From introduction: The technology of isotopic power generation, though recent, is a logical extension of the search for power from the atom. Controlled fission of uranium utilizes only a fraction of the total energy made available from this nuclear process.

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An unclassified design criteria for Fission Waste Container Storage Facilities is presented in HW-81771 PT1. The purpose of this document is to present information not given in HW-81771 PT1. This information deals with fission waste container production rates and fission waste inventories.

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Report containing a description of the Oak Ridge National Laboratory's High-Flux Isotope Reactor (HFIR) and its operation.

A thermal and nuclear NRX-A5 Design Review was held at WANL on April 10, 1964. Analyses and planning performed to date on the NRX-A5 and subsequent reactors were presented. Systems analyses were performed on various "cooled periphery".and "hot periphery" seal configurations. A number of inner reflector designs were examined, as well as means for cooling the lateral support springs. Core component redesign incl,uded methods for controlling inter-element pressure distribution by undercutting or chamfering of fuel elements. Changes in tie rod diameters, use of as-extruded fuel elements, and performance analysis of the various systems were also described. Nuclear analysis was confined to parametric studies on excess reactivity and control drum span for inner reflector material combinations of graphite, aluminum, and/or beryllium. Changes required to more precisely define the NRX-A5 were discussed together with the effects associated with the twice power reactor capability envisioned for subsequent reactors.

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From Introduction: "The major difficulty in interpreting the results obtained by this simple experimental technique is the specification of the temperature at the crystal-liquid interface. Since, the liquid-to-solid transformation is exothermic the temperature in the vicinity of the interface will exceed the temperature in the vicinity of the interface will exceed the temperature of the bulk of the cooling bath, which is the quantity most conveniently measured and most frequently reported."

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The capability of calculating the close-in effects of the shock wave from an underground nuclear explosion has been demonstrated. Agreement was obtained between calculation and measurements using .a spherically symmetric, hydrodynamic, elastic-plastic code called SOC for the Hardhat event, a 5-kiloton nuclear detonation in granite. This capability is dependent upon having a more or less complete de scription of the elastic and dynamic properties of the materials involved. When this information is available, agreement within the limits of uncertainty of the measurements can be calculated for peak pressures, peak particle velocities, shock wave time of arrival, and pressure pulse shapes.

This report addresses the cryogenic mock-up loop design study.

Abstract: The structural design criteria and the system basic loads for the SNAP 2 compact power unit are presented.

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From introduction: "This report presents lithologic and geophysical logs and construction data for NRTS research observation wells."

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Surface contamination with beryllium becomes a hazard to health only when the potential exists for resuspension in air in enough quantity and for enough time to exceed the prescribed standards for airborne exposures. There are several factors governing the rate and nature of resuspension phenomena. These factors include: the quantity and properties of the particular beryllium compound causing the contamination, the nature of the surface, activities in the vicinity, ventilation in the area which might affect the dilution of resuspended particles, and the presence of other control measures such as respiratory protection and use of wet methods. Generally, it has been found that the problem is minimal and can be easily controlled by exercising good judgement based upon consideration of pertinent factors governing resuspension, and a knowledge of the nature of beryllium toxicity.

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