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: Under Section 6 of Article 8306 of Vernon's Civil Statutes, should the first day which an injured employee is unable to perform his regular task for any part of such day be counted as the first day of incapacity for purposes of this section?

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 Roosevelt Hotel is exempt from ad valorem taxes under the stated facts.

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 Article 1109k of Vernon's Civil Statutes is constitutional, and whether disbursements may be made from the Permanent Improvement Fund for the construction of water control and soil conservation structures, and related questions.

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: Construction of the term "allocated" as used in reference to Item 12 of the current appropriation to the State Building 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: Whether students in a barber school may be compensated for services performed by them while in school.

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 Executive Secretary of the Texas Water Pollution Control Board is an "Executive Head of a State Agency" as used in the General Appropriations 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 the Texas Liquor Control Board should cancel the permit granted to Claude D. Neeley by virtue of the stated facts.

The purpose of this report is to transmit revised goal exposure plans for normal production material. These plans supersede previous recommendations. Inherent in these plans are the assumptions: (1) The plant must produce a product containing six percent Pu-240, and (2) product blending capabilities are such that there are no restrictions, other than economic, on Pu-240 buildup at an individual reactor. Due to recent assessed changes in metal performance and conversion of DR Reactor to bumper natural material, revision of recommended goal exposure plans is called for. During the past year a significant shift in the relative metal performance between reactor types occurred. You may have observed the low rupture frequency at the C and K reactors compared to the rupture frequency at the old reactors. Based on the observed experience, goal exposures should be raised for C and K material and lowered for old reactor material. The goal exposure plans recommended herein are based on present, July 1962, assessed rupture performance and the latest conversion tables, incremental metal costs and burnout cost data. The current reactor optimization program was used to determine optimum goal exposures.

The objective of the production test detailed in this report is to authorize testing in the 1706-KE single-pass facility to measure the corrosion of aluminum-clad fuel elements in process water containing 0.20 ppm of Quachrom Glucosate added in place of dichromate and to compare this corrosion to corrosion in normal process water. Tubes SP-5 and SP-6 will be run with 0.20 ppm of Quachrom Glucosate and no dichromate; tests will be made at both pH 6.6 and 7.0. Simultaneous comparison corrosion measurements will be made in two regular tubes, 4561-KE and 4660-KE, supplied with normal process water. The use of SP-1 and SP-2 as additional control tubes is authorized, but not planned. Effluent-activity samples will be taken. Premature discharge and special pick-up are authorized.

To permit more accurate evaluation of the incentives for isotopes producing control rods a determination was performed of the tritium production which would result from conversion to lithium HCR`s. A cursory examination of the gains resulting from the use of lithium shows that a significant amount of tritium could be produced in this manner totaling 1.6 percent of the present Pu-239 production on an atom equivalent basis.

Hanford production reactor operation requires the rejection of very large heat loads. At the present time the heat load is rejected to the Columbia River by the reactor effluent. At low river flows the hot effluent can have appreciable effects on river temperatures. The purpose of this study is to evaluate the feasibility and costs of Cooling Towers as a means of reducing the heat load rejected to the Columbia River. After evaluation of published information, available data, and Hanford plant conditions, it is concluded that: (1) That an induced draft cooling tower, because of its longer cooling range,, would be an effective cooling device for reduction of gross heat load rejected to the Columbia River. Additional study will be required to determine effective use on an area to area basis. (2) That a basically wood, counter-flow, induced draft cooling tower could be installed for approximately $1600 to $2000 per megawatt capacity. This cost is a probable minimum and might be increased by the cost of auxiliary features required for radiation control. (3) That additional study and developmental testing would be required to determine the extent of contamination problems which would result from the cooling tower installation. These problems would …

In order to provide advance direction for 333 Building equipment development work, a survey of potential areas of significant savings through equipment improvement has been made. The purpose of this report is only to indicate areas for investigation, not to define a program. Equipment is adequate to maintain operating continuity and provide for safe operation of the building. Special attention should be given to ``one-of-a-kind`` pieces of equipment. These include the press, cutoff saw, beta heat treat facility and autoradiograph film developer. Manpower savings will result principally from refinement of each operation. There are no really outstanding areas for improvement. The greatest potential for savings is in material costs. These are illustrated in Tables I&IV. Maintenance costs provide for possible significant reductions at braze, vacu-blast, nondestructive test, autoclaves, and chemical processing equipment.

A program has been carried on at Hanford for a number of years to study the effect of neutron radiation on the dimensional changes in graphite. This program has been concerned with the changes measured on small graphite samples which have been exposed to various conditions of temperature and neutron flux. Theoretical studies have also been conducted to determine damage mechanisms. The prime purpose of this research program has been to develop, with the support of the carbon companies a radiation resistant graphite for use as a reactor moderator at high temperatures. In recent years it has been found that graphite contracts under prolonged neutron exposure at temperatures above approximately 300{degrees}C. This contraction is of concern because of the possible effects on reactor operation and life. For example, distortion of process tubes, vertical safety rods, and horizontal control rod channels can cause increased operating and maintenance problems. This report presents information on the actual depression of the graphite moderator at B, D, F, H, DR, and C Reactors.

This is a condensed version of an extended hazards safety review of a proposal to modify the six 8 3/8-inch lattice reactors on the Hanford site. The review was intended to satisfy the specifications for a Preliminary Hazards Review as adopted at the third meeting of the General Electric Technological Hazards Council at New York City on June 15-16, 1961. This supplement is a tabular condensation of the information in the general document. One departure is made from the specifications for such a review: since the overbore proposal is a modification to existent production reactors, those items which will not be changed by the modification are not as a rule included.

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The NPR Hazards Review is being issued in a series of volumes. Volume 1, which has already been published, was of the nature of an expanded summary. It included the results of hazards analyses with some explanatory material to put the results in context. Volume 2 presents results of reviews made after the preparation of Volume 1. It also contains supporting material and details not included in Volume 1. Volumes 1 and 2 together provide a nearly complete ``Design Hazards Review of the NPR.`` However, certain remaining problems still exist and are to be the subject of a continuing R&D program. These problems and programs are discussed in Appendix H. Neither Volume 1 nor Volume 2 treat operational aspects of reactor hazards in detail. This area of concern will be the primary subject of a third volume of the NPR Hazards Review. This third volume, to be prepared and issued at a later date, may also contain information supplementing Volumes 1 and 2.

On Saturday morning, April 7, 1962, at about 1059 Armed Forces time, an accidental nuclear excursion occurred in the plutonium waste recovery facility (Recuplex) of the 234-5 Building. This excursion did not result in any mechanical damage or spread of contamination. Three employees of the General Electric Company received overexposures to gamma and neutron radiation. None were fatally exposed; in each case the overexposure was recognized promptly, and following medical observation and testing the men were released to return to work. In compliance with AEC Manual Chapter 0703, an AEC-HAPO committee composed of two AEC employees and five General Electric employees was appointed by the Manger, HOO, with the concurrence of the General Manager, HAPO, to conduct an investigation of the incident. The committee`s purpose was to determine the cause, nature, and extent of the incident, and recommend action to be taken by others to minimize or preclude future incidents of this magnitude. A study of operating practices and operating conditions that appeared to exist prior to, during, and subsequent to the accident was made by the committee. The committee believes that this report provides sufficient information to answer questions which may arise as a result of the criticality incident …

"This report tells the lessons learned from the second refueling of the Shippingport Atomic Power Station."

A flowsheet representing start-up conditions of the Filtrate Ion Exchange Facility is given. These flowsheet conditions are used for the routine recovery of plutonium from oxalate precipitation filtrates. (LK)

Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.

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Declassified 26 Nov 1973. Fuel elements for the Tory II-C reactor are described along with fuel fabrication processes and mechanical and physical properties of the BeO-- UO/sub 2/ fuel materials. (JRD)

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The problem of current continuity and viscous drag at the boundaries in rotating-plasma experiments is discussed. A hypothetical model having a steady state with axial symmetry is emphasized; it is shown that the discharge impedance derived from this model does not agree with many observations. The Homopolar III'' experiment is described in which the flux surfaces were strongly convex and parallel to the toroidal-shaped electrodes. In this way friction at the insulators was reduced. But the structure of the discharge deviated drastically from axial symmetry near the outer surface. Several studies led to the conclusion that the flow pattern probably involved secondary flows. A detailed analysis of this structure was not possible. It was also found that the rotational speed could not be raised above a few cm/ mu sec because the insulators failed in spite of the special design of the experiment. 28 references. (auth)