Trends in reactor operation and maintenance have created the need for a rear face Hanford reactor manipulator which can routinely perform certain maintenance and operational functions, and which under high radiation exposure conditions can permit ruptured slug removal or other emergency type operations tb be conducted with little or no personnel radiation exposure. Because of the need for several tools, it was decided that the most desirable approach to a satisfactory manipulator program would be to provide a multi-tool manipulator which could do several distinct tasks. Of these tasks removing the rear face nozzle caps to facilitate removal of ruptured slugs and performance of ruptured slug removal operation were the most profitable routine functions which could be accomplished by a manipulator. The conventional mechanical arm was considered for use in non-routine situations such as recovery of slugs lodged in rear face piping or other disaster type situations which on occasions do happen. To insure the quickest return on the economic benefits of the program, the cap remover development was conducted as a separate study since it is more definitive then,the remainder of the manipulator program. A second phase involving the application of the mechanical arm and development of specialized tools …

It was found from graphite irradiations that the changes can be described by a growth component and a contraction component, and that the contraction is a linear function of exposure, while the growth is a function of both exposure and temperature which saturated at high exposures, say 3000 MWD/a ton. A graph is included. Contraction rate is determined for KW, KE, and H piles.

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: Constitutionality of Senate Bill 444, 56th Legislature.

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: Constitutionality of House Bill 42 of the 56th Leg., the Psychologist Certification Act.

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 or not there could be convictions for false swearing or perjury under the declaration provisions to be signed by the electors when not required to be notarized or upon affidavit of a witness.

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 Chairman of the Livestock Sanitary Commission of Texas is entitled to vote on matters before the Commission.

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: Authority of Texas Commission on Alcoholism to send its Education Director to the Yale Summer School of Alcohol Studies at State expense.

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: Questions relating to amounts due retired Texas Rangers under Section 66, Article XVI, Texas Constitution, and Senate Bill 53, Acts 56th Legislature, Regular Session, 1959.

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: Constitutionality of Senate Bill No. 193, Acts 56th Legislature, Regular Session, 1959, Chapter 27, Page 52, relating to appointment and salaries of court reporters in certain counties.

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: Authorization of the State Building Commission to pay the City of Austin for paving its half of the existing thoroughfare and the additional five feet (approximate) inside the State property line in order to render the access completely finished up to the curbing at the west end of the Supreme Court Building.

Abstract: The theoretical response of a low-geometry scintillation counter to any photon-emitting nuclide whose decay scheme is known is developed. It is used to compute the counting rate, as a function of time, of (1) individual and total fission products resulting from. 10^4 simultaneous slow-neutron fissions of U^235 and (2) several other nuclides for 10 initial atoms. The calculations extend from ~45 min to 301 days after fission.

Results of an analysis to determine the extent of displacement of the EGCR core due to blowdown in case of several postulated hot main gas coolant pipe failures are summarized. Results show that the core will be damaged for ary hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing prior to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect. (auth)

Abstract: "An exploding copper wire, one millimeter in diameter, 30 centimeters long, has been developed as a fuse component for a Los Alamos capacitor energy source to be employed in controlled thermonuclear research studies. The fuse allows the passage of the high normal duty "action" (13,700 ampere-coulombs per capacitor) at a 20-second repetition rate. However, it interrupts the circuit to a shorted capacitor in 12 microseconds, thereby protecting the faulted capacitor from explosive energy consumption. The initial phase of the development included observations of various metals (copper, silver, iron, and nickel) as well as various configurations (straight wires, helixes, foils, and tubes). Direct scaling of previous small exploding wire studies at Sandia Corporation was demonstrated with scaling factors up to 700,000."

The latest HAPO Five Year Program review, indicates that significant increases in Pu production from the eight existing Hanford reactors may be achieved. These production increases would be attained by a combination of several methods including increased process water flow rates, reactor coolant outlet temperature, improved time operated efficiency, conversion ratio and induced transient reactivity looses. In order to provide a realistic basis for budgeting to meet these or other increased production goals, it to necessary that a study program be undertaken to determine in general terms the more nearly optimum plant changes required and to evaluate the economic and technical feasibility of achieving future process conditions. The purpose of this document is to present a plan for the execution of the prepared study. Included in the study outline are the basis study consideration, problem assignments and schedules, required manpower estimates, and tentative cost estimates.

The basic objective of the storage of radioactive wastes is to protect humanity from: (1) direct radiation, (2) contamination of food and water supplies, and (3) contamination of mineral resources. There have been many proposals for the disposal of high level liquid wastes from chemical plants processing nuclear fuels. These include our present Hanford system of tank storage; disposal to deep wells, such as the oil industry uses for discard of brines they pump; storage in salt caverns; disposal to selected geological formations, such as salt domes and anticlines, or impermeable substances, such as clay, etc.; or release to the depths of the ocean. Only the use of tanks and salt caverns can be considered as storage systems. The latter is essentially a dry mine into which material would be placed as solids or packaged liquids. There is no control over the movement of activity with the other disposal methods. This is also potentially true for tank storage should corrosion or other damage cause leakage. Storage of highly radioactive wastes pose a problem in handling the heat generated by fission product decay. Thus, it is advantageous to look for a substance of high density and high thermal conductivity to help …

This memorandum summarizes the results of an analysis to determine the extent of displacement of the EOCR core due to blowdown in case of several postulated hot main gas coolant pipe failures. Results show that the core will be damaged for any hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing proper to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect.

The addition of a surface active agent to an aqeous-organic interface produced a resistance to mass transfer equivalent to slightly more than 1 cm of water. Five semicontinuous Druhm runs were made with 1/2in. thick MgO liners and terminated due to either failures of the UFe nozzle or a top gasket leak. In preliminary scale-up tests of the flame calcination equipment, a maximum feed rate equivalent to 720 g oxides/hr was achieved using a 3-in. i.d. magnesia reflector with an outside wall temperature of 1500°C.

One of the UO2 fuel element designs proposed for use in the PTRT is the nested tubular concepts. This configuration compromises a central fuel todo surrounded by two concentric tubes of fuel (see sketch, appenx I.) . These UO2 shapes are to be jacketed in the Zircaloy and must be separated from each other and the procuresses tyvm vt annular spaces for the passage of coolant. The annuli are established and and maintained by the longitudinal ribs on the outer surface of all three jacketed fuel elements.

Abstract : Methods for the chemical separation of strontium, barium, cesium, cerium, yttrium, zirconium, niobium, and tungsten from complex matrices are described. Procedures for the radiometric determination of the longer-lived isotopes of these elements are outlined. Inert carriers are added and the sample is dissolved by fusion with sodium carbonate. The melt is leached first with water and then with hydrochloric acid. The elements are recovered from these fractions by a series of wet chemical and ion exchange procedures, and gravimetric and radiometric determinations performed.

Report documenting the ongoing research and developments of the Oak Ridge National Laboratory's Homogeneous Reactor Project.

Report containing information regarding the design of the Tory II-A nuclear ramjet engine, and descriptions of its locale, test program, and possible hazards.

Uranium dioxide, uranium monocarbide, and uranium mononitride are potentially useful ceramic nuclear fuel materials. This paper reports the results of a determination of the melting points of these materials.

At the request of Design Development Operation, various heat transfer and fluid flow problems were examined which are peculiar to the CO2 Gas-Cooled Loop in the PRTR. The results of these calculations are desired primarily to aid in demonstrating the adequacy of the design proposal. In addition, the operational limits of the loop and the consequences of the gas loop installation on the PRT reactor are of interest.

One of the research studies of the Chemical Effluents Technology Operation is the improvement of the method for predicting the capacity of a crib for the retention of wastes. In addition to laboratory work the research was extended a field experiment using a simulated crib fed with a solution containing a radioactive tracer. The purpose is twofold: (1) to check the validity of laboratory findings and (2) to observe several features of the behavior of solutions put to ground in the field.