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9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090
The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format have been held as consistent as possible with 9-ZOOM, the companion one-dimensional program.
Date:
October 28, 1960
Creator:
Stone, Stuart P.
System:
The UNT Digital Library
9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709 [Supplement]
The following document describes the usage of the LRL 9-ZOOM code, a neutron diffusion theory reactor code for the IBM 709. The code has been modified to solve configuration of a series of stacked cylindrical disks, designating a new geometry case.
Date:
July 12, 1960
Creator:
Stone, S. P.
System:
The UNT Digital Library
13-Watt Curium Fueled Thermoelectric Generator for a Six-Month Space Mission. Final Report
None
Date:
July 1, 1960
Creator:
Bloom, J. L.
System:
The UNT Digital Library
13-Watt Curium-Fueled Thermoelectric Generator for Hard Lunar Impact Mission. Final Report-Subtask 5.8
Results of a conceptual design study for a curium powered thermoelectric generator of minimum size and weight which is capable of sustaining hard impact is presented. The generator produces a minimum of 13 watts of d-c power at 3 volts, and weighs 6.2 pounds excluding shielding. (J.R.D.)
Date:
August 1, 1960
Creator:
Bloom, J. L.
System:
The UNT Digital Library
14-Inch Swing Check Valve Test
The check valve for the Hallam Power Reactor uses a knife-edge bearing for the flapper in place of the usual journal-type bearing. Mechanical cycling in sodium at 600 deg F was used to check operation of this bearing. A total of 309 mechanical cycles was completed with no apparent malfunctioning of the valve. Measured leskage rates were 0.46 gpm at 0.93 psig, 0.73 gpm at 3.4 psig. and 0.32 gpm at 5.9 psig. (M.C.G.)
Date:
February 10, 1960
Creator:
Cygan, R.
System:
The UNT Digital Library
20-ton HE Cratering Experiments in Desert Alluvium: Final Report, May 1962
From abstract and summary: Project Stagecoach consisted of the detonation of three 40,000-pound charges. Blocks of cast TNT were stacked to resemble a sphere and, the whole center-detonated.
Date:
March 1960
Creator:
Vortman, Luke J. & MacDougall, H. R.
System:
The UNT Digital Library
40-MW(E) PROTOTYPE HIGH-TEMPERATURE GAS-COOLED REACTOR RESEARCH AND DEVELOPMENT PROGRAM. Summary Report for the Period January 1, 1959-December 31, 1959 and Quarterly Progress Report for the Period October 1, 1959-December 31, 1959
The HTGR prototype plant (Peach Bottom Power Reactor) is being designed to produce steam at l450 psi and 1000 deg F and to have a net capacity of 40 Mw(e). The fuel temperatures and gas pressures will be approximately the same as those required for larger plants. The reactor data and operating conditions for the graphite-clad core are given. The reactor and primary coolant systems are described. The prospects for development of the graphite-clad fuel element in time for use in the first loading of the reactor were improved by important advances in methods of fabrication and testing of both fuel compacts and graphite sleeves. The hot-pressing process for making fuel compacts was used successfully to make full-size compacts with a uniform distribution of ThC/sub 2/- UC/sub 2/ particles. Three irradiation capsules were fabricated and inserted in a test reactor to determine fuel compact and sleeve performance under HTGR conditions of irradiation and temperature. Two of these ran satisfactorily for the scheduled time of operation. A scope design study of the in-pile loop that will be used to evaluate the full-diameter graphite-clad element was completed. Experiments to determine the extent of fuel migration within the element were undertaken. Preliminary results …
Date:
September 1, 1960
Creator:
unknown
System:
The UNT Digital Library
75,000 KILOWATTS OF ELECTRICITY BY NUCLEAR FISSION AT THE HALLAM NUCLEAR POWER FACILITY
For presentation at ASCE Convention in Reno, Nevada on Thursday, June 23, 1860. A description of the Hallam Nuclear Power Facslity is presented. The history of the project, program participants, site description, component development program, reaetor building, reactor structure, reactor core, sodium systems, instrumentation and control, fuel and component handling, auxsilary sustems, special design features, and advantages of sodium graphite reactor systems are discussed. (M.C.G.)
Date:
January 1, 1960
Creator:
Gronemeyer, F.C. & Merryman, J.W.
System:
The UNT Digital Library
100-K Area electrical power system load and voltage study for project CG-775. Revision
The proposed increased water capacity for 100-K plants will increase the electrical load to be supplied. The load study showed that the capacity of the existing 13.8 kV system is adequate to carry the increased loads proposed for Project CG-775, while for the 5 kV system, an expanded power system is proposed. Likewise, the voltage regulation on the kV system bus will be excessive, and voltage regulators should be added.
Date:
February 22, 1960
Creator:
Thorson, W. R.
System:
The UNT Digital Library
100-N Decontamination Facility Design Guide.
Space has been reserved near the southeast corner of the 100-N Area for the 122-N Decontamination Facility. Previous correspondence between Burns and Roe, Inc and General Electric bae discussed various facilities which might be needed in the building. The concepts of the decontamination processes are under active development by research groups at Hanford. At present, there are several workable processes known; each one has one or more fairly serious drawbacks.
Date:
March 8, 1960
Creator:
Bainard, W. D.
System:
The UNT Digital Library
100-Watt Curium-242 Fueled Thermoelectric Generator--Conceptual Design. SNAP Subtask 5.7 Final Report
A thermoelectric generator which produces 100 watts of electrical power continuously over a six-month operational life in a space environment was designed. It employs the heat produced by the decay of Cm/sup 24/ as the source of power. Uniform output over the operational life of the generator is accomplished by means of a thermally actuated shutter which maintains the hot junction temperature of the thermoelectric conventer at a constunt figure by varying the amount of surplus heat which is radiated directly to space from the heat source. The isotopic heat source is designed to safely contain the Cm/sup 242/ under conditions of launch pad abont and rocket failure, but to burn up upon re-entry to the earth's atmosphere from orbital velocity. (W.L.H.)
Date:
May 1, 1960
Creator:
Weddell, J. B. & Bloom, J.
System:
The UNT Digital Library
300,000-KWE SGR Nuclear Power Plant of Current Technology
Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date:
August 1, 1960
Creator:
Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
System:
The UNT Digital Library
EEN-307, Irradiation of units at low temperature test
EWR-ESE-144, Fifty MC-890 type final assemblies were subjected to irradiation at low temperature test in order to determine if irradiation would reduce the frequency of high voltage breakdowns. A control lot of a like number of units was subjected to low temperature test in the same manner except without irradiation.
Date:
April 13, 1960
Creator:
Guthrie, J.B.
System:
The UNT Digital Library
EN-318 evaluation of slow warm-up through special test of MC-890 type power supplies
ESE-171: This EN run was made to determine if there is any relationship between the H-5 transistor electrical characteristics, the assembly processes, and slow warm-up of the MC-890 Power Supply. Included is the test data on the H-5 transistors and the results of the High Temperature Life Test (185 {degrees}F) of 380 MC-890 Power Supplies.
Date:
September 1, 1960
Creator:
Ling, R.F.
System:
The UNT Digital Library
EEN-333, revised getter flash procedure
EWR No. VTE-188--Tubes processed by flashing getters immediately prior to seal-off from vacuum systems are compared for total residual gas pressure to tubes processed by flashing getters after tubes were sealed off vacuum systems. Comparisons of residual pressures determined from current flows in the cold cathode ion gauge.
Date:
June 28, 1960
Creator:
Brown, W.C.
System:
The UNT Digital Library
568 Report
Final report for a grant contract documenting information about the scope of the project and results.
Date:
1960
Creator:
Pollard, Ernest C. (Ernest Charles), 1906-1997
System:
The UNT Digital Library
The 1958 He4 Scale of Temperatures: Part 1. Introduction, Part 2. Tables for the 1958 Temperature Scale
Report containing information regarding He4 vapor pressure measurement as of 1958, the recent history of the vapor pressure temperature scale, and a series of tables containing these measurements.
Date:
June 17, 1960
Creator:
Brickwedde, F. G. (Ferdinand Graft), 1903-; van Dijk, H.; Durieux, M.; Clement, J. R. & Logan, J. K.
System:
The UNT Digital Library
909B high energy gull generator
None
Date:
December 31, 1960
Creator:
Stephens, W. H.
System:
The UNT Digital Library
Abilene Fire Department Annual Report: 1960
Annual report of the Abilene Fire Department describing the organization and administration, with updates on goals, activities, and accomplishments during fiscal year 1960.
Date:
1960
Creator:
Abilene (Tex.). Fire Department.
System:
The Portal to Texas History
ABRAC--AN IBM-704 THREE DIMENSIONAL NUCLEAR-THERMAL DEPLETION PROGRAM WITH DISTRIBUTED VOID EFFECTS
ABRAC is a three dimensional nuclear thermal depletion program to study the effects of water moderator density changes, resulting from flow variations and boiling, on neutron flux distribution and depletion. The program requires an IBM-704 with a memory of 32.768 words and ten tape units. (auth)
Date:
March 1, 1960
Creator:
Jacobi, W. M.; Lawton, T. J.; Meanor, S. H. & Parrette, J. R.
System:
The UNT Digital Library
ABWR: PL-2 Design Report
From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date:
October 15, 1960
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
ABWR QUARTERLY PROGRESS REPORT, JANUARY 1 TO MARCH 31, 1960. VOLUME I. SL- 1 OPERATIONS AND EVALUATION . VOLUME II. SL-1 HEALTH PHYSICS AND SAFETY
The Stationary Low Power Reactor No. 1 is a three Mw boiling water reactor designed to demonstrate the feasibility of a nuclear reactor to supply electrical power and space heat for remote sites. In addition to performance evaluation the facility provides training for military personnel. The reactor was operated for 1159 hr during the quarter for a total core burnup of 20.3%. Power generation was 103.7 Mwd for a total power accumulation of 466.9 Mwd. Eight malfunctions occurred during the quarter for a total unscheduled downtime of 40 hr 44 min, As a result of malfunctions, aluminum keys will be installed on the control rod drives, instrument well covers were removed, and an order has been placed for a station auxiliaries breaker with a higher temperature rating. Data were taken on seven tests during the quarter. Four of these are expected to be completed during the next quarter. All equipment items on order for the SL-1 power extrapolation expansion program are scheduled to be delivered before June 15, 1960. Although condenser dampers and damper controls, process instrumentation, equipment cabinets, and the radiation monitoring equipment have not yet been ordered, construction will not be delayed. The two tie-ins to the existing …
Date:
May 25, 1960
Creator:
Canfield, R. T.; Rausch, W. P.; Vallario, E. J.; Young, R. G. & Henderson, S. K.
System:
The UNT Digital Library
Accelerator Beam Pulsing System With Extremely Wide Range of Pulse Lengths and Pulse Repetition Rates
The following document describes the usage and results of sending pulsed beams of electrically charged particles with electrically wide range of pulse lengths and pulse repetition rates.
Date:
June 28, 1960
Creator:
Aaland, Kristian
System:
The UNT Digital Library
Accurate Micrometer for Corrosion Samples
A micrometer that utilizes eddy current techniques is described. The gage is capable of measuring nominal 0.5000-in. aluminum rods to an accuracy of plus or minus 0.00005 in., and is unaffected by residual nonconductive surface filins such as oxides or corrosion products. (auth)
Date:
June 1, 1960
Creator:
Woodward, W. J.
System:
The UNT Digital Library