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5,451 Matching Results
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Shock Hydrodynamics of an Exploding Steam Pressure Vessel : Final Report
Initially issued as a brief survey of the shock problems associated with an assumed failure of a pressurizer vessel in a vapor container, this paper contains more detailed calculations and considerations of the analysis present in the original study.
Date:
November 25, 1955
Creator:
Porzel, F. B.
Object Type:
Report
System:
The UNT Digital Library
The Preliminary Shield Design for the 50 MW Commercial Reactor
The investigation in this report were conducted to determine the required shielding to reduce radiation to a workable level, to determine the heeating in the various core components so coolant flow rates could be determined, and to determine the thermal stress and temperature distribution in the structural and load bearing members.
Date:
December 18, 1958
Creator:
Bagley, R. O., Jr.
Object Type:
Report
System:
The UNT Digital Library
Primary Shielding Calculations on the IBM 650 (ROC Codes)
In order to calculate the gamma dose rates in the primary shielding of thermal reactors, four programs were written for thew IBM 650 computer.
Date:
October 15, 1958
Creator:
Rosen, S. S.; Oby, P. V. & Caton, R. L.
Object Type:
Report
System:
The UNT Digital Library
Thermal Design Criteria for APPR Pressurized Water Reactors
The following criteria have been established for thermal design of APPR pressurized-water reactors in this study
Date:
November 26, 1958
Creator:
Love, J.
Object Type:
Report
System:
The UNT Digital Library
Material Specifications for APPR-1 Core II Control Rod Fuel Elements and Absorber Sections
The specifications reported in this study are based on the results of development performed at Oak Ridge National Laboratory under the supervision of the Metallurgy Division.
Date:
December 30, 1958
Creator:
Edgar, E. C. & Robertson, R. D.
Object Type:
Report
System:
The UNT Digital Library
Lovely-1, Program No. 55, Thermal Analysis on the IBM 650
This program is intended to be utilized for the establishment of flow requirements of a tailored flow core.
Date:
November 26, 1958
Creator:
Love, J. D. & Stueck, C. J.
Object Type:
Report
System:
The UNT Digital Library
IBM 650 Computer, Program Number 755, Collation of ROC Code Output
Using the output of programs 653 and 654, each card of which contains the dose information for one dose point at one energy, program 655 produces the sum of the dose values of all energies for one dose point
Date:
December 19, 1958
Creator:
Stueck, C. J.
Object Type:
Report
System:
The UNT Digital Library
Reactivity of Substitution Elements
A method is sought for predicting the reactivity differences between fuel elements attached to control absorbers and fixed fuel elements
Date:
January 19, 1959
Creator:
Murray, R. L., Dr.
Object Type:
Report
System:
The UNT Digital Library
Rolling and Welding Type 430M Tubes to Stainless Steel Overlaid Carbon Steel Tubesheets
In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tube-sheets. The rolled joint was a necessary precaution to prevent secondary water from contacting the stainless steel weld.
Date:
February 16, 1959
Creator:
Bennett, R. W.; Meister, R. P. & Kerton, R. J.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Excursion Analysis on the IBM 650 (Early Code)
The Early program is based on the design to compute the peak power and total energy release which will occur in a reactor due to a step increase of reactivity.
Date:
February 26, 1959
Creator:
Stueck, Clifford J. & Reiback, Earl M.--1931-2006
Object Type:
Report
System:
The UNT Digital Library
Nuclear Excursion Analysis on the IBM 650 (Early Code)
The Early program is based on a design to compute the peak power and total energy release which will occur in a reactor due to a step increase of reactivity.
Date:
February 26, 1959
Creator:
Reiback, Earl M.., 1931-2006 & Stueck, Clifford J.
Object Type:
Report
System:
The UNT Digital Library
Formerly (APPR-1) Research and Development Program (Interim Report on) Core Measurements, Task No. VII
Physics experiments were performed on the SM-1 (formerly APPR-1) core to evaluate temperature and pressure coefficients, transient xenon, neutron source requirements, safety margin and core reactivity as a function of core life.
Date:
March 1, 1959
Creator:
MacKay, S. D.; Tubbs, D. C. & Bagley, R. O.
Object Type:
Report
System:
The UNT Digital Library
SM-2 Vault Criticality
In order to determine the safety of the location of the experimental fuel plates two criticality criteria were applied.
Date:
February 27, 1959
Creator:
Fried, B. E.
Object Type:
Report
System:
The UNT Digital Library
SM-1 (APPR-1) Research and Development Program Activity Buildup Program Task 1
This report presents the results of experimental work performed from February to November 1958 to determine the nature and extent of the buildup of radioactivity in the primary system of the SM-1 (APPR-1).
Date:
1959-03-001
Creator:
Brown, William S.; Bergen, C. Richard; Bergmann, Carl A.; Chupak, Julius; Grant, Louis G. & Ryan, Susanne
Object Type:
Report
System:
The UNT Digital Library
A Boiling Water Analysis Code on the IBM-650
A method has been developed for using the IBM 650 Electronic Data Processing Machine to obtain detailed information concerning thermal and hydraulic conditions within a plate type reactor channel when the coolant in the channel is present in both vapor and liquid phases
Date:
March 10, 1959
Creator:
Beretsky, I. & Pacine, S.
Object Type:
Report
System:
The UNT Digital Library
ATBAC Check Calculation on the IBM 650, Program No. 303
This program using the IBM 650 electronic data processing machine is used primarily as a tool in order to prepare input data for the IBM 704 code, entitle ATBAC. The code calculates steady state thermal characteristics of a plate type fuel element for both a nominal and adverse channel
Date:
March 13, 1959
Creator:
Beretsky, I. & Oby, P. V.
Object Type:
Report
System:
The UNT Digital Library
Organic Coolant Reclamation Annual Report : December 15, 1958 through December 14, 1959
Potential methods have been examined for the reclamation of high boiler arising from the degradation of polyphenol materials in use as reactor coolants and moderators. To define the chemistry of potential reclamation processes, model polyphenol compounds were used. These include biphenyl, o, m and p-terphenyl, and p-quaterphenyl. Emphasis has been on hydrocracking, redistribution (reaction with benzene), and partial reduction. Preliminary study has been made of the application these techniques to high boiler from Santowax-OM used in the OMRE. The three methods show promise but require detailed investigation to minimize carbon formation to locate optimum operating conditions,.
Date:
December 23, 1959
Creator:
Wineman, Robert J.; Adams, J. S.; Gudzinowicz, Benjamin J. & Scola, D. A.
Object Type:
Report
System:
The UNT Digital Library
Biological Effects of Radiation, and Related Biochemical and Physical Studies : Semiannual Progress Report [for] Period May 1, 1959 - October 31, 1959
Progress reports from four divisions are included: (1) Division of Biophysics; (2) Division of Clinical Investigation; (3) Division of Nucleoprotein Chemistry; and (4) Radiochemistry Section.
Date:
December 1, 1959
Creator:
Denues, Arthur Russell Taylor, 1914-
Object Type:
Report
System:
The UNT Digital Library
Results of Experiments Made With U.S.B.M. Electrocerium
Data obtained in test of Bureau of Mines electrocerium are presented. The cerium was subjected to spectrochemical analysis, x-ray diffraction analysis, thermal analysis, metallographic tests, and high-pressure experiments.
Date:
February 26, 1959
Creator:
Miner, William N.
Object Type:
Report
System:
The UNT Digital Library
Studies of Reactor Containment : Monthly Technical Progress Report No. 32
The report covers work performed during the period December 1, 1959 through December 31, 1959. The general objectives of the program of "Studies of Reactor Containment" are to accomplish theoretical and experimental investigations of the loads to which external containment structures for nuclear reactors are subjected in the vent of a violent incident at the reactor core, the evaluation of methods of reducing that loading, and the study of the response of and design criteria for external containment structures as a result of such loading. Progress of technical effort during the report period is summarized for each of the eight tasks of the program..
Date:
January 15, 1960
Creator:
Zaker, T. A. (Thomas Allen)
Object Type:
Report
System:
The UNT Digital Library
Low Energy Nuclear Physics : Second Annual Report for the Period February 1, 1959 to January 31, 1960
The general expression for the angular correlation between radiations produced in successive cascade transitions is derived by use of Racah algebra. The result is then specialized to the beta - gamma correlation and applied to two cases in which additional properties of the photon are specified, the circular polarization and the plane polarization. The prospect of testing time reversal and determining nuclear matrix element ratios by beta - gamma correlation measurements is explored using the nuclide Tm/sup 170/ as an example. The directional angular correlation between the 2.31-Mev beta and the subsequent 0.605-Mev gamma emitted in the decay of Sb/sup 124/ was measured as a function of the beta energy. The K-conversion coefficient of the 279-kev gamma following beta decay of Hg/sup 203/ was measured by comparing the x-ray and gamma intensities in a scintillation spectrometer. The measured valve of alpha /sub k/ = 0.195 plus or minus 0.014 indicates that the transition is M1 with E2 mixed to the extent of 63%. The angular correlation of the 107-1.24 Mev gamma cascade in Zn/sup 68/ following the decay of 68-min Ga/sup 68/ is shown. The Legendre polynomial expansion coefficients were deter-gular correlation in the decay of Sb/ sup 118/ was …
Date:
January 23, 1960
Creator:
Jastram, Philip S. (Philip Sheldon), 1920-1992
Object Type:
Report
System:
The UNT Digital Library
Research on Krypton 85 : Seventh Monthly Progress Report Covering December 1, 1959 to December 31, 1959
Work during this report period includes a continuation of the study of the effect of krypton 85 on the polymerization of styrene; an attempt at evaluation of the polymers produced; and the effect of krypton radiation on the electrical properties of gases, such as the rare gases, and nitrogen, and oxygen. the results obtained are summarized in the report.
Date:
January 21, 1960
Creator:
Miller, H. S.; Marancik, W. G. & Zufall, J.
Object Type:
Report
System:
The UNT Digital Library
Upper Atmosphere Monitoring Program : Progress Report No. 8 for May 1, 1959 through July 31, 1959
The overall scope of the program encompasses both research into the physical parameters involved in the collection of airborne radioactive particles and the development, fabrication and calibration of balloon-borne sampling equipment to enable the precise determination of stratospheric particle concentration and particle size distribution.
Date:
January 15, 1960
Creator:
Baumstark, J.; Jones, S.; Stern, S.; Torgeson, L. & Zeller, W.
Object Type:
Report
System:
The UNT Digital Library
Progress Report for Period Covering January 15, 1960 - February 15, 1960
Thorium Procedure: As was mentioned in the last report, ammonium nitrate was substituted for ferric nitrate as a salting agent. Also, the acidity of the nitrate solution was reduced from 3.0 molar to 0.5 molar. the revised thorium procedure is described in the report. Radium Procedure: Work has ben initiated on the procedure of Petrow, Nietzel and DeSesa (Winchester Procedure) to determine if the procedure is suitable for very low level concentrations of radium.
Date:
February 15, 1960
Creator:
Petrow, Henry G.
Object Type:
Report
System:
The UNT Digital Library