This memorandum was written to provide additional technical basis for preparing Process Standards. Fuel surface-tube outlet temperature data is also provided. These data will help establish dichromate concentration and coolant pH based on the outlet coolant temperatures of the hottest reactor process tubes.

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In FY-1970, the former ten missions which had existed under the Richland Five-Year 02 Research and Development Program were consolidated into four program areas as follows: Basic Production; Product Flexibility; Environmental and Regulatory Technology; and Waste Management. Each program area has included one or more separate distinct programs, some of which were basic to sustaining and improving production operations while others were directed to broadening plant versatility for producing potentially marketable products. Midway through FY-1970, the shutdown of KW Reactor with subsequent curtailment of funding resulted in a substantial reduction in the level of effort in both of these directions. Consequently, during the balance of FY-1970 improvement effort has primarily been concentrated on N Reactor operation, and plant versatility effort was virtually stopped. The research and development reported herein represents progress made during the period January 1, 1970, through May 30, 1970, and, contrary to recent annual and semiannual reports, includes only that work primarily funded with 02 R&D funds. No process technology funded activities are included, these being reported regularly in Douglas United Nuclear Monthly Reports.

This report addresses the determination of excess reactivity and control worth for the core test reactor.

Rear face dose rates at the single pass reactors were found to have significantly increased between 1965 and 1967. It was suggested by Battelle-Northwest that an increase in scandium-46 activity may have been a possible cause of the increased dose rates. Battelle-Northwest records showed that considerably more {sup 46}Sc was present in the Columbia River at Richland starting in the summer of 1967 than had been found previously. The ratio of {sup 46}Sc to {sup 65}Zn activity, a correlation which removes seasonal variations in activity, was shown to have increased from 0.1 early in 1967 to l.0 by November of 1967. It was concluded that indeed the {sup 46}Sc release rate from the single pass reactors and the rear face dose es had increased in 1966 and 1967, but not necessarily at the same time {sup 3}. Data presented in the review showed that there had been no changes in parent {sup 45}Sc concentration in the Columbia River between 1962 and 1969, but there had been several changes in water chemistry in 1966 and 1967 which may have contributed to the increased {sup 46}Sc concentration in the reactor effluent. The review document suggested that rear face components be analyzed to …