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 authority of Department of Public Safety in enforcing the Texas Motor Carrier Act as to motor carriers transporting in interstate commerce, over Texas highways, commodities which are exempt from ICC regulations.

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 tax refund may be made on special fuel delivered by the user thereof into the fuel supply tank of a motor vehicle, under the provisions of Chap. 10 of Title 122A, Taxation-General.

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 Commissioner's Court of Jefferson County has the authority to retain legal counsel to defend certain members of a Grand Jury in cases brought against them 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, Crawford Martin, regarding a legal question submitted for clarification: Whether the Alabama-Coushatta Indian Reservation-Tribal Council, with the consent of the Texas Commission for Indian Affairs has the authority under Art. 5421z, V. C. S., to borrow money from a bank for the purposes stated and to execute security for the loan on the chattels to be purchased with the borrowed money.

From abstract: "Fuel materials proposed for use in the Advanced Test Reactor were evaluated."

"This report covers fire tests conducted on an experimental design of a wooden-jacket shield for radioisotope shipping containers" (p. i).

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A nontechnical description of the mechanisms of local and world-wide fall-out from nuclear explosions is given. The relative importance of local fall-out in a nuclear war is discussed. The effects upon man of world-wide fall-out from past nuclear testing is discussed. It is pointed out that doses to man frcm testing are quite small when compared to the natural radiation background. (auth)

Experiments were carried out on a Cs/sup 137/ plaque source of 40 x 40 x 1/2 inches. Measurements were made of dose distributions in water and of photon spectral distributions in paraffin. For 9-inch-thick water siab absorbers without air gaps, it was found from the preliminary experiments that the depth dose uniformity can be varied over the range 1.10 to 1.40. The absolute dose rates found were in general agreement with design predictions which indicate irradiator efficiencies in the region of 50% and dose rates in the region of 1 Megarad/hour for high-level indicators. (W.D.M.)

An instrument has been developed for the detection of uranium dust in the atmosphere. The principle feature of this device is its ability to indicate a gross release of alpha radiation within a few minutes of its occurrence. The unit will sound an alarm when either the indicated level or the rate of increase exceeds preset values above normal background variations. (auth)

The criteria and methods for test evaluation of electromagnetic clutch characteristics are discussed. An evaluation of the relative merits of two commercial clutches, both of the multiple disk friction type, is presented with test results. One of these clutches was incorporated in the clutch assembly design for the Array Reactor (SM-2). (auth)

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Several safety parameters are calculated for a large, fast, Na-cooled, oxide-fueled reactor. The Doppler coefficient is studied as regards its effect on the reactivity during a power excursion, and its dependence on the neutron spectrum, on the concentrations of U/sup 238/, Pu /sup 239/ , a nd Pu/sup 240/, on spatial temperature and power distributions, and on temperature. Other parameters studied include the Na temperature coefficient of reactivity, and the reactivity insertion caused by total Na loss; reactivity coefficients caused by thermal expansion of fuel and steel cladding; the excess operating reactivity; and the reactivity caused by a fuel slump. The effects of a Be reflector on neutron lifetimes are determined. The safety aspects are balanced against economic considerations. (T.F.H.)

Quarterly progress report describing work related to a study of radiation physics problems involved in the design of high-level cesium-137 gamma sources. It outlines work completed and ongoing goals for the project.

This document discusses a proposal that certain presently installed reactor process water outlet temperature data logging equipment in subject reactors to be replaced with new functionally simplified equipment of a more adequate design. The primary purpose of the proposed installation is to replace existing equipment which is obsolete and in three reactors is worn out to the point where the equipment is out of service frequently for periods of time up to 8 hours or more. The new equipment will provide reliable process tube temperature information for use in the functions of reactor control and product accountability. Based upon anticipated incremental production gains resulting from use of the new equipment, the amortization period for the project is calculated at 2.7 years.

The purpose of this report is to establish the scope of a project to provide a system which will quickly and accurately identify the sources of all reactor scrams.

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Overbore fuel for charging under the proposed Plant Improvement Program is fabricated according to the standard ``F`` process with a few exceptions. Due to the size and weight of individual components and cores, it was necessary to modify the process and change several of the process times to produce a fuel of equal or better quality than standard production. The additions and modifications to the standard lead-dip fuel element manufacturing process are required for production of Model CVIN fuel elements and are discussed in this report.

Abstract: This report presents metallurgical .analyses and corrosion tests conducted to determine :causes of failure of two SM- 1 reactor vessel studs due to fracture in the threaded areas, after 23 months' operation (March 1959). Conclusions of corrosion tests are: (1) failure of the studs was caused by stress corrosion cracking, (2) contributing factors to failure of the studs were improper control of heat treatment of the studs and absence of treatment for stress relief after thread grinding operation.

This report discusses the mathematical and statistical questions concerned with the estimation of a leak rate from data collected during a reactor containment vessel pressure test such as that performed on the PRTR vessel in May, 1959. A mathematical method is suggested in Section 3 for the construction of a total number of gas molecules in the containment vessel time series using vessel absolute pressure and temperature readings at several positions within the vessel. A formula for the precision of the series is given in terms of the individual instrument precisions. The question of accuracy and its relationship to the temperature gradient within the vessel is also considered.