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Office of Scientific & Technical Information Technical Reports
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Atomic Energy Commission Reports
296
7.5 Minute Series (Topographic)
139
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138
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101
General Electric Company Atomic Power Reports
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5 and 5 hot cell configuration for E-MAD facility. Phase 2
None
Date:
January 17, 1963
Creator:
Svasek, A. J.
Object Type:
Report
System:
The UNT Digital Library
A 5 mechanical test of core support block. Preliminary report
This report contains seven different configurations of support blocks.
Date:
September 30, 1963
Creator:
Lee, D. Y.
Object Type:
Report
System:
The UNT Digital Library
A 23-Group Neutron Thermalization Cross Section Library
A set of 23-group neutron cross sections for use in the calculation of neutron thermalization and thermal neutron spectral effects in SNAP reactors is compiled. The sources and methods used to obtain the cross sections are described. (auth)
Date:
July 15, 1963
Creator:
Doctor, R. D. & Boling, M. A.
Object Type:
Report
System:
The UNT Digital Library
40-MW(e) Prototype High-Temperature Gas-Cooled Reactor Research and Development Program. Quarterly Progress Report for the Period Ending June 30, 1962
Research and development progress specifically directed toward the construction of a 40-Mw(e) prototype power plant employing a high-temperature, gas-cooled, graphitemoderated reactor known as the HTGR is reported. Irradiation of element III-B in the in-pile loop continued satisfactorily. The element has generated a total of l36.3 Mw-hr of fission heat. The gross activity in the purge stream increased slightly to about 350 mu C/cm/sup 3/. By taking larger gas samples than were previously taken, a value of 0.02 VC/cm/sup 3/ was obtained for the gross activity of the primary loop. Element III-A, which was removed from the loop after generating 133 Mw-hr of fission heat, was disassembled and examined. No fuel-compact damage of any type was visible. Determination of the distribution of fission products in the element is under way, Fissionproduct- release data for in-pile-loop element III-A were calculated. During the 133 Mw- hr of operation, the release fraction increased by approximately one order of magnitude. Also calculated were the xenon and krypton release data for the first 100 Mw-hr of III-B operation. The release rate for the longer-lived isotopes increased bv about a factor of 10 and that of the shorter-lived isotopes by about a factor of 100. A test …
Date:
October 31, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
100-N technical manual. Volume 2A: Systems descriptions
This report contains engineering drawings for the control room, reactor monitoring systems, and reactor control systems for the N reactor. Each console in the control room is detailed. Other systems discussed are: stack air monitoring system, charging machine control systems, and heating and ventilation control systems. A N reactor plant glossary is included.
Date:
December 31, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
190-H drawdown test
A discrepancy of about 1000 gpm has existed between the full-flow recorded 190, 105 and ROL flows. While past operating practices have not used the 190 or ROL flow rates for official purposes, the disquieting, though not theoretically unexplicable, differences require some quantitative resolution. On November 24, 1962, a drawdown test of the 190-H storage tanks was performed to establish the accuracy of the various flowmeters. The drawdown test of the 190 storage tanks was run at the beginning of a scheduled reactor shutdown. With the full reactor flow supplied by the electric process pumps feeding from the storage tanks, the 183-H supply to the storage tanks was valved off. Additionally, non-process water usually taken from the storage tanks was valved off. The storage tank water levels were taken, then recorded as a function of time.
Date:
January 17, 1963
Creator:
Cremer, B. R. & Bokish, K. P.
Object Type:
Report
System:
The UNT Digital Library
A 200-Watt Conduction-Cooled Reactor Power Supply for Space Application
The limited supply of relatively long-half-life isotopes having a reasonably high power density and the low conversion efficiencies obtainable with thermoelectric devices have so far limited the power output of isotope-fueled sources of electric power to several tens of watts. In addition, the high cost of the available isotopes results in a very large expense for isotope-fueled generators producing several hundred watts. It appears that a small, minimumweight, conduction-cooled reactor is an attractive alternate to the isotope-fueled power supplies in the 200-w size range. The proposed reactor is a small, high-density fast core of U/sup 233/ surrounded by a beryllium reflector. This approach, generally speaking, gives a reactor that is more compact and of lighter weight than can be obtained with a moderated system having a softer neutron spectrum. In the reactor design, the path of heat flow is from the core to the inner reflector and then to the thermoelements in close contact with the inner reflector. The reject heat flowing from the thermoelement cold junctions enters the outer pontion of the reflector, which acts as the heat sink and conducts the reject heat to the large, circular, tapered-fin radiator which is attached to the reflector. Survey physics calculations …
Date:
March 1, 1963
Creator:
MacFarlane, D. R.
Object Type:
Report
System:
The UNT Digital Library
250-Watt(e) Isotope-Fueled Thermionic Generator Study. Final Report.
None
Date:
January 1, 1963
Creator:
Kortier, W. E. & Lyon, W. C.
Object Type:
Report
System:
The UNT Digital Library
1000 Mwe Closed Cycle Water Reactor Study
This report has two volumes, volume 1 contains the summary and detailed description of plant design, volume 2 contains a comprehensive nuclear evaluation of the reactor core.
Date:
March 1, 1963
Creator:
Westinghouse Electric Corp., Pittsburgh, Pa. Atomic Power Div.
Object Type:
Report
System:
The UNT Digital Library
1000 MWE Closed Cycle Water Reactor Study Volume II
This report includes the nuclear evaluation that has been conducted for the purpse of studying those problem areas which are expected to increase in severity as the core size is increased to produce 1000 MWE.
Date:
March 1, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
1000-Mwe Sgr and Prototype Evaluation Study. Volume 2. 200-Mwe Sgr Prototype Preliminary Design
None
Date:
December 1, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
1000-Mwe Sgr and Prototype Evaluation Study. Volume I. Large Sgr Design Bases, Economics, and Development Program
None
Date:
December 1, 1963
Creator:
unknown
Object Type:
Report
System:
The UNT Digital Library
1000 MWe SGR Parameter Study--Core Thermal and Hydraulic Analysis
None
Date:
November 19, 1963
Creator:
Imig, J. K.
Object Type:
Report
System:
The UNT Digital Library
1559/RE: A CODE TO COMPUTE RESONANCE INTEGRALS IN MIXTURES
The computer program 1559/RE is an experimental IBM-704 code in FORTRAN language for computing the resonance integrals of isotopes in mixtures in the presence of hydrogenic moderation. There may be up to four isotopes, each with no more than 75 resolved resonance levels. Doppler broadening and interference scattering are included No estimate is made of contributions from unresolved resonances. Typical running times are 30 min (with no Doppler broadening) to 90 min (with Doppler broadening) for problems involving 67 levels and unit lethargy widths. Input and theory are discussed, and a typical listing is given. (auth)
Date:
May 1, 1963
Creator:
Kelber, C.N.
Object Type:
Report
System:
The UNT Digital Library
A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations
An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.
Date:
April 1963
Creator:
Walker, D. G.
Object Type:
Report
System:
The UNT Digital Library
A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method
An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.
Date:
April 1963
Creator:
Walker, D. G.
Object Type:
Report
System:
The UNT Digital Library
1963 State legislative program of the Advisory Commission on Intergovernmental Relations
The ACIR Library is composed of publications that study the interactions between different levels of government. This document addresses the ACIR state legislative program.
Date:
October 1963
Creator:
United States. Advisory Commission on Intergovernmental Relations.
Object Type:
Book
System:
The UNT Digital Library
4th Annual Report
The ACIR Library is composed of publications that study the interactions between different levels of government. This document is an annual report.
Date:
January 1963
Creator:
United States. Advisory Commission on Intergovernmental Relations.
Object Type:
Book
System:
The UNT Digital Library
630A Maritime Nuclear Steam Generator: Status Report Number 1
From foreword: The primary purpose of this document is to set forth the current status of the 630A Nuclear Steam Generator, under development for the U.S. AEC.
Date:
September 12, 1963
Creator:
General Electric Company. Nuclear Materials and Propulsion Operation.
Object Type:
Report
System:
The UNT Digital Library
Abscopal Effects of Localized Irradiation by Accelerator Beams
The aim of this series of experiments was to evaluate the existence of abscopal effects of irradiation. No attempt was made towards the elucidation of mechanisms. Very early in the history of radiological research it was noticed radiation produces both local and general effects involving the entire body. Gauss and Lembcke introduced the term "Roentgenkater" (radiation sickness). They ascribed these "General Effects" to the circulation of toxic substances released from cells that disintegrated following irradiation.
Date:
February 1, 1963
Creator:
Jansen, C. R.; Bond, V. P.; Rai, K. R. & Lippincott, S. W.
Object Type:
Report
System:
The UNT Digital Library
Absolute and Comparison Techniques for Calibrating Shock Pickups; Frequency Limitations for Shock Motion Measurements - Extracted from Minutes
This report addresses the absolute calibration, a technique used for calibrating shock pickups. This technique can be used for an applied motion regardless of its shape.
Date:
August 26, 1963
Creator:
Bouche, R. R.
Object Type:
Article
System:
The UNT Digital Library
Absorption-Multistage Flash Distillation Process
"The major factors which influence the cost of water production from sea water by distillation methods are (1) the cost of fuel or energy required by the distilling plant, and (2) the required capital investment. Preliminary studies on the application of absorption or solution cycles to distillation methods for saline water conversion indicated that the fuel cost or thermal economy of a distillation plant could be improved by combining the distillation process with an absorption or solution cycle" (p. 1).
Date:
September 1963
Creator:
Fluor-Singmaster & Breyer, Inc.
Object Type:
Report
System:
The UNT Digital Library
Acceptance Test Facility Safeguards Report.
The purpose of this report is to describe the operation of the Acceptance Test Facility (ATF) and testing of SNAP 10A Auxiliary Power Units (APU) in the facility.
Date:
January 1, 1963
Creator:
Soske, P. L.; Ostenso, A. S.; Kamensky, F. J. & Berger, S.
Object Type:
Report
System:
The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)
The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date:
December 1, 1963
Creator:
Rider, B. F.; Ruiz, C. P.; Luke, P. S., Jr.; Peterson, J. P., Jr. & Smith, F. R.
Object Type:
Report
System:
The UNT Digital Library