Texas Attorney General Opinion: WW-1396 (open access)

Texas Attorney General Opinion: WW-1396

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the Frank White farm, which has been designated by the Hood-Parker Soil Conservation District as an experimental farm, is exempt from ad valorem taxes under stated facts.
Date: July 25, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1398 (open access)

Texas Attorney General Opinion: WW-1398

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether a City Councilman is disqualified from holding such office by virtue of being an officer of the depository bank where the city funds are deposited, and, if so, whether the County Attorney has a duty to institute removal proceedings.
Date: July 25, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1400 (open access)

Texas Attorney General Opinion: WW-1400

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether the County Auditor should audit the books of the District Clerk concerning payments received as a result of divorce proceedings where the Court ordered one spouse to make child support payments to the District Clerk's office.
Date: July 25, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1401 (open access)

Texas Attorney General Opinion: WW-1401

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether a county may pave and maintain streets located within a municipality and related questions.
Date: July 25, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1403 (open access)

Texas Attorney General Opinion: WW-1403

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether a nurse or a practitioner's assistant can dispense drugs or medicine to his patients under the practitioner's direction and supervision, and related question.
Date: July 25, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Texas Attorney General Opinion: WW-1404 (open access)

Texas Attorney General Opinion: WW-1404

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Will Wilson, regarding a legal question submitted for clarification: Whether Chapter 6, Title 94, V.C.S., repealed Chapter 5, Title 94, V.C.S.
Date: July 25, 1962
Creator: Texas. Attorney-General's Office.
Object Type: Text
System: The Portal to Texas History
Summary of HRT Run 25 (open access)

Summary of HRT Run 25

Run 25 was the final period of power operational of the HRT. The reactor was operated for periods of 62, 8, 52, and 80 hours at 5 Mw with no outward indication of fuel and core and blanket average temperatures of 270 and 230 deg C, respectively. The uranium concentration in the was 1.7 to 2.0 g U/kg D/sub 2/O. Longer periods of operation were prevented by mechanical difficulties, notably with the fuel feed pump. While the reactor was subcritical after the last of the above runs, the upper patch in the core tank wall became dislodged, allowing greater core-to-blanket mixing. The resultant blanket uranium concentration was 2.9 g U/kg D/sub 2/O. The reactor was subsequently operated at April 28, 1961. The experiment was operated at high temperature for a total of 10,866 hours. The system was critical for a total of 8,841 hours and produced 16,295 Mwhours of power. The fuel, heavy water, and some corrosion specimens were recovered, and the reactor was stored in an assembled state. (auth)
Date: July 25, 1962
Creator: Engel, J. R.; Bauman, H. F.; Buchanan, J. R.; Haubenreich, P. N.; Piper, H. B. & Richardson, D. M.
Object Type: Report
System: The UNT Digital Library
Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina (open access)

Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina

A seven- to twenty-fold volume reduction can be obtained from fluidized bed calcination of aqueous aluminum nitrate wastes, depending on the operating conditions employed and their effect on the intra-panticle porosity and absolute density of the calcined alumina. Among the calcining variables, only the bed temperature and the fuel aluminum concentration had a significant effect on the intra-particle porosity of alumina generated during studies conducted primarily in a two-foot-square fluidized bed calciner. A quantitative correlation of the effect of these variables is presented. Alumina with an intra-particle porosity as low as five per cent can be generated by employing a suitable combination of low bed temperature and dilute aluminum feed concentration. Feed sodium concentration and product alpha alumina content were found to have minor effect on intra-particle porosity. Results also show that an inverse relationship exists between the nitrate content of the calcine and the calcination temperature. (auth)
Date: July 25, 1962
Creator: Wheeler, B. R.; Grimmett, E. S. & Buckham, J. A.
Object Type: Report
System: The UNT Digital Library
A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Quarterly Progress Report for the Period Ending June 30, 1962 (open access)

A PROGRAM OF BASIC RESEARCH ON MECHANICAL PROPERTIES OF REACTOR MATERIALS. Quarterly Progress Report for the Period Ending June 30, 1962

The effect of modifying the dislocation structure by room-temperature prestraining on the subsequent yielding behavior at 77 deg K is being studied. Results on tantalum single crystals indicated that a considerable decrease in the early yield stress for a given strain is effected by prestraining at room temperature. Twinning was observed in the tantalum at 77 deg K and normal rates of strain. It is shown that the potential barrler to dislocation motion in crystalline solids can be measured in relatively pure bcc transition metals such as Nb, Ta, Mo, and W. Work is being carried out to extend the method of differential calorimetry to measurements of stored-energy-release spectra in deformed bcc metals. Measurements for copper are discussed. (M.C.G.)
Date: July 25, 1962
Creator: Trozera, T.A.; Flynn, P.W.; Chambers, R.H. & White, J.L.
Object Type: Report
System: The UNT Digital Library
Preliminary hazards review overboring Hanford reactors (open access)

Preliminary hazards review overboring Hanford reactors

The General Electric Company, as prime contractor to the AEC at Hanford, is proposing to modify the lattice characteristics of the 8 3/8-inch lattice reactors for the purposes of improving the conversion ratio of these reactors. The proposed overbore modification of the reactors would remove the existing aluminum process tubes, enlarge the diameters of the graphite channels by about one-half inch, insert smooth-bore Zircaloy-2 process tubes and refuel the reactor with larger size, self-supported fuel elements. The overbore fuel will remain the internally-and-externally-cooled cylindrical type, but the weight per foot will be about twice that of the present fuel element. The removal of the inlet and outlet piping connections which would be required in the overboring process will permit the replacement of the existing fittings with ones of improved design. Furthermore, new orifices and venturis which are compatible with the hydraulic characteristics of the overbore tube and fuel geometry and the pumping system will be installed. No basic changes are proposed in the pumping system though the reactor flaw rate may be increased 5--10 percent by changes in hydraulic characteristics depending on the water plant flow capacity.
Date: July 25, 1962
Creator: Nilson, R. & Carlson, P. A.
Object Type: Report
System: The UNT Digital Library
Final report: Irradiation performance of a coextruded, Zircaloy-2-clad three-rod cluster fuel elements, PT-IP-186-A (open access)

Final report: Irradiation performance of a coextruded, Zircaloy-2-clad three-rod cluster fuel elements, PT-IP-186-A

One of the early candidate fuel elements for N Reactor use was the coextruded, Zircaloy-2-clad seven-rod cluster. As part of the program of evaluating the seven-rod cluster geometry, three-rod cluster fuel elements, two and three feet long, were irradiated. These long cluster fuel elements were irradiated to determine the distortion (or sag) which might occur at the center of the unsupported length during irradiation. Two three-rod clusters made up of 0.630 inch diameter rods, containing natural uranium cores were irradiated in KER Loop 3. The rods of one cluster were three feet long; the rods of the other were two feet long. The three-feet long rods were supported at their ends and at their midlengths, the two-feet long rods only at their ends. During the irradiation, the maximum core temperature was 435 C. The fuel elements were discharged from the loop after they had reached an exposure of 1400 MWD/T. Following the discharge, the fuel elements were visually examined in the KE view pit. No sag was observed in any of the rods. The test demonstrated that two- and three-feet long rod cluster fuel elements can be irradiated without appreciable sag occurring in the rods.
Date: July 25, 1962
Creator: Call, R. L.
Object Type: Report
System: The UNT Digital Library
Low exposure irradiation of an enriched seven-rod cluster in KER Loop 1, PR-IP-246-A: Final report (open access)

Low exposure irradiation of an enriched seven-rod cluster in KER Loop 1, PR-IP-246-A: Final report

One of the early candidate fuel elements for the N Reactor was the seven-rod cluster fuel element. An objective of the program to determine the suitability of the seven-rod cluster fuel element for N Reactor use was to evaluate the irradiation performance of coextruded, Zircaloy-2-clad, seven-rod cluster fuel elements over a range of exposures from low exposures to high exposures. This report describes the irradiation testing of an enriched seven-rod cluster fuel element which was irradiated to 520 MWD/r.
Date: July 25, 1962
Creator: Call, R. L.
Object Type: Report
System: The UNT Digital Library
Power Distributions for Type 3 Replacement Cores for SM-1, SM-1A and PM-2A (open access)

Power Distributions for Type 3 Replacement Cores for SM-1, SM-1A and PM-2A

Abstract: The most adverse power distribution and power peaking factors have been developed for Type 3 replacement cores for SM-1, SM-1A, and PM-2A. Also included is the 37 element Type 3 core for SM-1, which is known as SM-1 Core III and is a prototype of a Type 3 core for PM-2A. The power distributions were compared with measured distributions obtained on type 3 fuel elements in SM-1, SM-1A and PM-2A core configurations. Using the measured data as a standard, correction factors were obtained and applied to the analytical predictions of the most adverse power distribution.
Date: July 25, 1962
Creator: Oggerino, J. P.
Object Type: Report
System: The UNT Digital Library