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.

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.)

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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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.

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.

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.

The feasibility of removing and recovering cesium-137 from various HAPO process solutions by precipitation of Cs2ZnFe(CN)6 has been demonstrated previously. Pilot plant studies of calcination and steam hydrolysis of non-radioactive Cs2ZnFe(CN)6 precipitates by members of the Process Equipment Development Operation are currently in progress. In support of these pilot plant studies, experiments were performed to determine the extent, if any, to which cesium volatilizes during calcination and hydrolysis of Cs2ZnFe(CN)6 precipitates containing cesium-137. Experimental procedures and results are presented in this report.