The information contained in this report was copied from carts used for discussions at Richland on May 4--6, 1965. Representatives of the Martin Company, US Rubber company, General Electric -- HAPO, and AEC-RL00 were present. The data represent the best current information on the quantity, quality, and availability of each fission product considered, i.e., strontium-90, cesium-137, promethium-147, and cerium-144.

This monthly report details activities of the N-Reactor Research and Engineering Department during the month of March 1965.

The purpose of this study was to examine the general area of criticality prediction errors at the smaller (``pre-K``) reactors. Such errors evolve from a number of uncertainties which are difficult if not impossible to eliminate with present measuring and accounting techniques; the magnitude of these uncertainties in aggregate was indicated in an earlier study about 1.5 milli-k, which, at the time of the study, represented an ``inherent`` prediction error that constituted a practical limit on accuracy. Present day computer usage has improved considerably upon this. Predictions at the various Hanford reactors are made on the basis of a fundamental pile variable known as cold clean reactivity. This variable may be qualitatively defined as the ultimate reactivity of the room temperature reactor with all poisons and poisonous short-term fission products removed. The quantity CCR may be determined during operation by properly evaluating the temperature-reactivity coefficients C{sub m} and C{sub g}, or it may alternatively be determined at startup, when these effects are zero and the equation reduces to CE = R + {rho}{tau} + L + P4. The latter equation serves as the basis for the uniform calculational approach used herein.

This report details activities of the N-Reactor Research and Engineering Operation Department for the month of May 1965.

A status report is given for the N Reactor. Brief summaries are included for the following technical activities: Co-product physics studies; Target melting calculations; Critical mass parameters; Stack flooding calculations; Co-product metal handling; Co-producer demonstration test; Thermal hydraulics; Primary cooling system supply characteristics; Fringe tube orificing; Fuel tube power split; Simulated driver-target test; Fuel element failure evaluation; 1.96% Integral-target production test; Conversion ratio tests; Fuel examination facility; Process tube monitoring; Corrosion monitoring; I-131 concentrations in river influent following ruptures; and Production of Np-237 and Pu-238 in the N Reactor.

The Special Metallurgical Building at Mound Laboratory, a building of 18,515 sq ft of floor space, was decommissioned. This decommissioned facility formerly housed 238PU processes for the fabrication of radioisotopic fueled heat sources. The 238PU work was conducted in 585 linear ft of gloveboxes occupying approximately 12,600 sq ft of the building. All of the gloveboxes, process services, building services, interior walls, and ceilings were removed to the point of exit at the roof. Eighty-five percent of the filter banks occupying 700 sq ft of floor space was also removed. Special procedures and special equipment were used to reduce the amount of 238PU in the building from approximately 100,000 Ci at the start of the effort to less than 0.3 Ci without a significant release to the environment.

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Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design, (DCC)

This document records the chart materials and talk outlines used in presentations at the Advisory Committee on Reactor Safeguards meeting of September 10, 1965, on the Irradiation Processing Department, General Electric Company, operated production reactors. The general objectives of the meeting were to review administration of safety during contractor transition, the status of N-Reactor operation and conversion project progress, and progress on the confinement studies for the production reactors. Review of the proposal to raise the K-Reactor power level limit was the specific objective of the meeting. K and N Reactor Presentation Agenda is included. The list of meeting attendees and information used for the K-Reactor tour are included in the appendix.

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