As a result of an AEC directive, a review has been made of the disposal of chemicals to the Columbia River by 100-N to determine if any water pollution hazards exist. The search revealed that no chemicals are released continuously in hazardous concentrations; that three cases exist where hazardous concentrations might be released intermittently under worst-case conditions; that two cases exist where intermittent releases result in questionable conditions; and that two cases exist where accidental release from storage might result in hazardous conditions. Recommendations for corrective action are given in all cases.

An extensive knowledge of the effect on the mechanical properties of metals of prolonged exposure to neutron radiation is considered necessary to properly establish design and operating criteria for in-reactor pressure tubes and test loops. An opportunity to obtain a limited amount of this information on Zircaloy-2 presented itself when, after two years of service, the pressure tubes were replaced in the RE reactor recirculating test facility. Three Zircaloy-2 tubes, with a two-inch inside diameter and 48 feet long, had operated intermittently with prototypical fuel elements at water temperatures up to 250 C (480 F) and pressures up to 1350 psi. During this period, the tubes received an estimated integrated neutron exposure of 1.9 {times} 10{sup 22} nvt. After the tubes were removed from the reactor, metallographic examinations, longitudinal-tensile tests, flattening tests, and burst tests were performed. In this report, the techniques for performing the burst tests are described and the results of the burst tests are compared with the results from tensile tests on coupons cut from corresponding locations along the tube.

Instrumentation studies and the Hazards Review have demonstrated the need for instrumentation which will scram the reactors if the exponential rate of power increase is excessive. A development program has demonstrated the feasibility of such a system. This document defines the program necessary to provide Intermediate Range exponential rate protection in the safety circuits of five reactors, provides justification for the project, and presents estimates of the cost and schedule required to accomplish the program. Three channels of IRATE (Intermediate Range Automatic Trip Equipment) should be installed in the two K and three small reactors., and incorporated into the Number 1 Safety Circuits. Each channel should sense the output of its own gamma-compensated ion chamber located in the thermal shield of the reactor. A two-out-of-three channel coincident trip circuit should be used in the safety circuit. GE should manage the program and develop the specifications for the engineered equipment. Procurement should be by competitive bids to GE`s specifications and drawings. The proposed program is estimated to cost $520,000.

The study of focusing aid techniques was conducted to evaluate the performance and convenience of the split image, projection, and ground glass techniques used for focusing oscilloscope cameras. Specifically, the study was intended (1) to determine the usefulness of projection-type focusing aid devices now used on EG&G Type 3171 cameras, (2) to lead to recommendations for the most satisfactory device for use with the new LC-4 type camera, and (3) to evaluate the usefulness of such devices for production-line focusing of EG&G Type 850 cameras. The study included a brief theoretical evaluation of each focusing method and a statistical determination of actual performance. The primary tests were made using a simulated oscilloscope trace to insure reproducibility. Comparisons of the results were made on a Tektronix oscilloscope to confirm validity of the trace simulation. Most of the tests were made with an LC-4 camera because the Nikon lens used in the LC-4 camera will be used in future 3171 cameras. A few experiments were conducted to confirm the correctness of applying the LC-4 camera results to unmodified 3171 cameras. A special split image focusing aid developed at Lawrence Radiation Laboratory (LRL) for the LC-4 camera was used in the split image …

From Scope of Investigation: "The work reported here is part of a continuing program concerning the long-term volume changes in concretes made from lightweight and normal-weight aggregates. The creep, drying-shrinkage, and strength data presented are for concretes made with 24 expanded shale lightweight aggregates and 5 natural, normal-weight aggregates. These aggregates were from widely separated geographical locations and were to be representative samples of aggregates being used in the production of structural concretes."

From Introduction: "The object of this research was to identify and study some of the factors involved in premature failures and to relate the pertinent factors to roof performance."

This technical report describes development work done on zonal centrifuge systems at the Oak Ridge National Laboratory and the Oak Ridge Gaseous Diffusion Plant during the period July 1 to December 31, 1962 under the Joint National Institute for Health-Atomic Energy Commission Zonal Centrifuge Development Program. A basic purpose of this project is to develop new methods for isolating virus particles associated with cancerous cells and tissues. Three classes of rotor systems capable of separating particles ranging in size from whole animal or plant cells to protein or nucleic acid molecules on the basis of either sedimentation rate or density alone have been developed. Experiments with phage particles indicate the feasibility of large-scale virus isolation by continuous-flow centrifugation, followed by isopycnic banding in cesium chloride and velocity sedimentation in sucrose - all steps being carried out sequentially in the same rotor. Zonal rotors using the reorienting gradient principle for molecular separations have been tested to 141,000 rpm (formula). Previous work on zonal centrifugation and future plans for this program are discussed.

Corporate income tax return of 1960 for the United States National Company. The return includes all necessary schedules.

The multi-purpose dissolver was designed to provide: 1. A critically safe vessel for dissolving uranium metal of enrichments up to one percent U-235. 2. A vessel which can be charged with fuel elements up to 10 feet long. 3. An off-gas arrangement which will eliminate return of ammonia to the dissolver during the Zirflex decladding process. 4. A vessel in which small charges can be dissolved without using extra chemicals. 5. A by-pass routing around the silver reactor during cladding removal.