Document Details


Title:
Hazards Analysis of Fuel Handling Facilities
Author(s):
Arnold, E D [ORNL, Union Carbide Corporation, AEC, Oak Ridge, TN]; Nichols, J P [ORNL, Union Carbide Corporation, AEC, Oak Ridge, TN]
Subject Terms:
accidents, X-10 Reactor; contamination, radioactive; fuel handling facilities; hazards analysis, ORNL; radiochemical, evaluation; releases, exposure
Document Location:
DOE INFORMATION CENTER 1 Science.gov Way, Oak Ridge, TN 37831; Eva Butler; Phone: 865-241-4780; Toll-Free: 800-382-6938, Option 6; FAX: 865-574-3521; Email: doeic@oro.doe.gov
Document Categories:
Health, Safety and Environment\Worker Health and Safety
Document Type:
REPORT
Declassification Date:
1958 Nov 05
Declassification Status:
Declassified
Document Pages:
23
Accession Number:
ORF65750
Document Number(s):
ORNL-TM-346, Copy 96; CF-50-9-137; CF509137
Originating Research Org.:
Atomic Energy Commission
OpenNet Entry Date:
1998 Jun 16
Description/Abstract:
This document dated August 24, 1962, concerns a hazards analysis of fuel handling facilities. Accidental releases of radioactive material at the Oak Ridge National Laboratory during the Fall of 1959 resulted in the establishment of building and ventilation design criteria and the requirement for a hazards evaluation for those facilities which contain or handle radioactive materials of physiological hazard greater than that equivalent to one gram of Pu-239. A quantitative method for estimating the hazards associated with the maximum credible accident in a radiochemical facility has been developed. The maximum credible accidents in such facilities are chemical or nuclear explosions which disperse radioactive aerosol and gases into ventilation streams which exhaust to the atmosphere. Approximate physical properties of these aerosols and gases have been combined with the efficiency of ventilation cleanup devices and meteorological correlations to evaluate the hazard to the environment. Methods of hazards evaluation have been applied to ORNL radiochemical facilities to establish necessary containment and ventilation criteria, to determine the more probable and important mechanisms of activity releases, and to demonstrate that acceptably low personnel exposure and ground contamination would result from a maximum credible accident in each facility after modification to meet the new containment criteria. Included is a document dated September 25, 1950, concerning hazards and accidents associated with the operation of the X-10 Reactor. Tables and figures are also included.


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