Preparation of enriched fuel elements and target (N) elements for a full H-Reactor E-N demonstration loading was authorized in April, 1960. The objective of this loading was to demonstrate the feasibility of operating a Hanford reactor economically as a plutonium-tritium producer to increase over-all conversion ratio and diversify product output. Irradiation of the E-N load began in May, 1961 and was completed in January, 1962.

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Appendices C and D may further be identified as SL1925 and CF-61-12- 20(Rev.), respectively. A comparative report is presented in which the economics and feasibility of plant protection from nuclear attack by plant hardening, remote siting, and utilization of optional fueling concepts for the coal-fired plant are evaluated. (J.R.D.)

A series of computer programs are described which Were successfully applied to the reduction of pulse-height data using digital computers. Calculations carried out by these programs include: determination of pulse height vs energy response of an NaI detector; calculation of coincidence sum spectra; and the analysis of complex pulse-height spectra to obtain energies and relative intensities of individual gamma rays or relative abundances from a mixture of radionuclides. Measurement problems and instrumental requirements are discussed in detail. (auth)

Calculations are presented to show the effect of uraniumbearing scale deposits on the HRE-2 core wall tempera ture, heat flux, and the temperature. of patches proposed for sealing the holes of the HRE-2 core vessel. Flow behavior in the HRE-2 core mockup with simulated patches installed and simulated corrosion pits drilled in the vessel wall was determined. A plausible mechanism was advanced to account for hot spots due to sedimentation of solids on metal surfaces projecting from the core wall. Patch designs with reduced metal projections from the core wall are presented. (auth)

Calcium-magnesium precipitation apparatus was used to reduce the concentrations of these elements in ORNL tap water, used as a substitute for waste water of low level of radioactivity, prior to strontium removal by foam separation. With and without alkali and flocculator chambers and with a stirred sludge of ratio height to diameter equal to 1/1 to ~4/1, use of 5 x 10/sup -3/ M each of NaOH and Na/sub 2/CO/sub 3/ and 2 ppm Fe/sup 3+/ reduced the dissolved Ca + Mg concentrations to 1 to 2 ppm as calcium. Simultaneously, a strontium DF of 20 to 200 was achieved, and, by adding Grundite clay in the proportion ~0.5 1b/ 1000 gal, a cesium DF of 10 to 40 was achieved. (auth)

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"The influence of compressive creep on the self-diffusivity of α-iron has been measured in the temperature range of 742-885°C. the diffusivity is enchanced in proportion to the strain rate, but this dependence decreases with increasing temperature. The magnitude of the strain is relatively unimportant in this connection. Strain rates from 0 to -2 x 10¯³ sec¯¹ were investigated with a corresponding increase in diffusivity up to 3 x 10³ times. The results are analyzed in terms of vacancy diffusion and the excess vacancies introduced during deformation. It is concluded that grain boundaries are the main vacancy sinks in polycrystalline iron and that the vacancy lifetime is therefore dependent on the grain size."