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Instruction Manual, Mercury Relay Pulse Generator Model 1-1212C
The Model Q-1212C Pulser is a single frequency (60 pps) generator whose output waveform is characterized by a rise-time of less than 4 mµsec and, depending upon the method of termination, an exponential decay having a time constant of 300 or 600µsec. The waveform approximates that produced by a radiation detector. The waveform approximates that produced by a radiation detector. The maximum available output from the instrument is 10 volts, positive or negative polarity, and is continuously adjustable by means of step switches and a 10-turn potentiometer. The potentiometer has a linearity of 0.1%.
Date:
September 20, 1960
Creator:
Fairstein, E.
System:
The UNT Digital Library
Oak Ridge National Laboratory Radioisotopes Procedures Manual
Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.
Date:
June 1964
Creator:
Case, F. N.; Fuccillo, D. A., Jr.; Ewing, Sylvia B.; Acree, E. H.; McFarland, C. E.; Massey, B. J. et al.
System:
The UNT Digital Library
Electrical Design Standards and Graphical Symbols
This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date, and supersedes the previously issued ORNL Electrical Symbols List and CF-58-12-141, Electrical and Electronic Drawing Standards for Wiring and Device Coding and Applications.
Date:
October 1960
Creator:
Bates, A.E.G; Bowelle, M.M.; Horton, J. L.; Moore, R. L.; Hyland, R. F. & Brashear, C.
System:
The UNT Digital Library
A Manual of HRE Control and Instrumentation
Technical reports outlining the controls for the Homogeneous Reactor Experiment (HRE); controls are divided into three principal groups. 1. Reactor. 2. Process or auxiliary. 3. Power generation. These are the classifications designating the primary functions of the controls. [From Introduction]
Date:
January 23, 1952
Creator:
Quarles, L. R. & Walker, W. P.
System:
The UNT Digital Library
Electrical and Electronic Symbols & Drawing Committee
This manual represents the recommendations of the Instrumentation and Controls Division committee on Electrical and Electronic Symbols and Drawing that have been issued to date. Section I consists of copies of the American Standards Association Graphical Symbols for Electrical Diagrams, with certain variations or additions that have been recommended by the Committee to clarify or more positively identify the device or element symbolized. Since publication of the present ASA standards, certain elements, such as the transistor, have come into common use. Committee and represent the symbols have been selected after considerable study by the Committee and represent the symbols that seem to be standard Reference Information series, Interim E--1.
Date:
November 1961
Creator:
Bates, A.E.G
System:
The UNT Digital Library
The ORNL Four-Linear-Element Package Analog Computer (FLEPAC) Instruction Manual
Report describing a computing device called the Four-Linear-Element Package Analog Computer (FLEPAC) at the Oak Ridge National Laboratory. The report includes a description of FLEPAC as well as instructions for its use.
Date:
1959
Creator:
Green, F. P.
System:
The UNT Digital Library
Analysis of Uranium Fuel-Element Wafers from Atomics International for Uranium, Plutonium and Samarium
Five irradiated and five unirradiated wafers were analyzed. Each wafer was analyzed for samarium by emission spectrography. The unirradiated wafers were analyzed for uranium by coulometric and potentiometric methods and for uranium isotopes by mass spectrometry. The irradiated wafers were analyzed for uranium and plutonium by coulometric methods, for plutonium isotopes by the 256-channel alpha pulse analyzer, and for the isotopes of uranium and of plutonium by mass spectrometry. The methods of preparing wafers for analysis are discussed; the data are tabulated.
Date:
December 27, 1960
Creator:
Gaitanis, M. J.
System:
The UNT Digital Library
Generalized Heat Conduction Code for the IBM-7090 Computer
The IBM-70% code GHT has been programmed for the 7090computer, to be run under control of the IBM-7090 FORTAN Monitor System. By eliminating the use of tapes for intermediate number storage, it has been possible to reduce computing time by a factor of 26 over the 704. A minimum of three tapes are required; one for input, one for output, and the System tape. One scratch tape is required for transient problems, and one punch tape is required if the steady-state temperature distribution is to be punched on cards.
Date:
February 9, 1961
Creator:
Fowler, T. B.
System:
The UNT Digital Library
Equipoise-2: A Two-Dimensional, Two-Group, Neutron-Diffusion Code for the IBM-7090 Computer
Equipoise-2, a two-dimensional, two-group neutron-diffusion code in R-Z geometry, has been programmed for the IBM-7090 computer. This code was designed to permit the running of large numbers of cases without requiring excessive machine time. Typical running times are of the order of one to three minutes per case for a 1000-point problems. The maximum number of mesh points that can be used is 1444.
Date:
November 21, 1960
Creator:
Fowler, T. B. & Tobias, Melvin
System:
The UNT Digital Library
A Transport Calculation of the HFIR Beam Hole Currents
An estimate was made of the beam hole currents to be expected from both the radial and tangential beam holes in the present HFIR design. The angular fluxes required for these calculation were determined by an 18-group, S8 transport calculation (SNG reactor code). Both type beam holes produced thermal neutron currents of 7.5 x 10^10 neutrons/cm^2 sec. at a power level of 100 Mw. The nonthermal component of the beam current was 7.0 x 10^10 and 4.5 x 10^10 neutrons/cm^2 -sec for the radial and tangential holes, respectively.
Date:
December 5, 1960
Creator:
Claiborne, H. C. & Rakavy, G.
System:
The UNT Digital Library
Specifications for Fuel Assemblies for Core I of the Experimental Gas-Cooled Reactor
These specifications for the fuel assemblies for Core I of the Experimental Gas-Cooled Reactor (EGCR) have been developed for use in procuring the first core loading. A fuel assembly for EGCR consists of a cluster of seven cylindrical fuel elements spaced and supported within a graphite sleeve. Each fuel element consists of a stainless steel tube containing a column of hollow UO2 pellets and having a spacer brazed at the midsection to control the spacing between fuel elements in a cluster. A master specification for the fuel assembly, a supplementary specification for each of the components, and a specification on record keeping during manufacture are included.
Date:
December 9, 1960
Creator:
Coobs, J. H.; Wick, E. A. & Evans, R. M.
System:
The UNT Digital Library
Paper Presented by M. Minashin
The attached paper is a translation of a rough draft of the paper, "Operating Experience of the APS-1", presented by M. Minashin in Russian at the IAEA Conference on Small and Medium Power Reactors, Vienna, Austria, September 5-9, 1960.
Date:
November 1, 1960
Creator:
Ullmann, J. W. & Gerrrard, Martha
System:
The UNT Digital Library
After Shutdown Heating in the HFIR
After shutdown heating rates have been calculated for the target, control plates, and the beryllium reflector of the HFIR. Hilvety previously calculated the after shutdown heating rates in the element and his results are reported in ORNL CP-60-4-110. Decay times of 1.0 10, 10^2, 10^3, 10^4, and 10^5 seconds have been considered, and heat fluxes have been computed for all of the mentioned components. The greatest heat fluxes were found to be at the surfaces of the control plates and the permanent beryllium reflector.
Date:
December 29, 1960
Creator:
McLain, H. A.
System:
The UNT Digital Library
Pulse Amplifier Manual
Manual for the use and repair of repair pulse amplifiers. This covers general testing routines, specific tests, and a bibliography of related materials.
Date:
1962
Creator:
Fairstein, E.
System:
The UNT Digital Library
Summary of HRT Run 14
This report presents a detailed study of HRT Run 14, which was abruptly terminated by the formation of a hole in the Zircaloy-2 core tank. In this run the reactor was operated at high temperature and pressure for ten days from March 25 to April 4, 1958. Nuclear power operation extended from March 29 until April 4, when fuel solution leaked into the heavy-water blanket. The maximum power level attained was 6.4 Mw.
Date:
June 8, 1959
Creator:
Engel, J. R.; Haubenreich, P. N.; Kolb, J. O. & Richardson, D. M.
System:
The UNT Digital Library
Lecture Notes on Reactor Controls
This course on reactor controls is for the purpose of acquainting the student with some of the elementary considerations involved in setting up a control and safety system for a nuclear reactor. This material is the outgrowth of the notes prepared for the lectures on Reactor Controls given in the Oak Ridge School of Reactor Technologu. The lectures given by T. E. Cole in 1953-1955 are the basis of portions of the subject matter on reactor kinetics. Many suggestions and ideas contributed by E. R. Mann are included throughout almost every section. In addition, several members of the Oak Ridge National Laboratory, and of the Reactor Controls Department in particular, have provided information which has been included in these lectures notes.
Date:
June 24, 1959
Creator:
Walker, C. S.
System:
The UNT Digital Library
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings
Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date:
August 1964
Creator:
Binford, F. T.; Cramer, E. N. & Cramer, E. N.
System:
The UNT Digital Library
Calculation of Shield Induced Gamma Radiation Escaping Through Openings in a Biological Shield -- Application to the HRT
A method was developed for calculating shield induced gamma radiation escaping through openings in a biological shield. The method was applied to the HRT and the results indicated that the contribution to the dose from induced activity in the HRT shield was around 0.1 r/hr and was insignificant in comparison to to other mechanisms contributing to the escape of gamma rays through shield openings.
Date:
January 11, 1957
Creator:
Claiborne, H. C. & Fowler, T. B.
System:
The UNT Digital Library
Uranium-235 Abundance by Gamma Spectrometry
Techniques are described for determining U-235 abundance by measurement of the intensity of 0.18 Mev gamma radiation. One method involves measurement of the ratio of the intensity of 0.18-Mev radiation to that of 0.1 Mev radiation. The preferred technique consists of chemical separation of uranium followed by direct counting of 0.18-Mev photons. Application has been made in analysis of uranium samples of abundances in the range of 0.05% to 93%. Accuracy appears to be better than 3% if the abundance is between 0.7% and 100%. Findings in the self-absorption of 0.18 Mev radiation in uranium oxide are presented.
Date:
January 2, 1957
Creator:
Reynolds, S. A. & Eldridge, J. S.
System:
The UNT Digital Library
Possible Radiation Damage to the Stator Windings of the HRT Circulating Pump
A study of the degree and effects of radiation damage to the motor winding of the HRT 400-! canned motor circulating pumps was made. With the gamma flux estimate and the available radiation damage data, the effective life of the stator windings was estimated to be about one year, for normal operation of the pump and motor.
Date:
April 80, 1957
Creator:
Gift, E. H.
System:
The UNT Digital Library
Section 9.0 to Status Report on the Disposal of Radioactive Wastes
Section 9.0 is the "Chemical Processes for Fission Product Concentration, Removal or Fixation" section of the Status Report on the Disposal of Radioactive Wastes. The report is divided into four areas: (1) Introduction; (2) Summary of waste processes; (3) Concept of a multipurpose waste processing facility; and (4) Details of some of the waste processes.
Date:
September 3, 1957
Creator:
Culler, Floyd L., Jr.
System:
The UNT Digital Library
Calculation of Wall-Scattered Gamma Radiation Escaping through a Shield Opening - Application to the HRT
A simplified method was developed for calculating wall-scatter gamma radiation escaping through a shield opening. The method was applied to the HRT and the results showed that next to the line of sight contribution, scattering of the wall of the shield opening was the main contribution to the dose at the rear edge of the shield. Design charts were prepared that give the dose as a function of the gamma source location with the reactor cell.
Date:
February 19, 1957
Creator:
Claiborne, H. C. & Fowler, T. B.
System:
The UNT Digital Library
Control System for HRT Cooling Water
The circuits described herein and shown functionally in Fig. 1 are to be added to the HRT control circuit to provide control and protection for the revised HRT cooling water system. The circuitry will provide protection against excess pressure in the demineralized cooling water loop and cooling water activity, will initiate action to insure containment of activity in event of an explosion and will provide emergency cooling water from the tower basin when required.
Date:
February 11, 1957
Creator:
Moore, R. L.
System:
The UNT Digital Library
The ORNL GCR-3, a 750-Mw(e) Gas-Cooled Clad-Fuel Reactor Power Plant : A Joint Design Study
Report documenting the design of the Oak Ridge National Laboratory Gas-Cooled Clad-Fuel Reactor Power Plant. This includes design criteria and parameters, costs, and descriptions of systems.
Date:
1963
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library