… more
Date: February 26, 1962
Creator: Graves, S. M.
Partner: UNT Libraries Government Documents Department
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River contamination reduction studies an evaluation of the artificial lake concept

Description: Currently the Irradiation Processing Department is working on a program which has as its goal the reduction of radioactive discharge to the Columbia River. The most significant radioactive isotopes of concern are the relatively long lived isotopes P{sup 32}, Zn{sup 65}, As{sup 76}, N{sub p}{sup 239} and Cr{sup 5l}. Because of their relatively long life they can be found in the Columbia River well below the Hanford Plant. P{sup 32}, because it is absorbed and concentrated by the river biota is o… more
Date: February 26, 1962
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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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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Hallam Nuclear Power Facility, Preoperational Test Interim Report Dry Excess Loading

Description: A test to obtain data for use in determining the reactivlty wohh of Na in the Hallam reactor core is described. The test is designed to obtain information on the dry temperature coefficient of reactivity and to train operators. An evaluation of results is included. (J.R.D.)
Date: February 25, 1962
Creator: Kempt, H. C. & Corcoran, W. P.
Partner: UNT Libraries Government Documents Department
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Hallam Nuclear Power Facility Preoperational Test Completion Report Dry Criticality

Description: A dry criticality test was carried out to determine the minimum critical mass of the HNPF Core without sodium. A subcritical calibration of the central control rod was performed and the relative reactivity worths of the inner ring of six control rods were determined. The extrapolated critical loading for the various plots after each incremental fuel loading with all rods out is shown. A tabulation is presented of multiplication data taken throughout the dry critical test. In order to find the r… more
Date: February 24, 1962
Creator: Kempt, H. C. & Corcoran, W. P.
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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Chemical Processing Department Monthly Report: January 1962

Description: This report, for January 1962 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.
Date: February 21, 1962
Creator: Hanford Atomic Products Operation. Chemical Processing Department.
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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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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THE TWENTY GRAND PROGRAM FOR THE NUMERICAL SOLUTION OF FEW-GROUP NEUTRON DIFFUSION EQUATIONS IN TWO DIMENSIONS

Description: The TWENTY GRAND program for the IBM 7090 is capable of solving neutron diffusion problems in cylindrical or slab geometry for one to six groups. Up to 3000 mesh points may be used. Neutron transfer from any group to any other group is permitted. Leakage in the third dimension in X-Y geometry may be treated by a buckling which can vary with region and group. Three types of symmetry conditions may be handled automatically. The zero flux, zero derivative, and logarithmic boundary conditions are a… more
Date: February 21, 1962
Creator: Tobias, M.L. & Fowler, T.B.
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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Welding and Brazing of High-Temperature Radiators and Heat Exchangers

Description: Procedures were developed for fabricating highperformance radiators and heat exchangers for the Aircraft Nuclear Propulsion (ANP) Program. These components, which contain multitudes of tube-to-tube sheet and tube-to-fin joints, are similar in design to those under consideration for a variety of space vehicle applications. In order to ensure reliability of the tube-to-tube sheet joints, techniques producing welds of extremely high quality were used and back brazing of the welds with a suitable a… more
Date: February 20, 1962
Creator: Slaughter, G. M. & Patriarca, P.
Partner: UNT Libraries Government Documents Department
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