The macroreticular anion exchange resin, Amberlite IRA-900-OH, and an experimental resin from Ionac Chemical Company were irradiated by a /sup 60/Co source to doses of 5 x 10/sup 7/ rad and 10/sup 8/ rad. These doses approximate or exceed the dose encountered by the deionizer resins in 100-Area service. The loss in exchange capacity and the volume changes of Amberlite IRA-900 on irradiation were similar to those found previously for Amberlite IRA-400. The Ionac experimental resin, which had a considerably lower initial exchange capacity, likewise was not stable to radiation. It is concluded that Amberlite IRA-900 offers no advantage over Amberlite IRA-400 for 100-Area purification service. Since there is little justification for further evaluation of macroreticular resin for 100-Area use, the present work completes RTA-893-R.

The results are presented of a parameter survey of the properties and mechanisms affecting the reentry ablation of SNAP fuel particles. The following properties and mechanisms were studied: aerodynamic heating, oxidation, oxide vaporization, metal vaporization, particle emissivity, specific heat, density, velocity, and initial size. These studies were made for particle release altitudes ranging from 170,000 to 228,000 feet.

Significant changes in fuel design, operating levels, loading geometry, and moderator condition have taken place since the Hanford reactors started operation. Changes which affect nuclear safety parameters require continuing analysis of the possible effects on safety system strengths and maximum potential reactivities. For this reason the shutdown of a Hanford reactor offered an excellent opportunity to measure many of the above factors without a significant production loss. Therefore a test program was proposed and carried out at H Reactor starting April 22, 1965 and ending May 5, 1965. All of the tests were designed to provide information concerning parameters which affect nuclear safety and control calculation limits. This document is a summary of the deactivation test results without application and recommendations to specific nuclear safety questions. Rather, it is intended that the results listed herein will serve as a basis for further study and application to nuclear safety technology.

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This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of materials undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, {open_quotes}Status Report Equations.{close_quotes} The integrated exposure reported is the average exposure received by the surrounding uranium columns. Conversion to exposure received by the sample is left to the customer.