Document Details

Hazards Evaluation for Building 3019: I. Solvent Extraction, II. Fluoride Volatility - Vol. 5
Subject Terms:
Building 3019, fission product; evaluation, solvent extraction; fluoride volatility; hazards, radiochemical; hydrofluorinator; nuclear safety, ORNL; plutonium, cell; waste disposal, radioactive
Document Location:
DOE INFORMATION CENTER 1 Way, Oak Ridge, TN 37831; Eva Butler; Phone: 865-241-4780; Toll-Free: 800-382-6938, Option 6; FAX: 865-574-3521; Email:
Document Categories:
Health, Safety and Environment\Worker Health and Safety
Document Type:
Publication Date:
1962 Aug 21
Declassification Status:
Never classified
Document Pages:
Accession Number:
Document Number(s):
ORNL-TM-316, Copy 77
Originating Research Org.:
Atomic Energy Commission
OpenNet Entry Date:
1998 Jun 16
This document concerns the evaluation of the hazards associated with radiochemical processing operations planned for Building 3019. Maximum plant inventories for fissionable materials and fission products and maximum magnitudes for the various types of credible accidents that might disperse radioactivity to the environment as air-borne aerosols have been established. Calculations indicated that the maximum credible accident would be a nuclear incident in the plutonium product storage vessel in the solvent extraction section. Containment modifications proposed for the building ventilation, cell exhaust and vessel off-gas systems will provide adequate containment for such a postulated maximum accident. In the fluoride volatility section a criticality incident in the hydrofluorinator during a water flush after a series of runs is considered the maximum credible accident, but the probability of occurrence is very low and the dose to personnel outside the cell would be only 1.4r. Standards of construction and containment, assumptions made to evaluate the potential hazards of release of radioactive material, and methods of calculation used for development of this hazards analysis are given in ORNL-2956, Summary Report - Hazards Analyses of Radiochemical Processing and Waste Disposal at Oak Ridge National Laboratory, Sects. 4.0, 5.0 and 6.0. Tables and figures are included.

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