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Dilute chemical decontamination program. Quarterly report 3, April 1-June 30, 1978. Report NEDC-12705-3

Technical Report ·
DOI:https://doi.org/10.2172/6657529· OSTI ID:6657529

The by-products generated by the radiolytic decomposition of oxalic acid, ethylenediaminetetraacetic acid (EDTA), nitrilotriacetic acid (NTA), citric acid, and ascorbic acid were determined by exposing 0.01 M solutions of the metal-ion-free acids to a dose of 4 x 10/sup 7/ rad at 90/sup 0/C with an inert gas atmosphere. The radiolytic decomposition rates of oxalic acid, NTA, and EDTA were investigated. The dissolution rates of unirradiated UO/sub 2/ pellets in 0.01 M solutions of oxalic acid, EDTA, and NTA at 90/sup 0/C were acceptably low. The general corrosion rates of unirradiated production-line Zircaloy-2 fuel cladding in 0.01 M solutions of oxalic acid and EDTA at 90/sup 0/C were acceptably low. The radionuclides absorbed on the regeneration and purification ion-exchange resins during a dilute chemical decontamination of a 5-year-old BWR will not cause significant radiation damage to the resins. At filter loadings below 10% of the filter matrix weight and flow rates below 40 liters/sec/m/sup 2/, the removal efficiency for Fe/sub 2/O/sub 3/ of the SALA-HGMS magnetic filter (Model 10-15-5) with SALA medium-grade Type-430 stainless steel wool was 80%. Preoperational testing of the VNC test loop was successfully completed and all instrumentation was calibrated. General corrosion tests were conducted under static conditions to provide data on the general corrosiveness of the potential reagents. Additional general corrosion tests were conducted to evaluate the effects of several additives and corrosion inhibitors on the corrosion rate of a low alloy steel in 0.01 M NTA.

Research Organization:
General Electric Co., San Jose, CA (USA). Nuclear Power Systems Engineering Dept.
DOE Contract Number:
AC02-76ET34203
OSTI ID:
6657529
Report Number(s):
DOE/ET/34203-T1
Country of Publication:
United States
Language:
English

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