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1,454
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633
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629
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619
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480
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396
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192
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Achieve!, June 1991
Periodic newsletter discussing information related to student drop-out rates, relevant legislative issues, and prevention programs. This issue focuses on the role of parents in school reform.
Date:
June 7, 1991
Creator:
Texas Research League
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Register: 2022 3rd Quarterly Index October 7, 2022, Index of Rules: Pages 23-46, Index of Non-Rulemaking Notices: Pages 47-64
A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code. This 3rd Quarterly Index contains Index of Rules an Index of Non-Rulemaking Notices.
Date:
October 7, 2022
Creator:
Texas. Secretary of State.
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Register, Volume 47, Number 40, Pages 6515-6694, October 07, 2022
A weekly publication, the Texas Register serves as the journal of state agency rulemaking for Texas. Information published in the Texas Register includes proposed, adopted, withdrawn and emergency rule actions, notices of state agency review of agency rules, governor's appointments, attorney general opinions, and miscellaneous documents such as requests for proposals. After adoption, these rulemaking actions are codified into the Texas Administrative Code.
Date:
October 7, 2022
Creator:
Texas. Secretary of State.
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Agriculture, Volume 36, Number 3, September 2020
Monthly magazine issued by the Texas Farm Bureau for farmers and ranchers discussing current news and issues in agriculture.
Date:
September 7, 2020
Creator:
Texas Farm Bureau
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Agriculture, Volume 36, Number 2, August 2020
Monthly magazine issued by the Texas Farm Bureau for farmers and ranchers discussing current news and issues in agriculture.
Date:
August 7, 2020
Creator:
Texas Farm Bureau
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Agriculture, Volume 36, Number 11, May 2021
Monthly magazine issued by the Texas Farm Bureau for farmers and ranchers discussing current news and issues in agriculture.
Date:
May 7, 2021
Creator:
Texas Farm Bureau
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
Texas Agriculture, Volume 37, Number 7, January 2022
Monthly magazine issued by the Texas Farm Bureau for farmers and ranchers discussing current news and issues in agriculture.
Date:
January 7, 2022
Creator:
Texas Farm Bureau
Object Type:
Journal/Magazine/Newsletter
System:
The Portal to Texas History
The Fast Effect in a Beryllium Moderated Reactor
The effect of the (n, 2n) and (n, o<) reactions on the neutron economy of a beryllium moderated reactor is investigated.
Date:
December 7, 1959
Creator:
Novak, P. E.
Object Type:
Report
System:
The UNT Digital Library
Amendment No. 2 To License Application For Nuclear Test Reactor
GE is amending its application of 6/5/57 to construct and operate the Nuclear Test Reactor in order to incorporate changes in procedure and equipment.
Date:
October 7, 1958
Creator:
General Electric Company
Object Type:
Report
System:
The UNT Digital Library
ORNL Metal Recovery Plant Processing Clementine Reactor Fuel Elements: Terminal Report
This report presents data obtained from processing 33 Clementine Reactor fuel elements in the ORNL Metal Recovery Plant to recover approximately 15 kg of plutonium and 0.16 g of americium.
Date:
September 7, 1955
Creator:
Matherne, J. L.; Brooksbank, R. K.; Campbell, D. O.; Chandler, J. M.; Rylton, C. D.; Leuse, R. E. et al.
Object Type:
Report
System:
The UNT Digital Library
The Effects of Reactor Irradiation of Thorium-Uranium Alloy Fuel Plates
Several plates of 98.7% Th - 1.2% U 235 (clad in aluminum) were irradiated in the MTR for an integrated flux of 2.6 x 10 21 neutrons/cm2. Although these samples represent an early development in bonding of aluminum to thorium and there are better methods at present, the bond proved to be quite strong and both clad and core were dimensionally stable under irradiation. The production of uranium 233 was as much as theory would indicate and the total amount of fissionable material material after irradiation and after decay of the protactinium 233 was greater than before irradiation. A fuel element of this nature appears to offer excellent potentialities from the standpoint of radiation stability.
Date:
September 7, 1955
Creator:
Carrell, R. M.
Object Type:
Report
System:
The UNT Digital Library
An Evaluation of the Corrosion and Oxidation Resistance of High-Temperature Brazing Alloys
The fabrication of heat exchangers and radiators to be used in conjunction with high-temperature nuclear reactors may present exceedingly complex problems. Rigid heat transfer requirements may necessitate the use of compact assemblies of thin-walled small-diameter tubes as integral parts of the heat transfer units. Intricate designs may also be required in which cooling fins must be securely joined to the tubes at closely spaced intervals. In addition to the difficulties in fabrication imposed by the designs themselves, the high operating temperatures involved require the careful selection of materials and joining techniques. The choice of fabrication procedure for a given component must not only be based upon the stresses and temperatures to be encountered, but also upon special factors peculiar to nuclear service. Since many reactor applications employ highly corrosive environments, compatibility of the structural ma terials with the corrosive media is of paramount importance. The low nuclear cross-section require ment for brazing alloys to be used inside the re actor also places stringent limitations on the possible choices of in-pile applications. The use of boron in alloys for certain service may not be considered feasible, for example, because of its high nuclear absorption cross section. Although welding is used extensively …
Date:
November 7, 1956
Creator:
Hoffman, E. E.; Leitten, C. F., Jr.; Patriarca, P.; Slaughter, G. M.; Pope, J. E.; Shubert, C. E. et al.
Object Type:
Report
System:
The UNT Digital Library
The Oak Ridge National Laboratory Research Reactor Safeguard Report
This memorandum sets forth a recommended uniform basis for designing the ORN shield.This includes design values for power level and emergent radiation, standards values for various material properties, and basic radiation intensities.
Date:
October 7, 1954
Creator:
Binford, F. T.; Cole, T. E. & Gill, J.P.
Object Type:
Report
System:
The UNT Digital Library
The Oak Ridge National Laboratory Research Reactor Safeguard Report
The proposed ORNL Research Reactor is designed to serve as a general purpose research tool delivering a maximum thermal flux of 8x10^13 n/cm2-sec at the initial power level of five megawatts. Operation at power levels up to ten megawatts is proposed for such items as sufficient cooling capacity is available to handle the increased heat load. The reactor will use MTR-type fuel elements and beryllium reflector pieces in a 7 x 9 grid with moderation and cooling provided by forced circulation of demineralized water. The reactor tanks are submerged in a barytes concrete pool, filled with water, which serves as a biological shield. Experimental facilities include two 18" diameter "Engineering Test Facilities" and six 6" diameter beam holes. In addition, access to the core is available through the water of the pool. The result on the surrounding population of release to the atmosphere of a large fraction of the radioactive material in the core has been computed by two methods. It is shown that under certain conditions off-area personnel could be subjected to greater than the maximum permissible exposure. An analysis of the maximum hazard caused by the release of the entire contents of the core to the local watershed …
Date:
October 7, 1954
Creator:
Binford, F. T.; Cole, T. E. & Gill, J. P.
Object Type:
Report
System:
The UNT Digital Library
Remarks on the Double Dispersion Approach to the Bethe-Salpeter Equation
The following remarks are made on the applicability of the double dispersion approach to the Beth-Salpeter equation introduced previously. 1) Any invariant solution of the Bethe-Salpeter equation in ladder approximation satisfies the double dispersion representation when the total energy-momentum is space-lake. 2) There are some exceptional invariant solutions which are not given by the previous method in the equal-mass case, but the existence of such solutions is very unlikely in the unequal-mass case. 3) In the case of the general separated kernel the previous results give the correct solutions even if the kernel does not reproduce the double dispersion representation.
Date:
August 7, 1962
Creator:
Nakanishi, Noboru
Object Type:
Report
System:
The UNT Digital Library
Process Improvement Transition Authorization #11-I Installation of Van Stone Seal Inserts - F Reactor.
Continued operation of F reactor with high water collection rates during the past 12 years has resulted in numerous detrimental effects. In addition to promoting external corrosion tube leaks, water leaks have corroded the Gunbarrel to the biological shield donut assemblies and cast iron thermal shield blocks, thus preventing the majority of tubes in F reactor from unrestrained thermal expansion. Fatigue of the Van Stone flange under the resulting compression loads leads to eventual failure in some cases. In addition, excessive compression loads exerted against the nozzle gasket result in plastic deformation and eventual failures of the gasket.
Date:
June 7, 1960
Creator:
Russell, A.
Object Type:
Report
System:
The UNT Digital Library
Scavenging as a Predisposal Treatment for NPR Decontamination Wastes
A disposal method is needed for wastes generated from the decontamination of the NPR primary coolant loop. The limitations imposed by facilities design criteria for the disposal of NPR wastes preclude direct river release of the spent cleaning solutions because of the anticipated quantities of radioactive material in these wastes. The soil at a 100-N Area trench or crib should not be relied on for removing radionucleotides by ion exchange or filtration because of the high salt content of the wastes and the presence of solubilizing reagents. Permanent or long term storage of large volume of decontamination wastes would be expensive. A waste treatment is sought for concentrating the radioactive materials to volume suitable for long term storage and which would permit dispersal of the excess liquid to the environs.
Date:
June 7, 1960
Creator:
Koop, W. N.
Object Type:
Report
System:
The UNT Digital Library
A Wrist Badge Film Dosimeter for Hand Dose Measurement
The wrist badge provides a dosimeter that is useful in estimating the radiation dose to the hands and forearms. Its new shield system gives good gamma and slow neutron dose discrimination with duPont 552 film packets. The film can be evaluated using the present technique and equipment. Several attempts to develop hand dosimeters have been made. Finger rings using film have been used routinely but have not been entirely satisfactory for all situations. The wrist badge was developed to provide improved gamma and slow neutron dose measurement of the upper extremities under certain appropriate conditions. The wrist badge dosimeter is not a substitute or alternate for finger ring dosimeters but is a necessary dosimeter for some extremity exposure situations.
Date:
June 7, 1960
Creator:
Bramson, P. E.
Object Type:
Report
System:
The UNT Digital Library
APDAC-I, A PCTR Data Analysis Code for the IBM 709
A flexible foil data processing program is described. Raw data on foil radioactivity are the basic input information required. Output may consists of relative activities, saturated activities, and/or cadmium ratio and flux spectrum data. A statistical analysis of the data is executed with the direct calculation, and errors estimated for the output data.
Date:
September 7, 1960
Creator:
Lilley, J. R.
Object Type:
Report
System:
The UNT Digital Library
Out-of-Reactor Tests on Pu-Al Type PRTR Elements for 1706-KER Testing
The small amount of irradiation tenting experience on the plutonium-aluminum type elements planned for the Plutonium Recycle Test Reactor (PRTR) has made such testing of great importance. The high temperature pressurized recirculating water 1706 KER facility is one possible place for conducting investigations of the irradiation behavior of this type fuel element. To obtain the maximum information from the in-reactor testing and to detect possible problems, out-of-reactor test both at room and anticipated operating temperatures must be made. Room temperature pressure drop measurements and high temperatures performance of two prototypical fuel element designs proposed for KER testing are reported in this document.
Date:
August 7, 1959
Creator:
Doman, D. R.
Object Type:
Report
System:
The UNT Digital Library
Heat Transfer Testing
Several tests are being performed and others being planned to investigate the role of heat transfer in corrosion processes. These tests are measuring both corrosion rates of metals (Zr-2 and X-8001 aluminum) under heat transfer, and the temperature rise associated with the buildup of the corrosion product. A brief description of these tests is given in this report.
Date:
July 7, 1959
Creator:
Doman, D. R.; Hokenson, J.F. & Lobsinger, R. J.
Object Type:
Report
System:
The UNT Digital Library
Experimental PRTR Moderator Flow Distribution Results
The moderator fluid will be injected into the PRTR calandrin through injectors located between the shroud tubes and at the bottom of the calandrin. It is important that the size and arrangement of the injectors be such that complete mixing of the moderator will occur and prevent hot sports from forming in the moderator. Such hot spots could lead to undesired changes in the moderating characteristics due to boiling within the moderator. Also of importance is the requirement that the injector should not produce excessive turbulence at the moderator surface thereby complicating moderator level control. To determine the extent of moderator mixing within the calandrin, experimental studies were made employing a full scale PRTR calandrin mockup.
Date:
January 7, 1959
Creator:
Kreiter, M. R.
Object Type:
Report
System:
The UNT Digital Library
Theoretical Study of a Source of Intermediate Energy Neutrons
Abstract. An analysis is made of a proposal to obtain neutrons of 15-25 Kev energy by moderating fast neutrons in aluminum and then reflecting off titanium. The fluxes calculated do not significantly exceed those obtainable from a standard antimony-beryllium photoneutron source. Two appendices treat aspects of the transport of neutrons through a slab of finite thickness.
Date:
January 7, 1954
Creator:
Bludman, Sidney A.
Object Type:
Report
System:
The UNT Digital Library
Correlation of Kinetic Isotope Effects with Chemical Bonding in Three Center Reactions
We consider the kinetic isotope effect in three center reactions of the type of A+BC→AB+C. Such model calculations are a good approximation to primary hydrogen isotope effects. For abstraction or transfer reactions, B becomes H, D, or T. The dynamics of the three storm system are calculated for a general quadratic potential, with the assumption that the potential energy is constant along the reaction coordinate (flat top barrier). This model system can be calculated in detail and serves to illustrate the relationship between kinetic isotope effect and chemical bonding in the transition state. The statistical mechanical part of the calculation can be carried out exactly within the framework transition state theory or in any one of a number of approximations. The γ bar method gives particularly good insight into the chemistry of the problem with a minimum of arithmetic.
Date:
January 7, 1964
Creator:
Bigeleisen, Jacob
Object Type:
Report
System:
The UNT Digital Library