HAZARDS SUMMARY REPORT FOR THE ARMY PACKAGE POWER REACTOR SM-1, TASK XVII
The SM-1 is described and the various hazards are reviewed. Because of the reactor's location near the nation's capital, containment is of the utmost importance. The maximum energy releace in any possible accident is 7.4 million Btu which is completely contained within a 7/8-in.-thick steel cylindrical shell with hemispherical ends. The vapor container is 60 ft high and 32 ft in diameter and is lined on the iside with 2 ft of reinforced concrete which provides missile protection and is part of the secondary shield. All possible nuclear excursions are reviewed. The energy from any of these is insignificant compared to the stored energy in the water. The maximum credible accident is caused by the reactor running constantly at its maximum power of 10 Mw and through an extremely uniikely sequence of failures, csusing the temperature of the water in the primary and secondary systems to rise to saturation, whereupon a ruptare occurs releasing the stored energy of 7.4 million Btu into the vapor container. If the reactor core melts during the accident, a maximum of 1.5 x lO/sup 7/ c of activity is released into the vapor container. While it is highly improbable for a ruptare of the vapor container to occur except by sabotage or bombing, the hazards to the surrounding area are discussed in the event of such a rupture occurring simultaneously with the maximum credible accident. The SM-1 has been in operation for about 3 years, during which time much operating experience was accumulated and nuclear and system data were obtained through both normal operations and the research and development programs conducted. These data are discussed in relation to their effect on the hazards evaluction of the SM-1 and include core nuclear data, primary and secondary system thermal data, radiological safety, dose rates at various positions in the primary system both during operation and after shutdown and their effects on maintenance, experience with radioactive-waste disposal, area monitoring, experience with the use of trainees in plant operation, and plant modifications accomplished during this period. During 3 years of operation, SM-1 has proved to be an extremely stable and safe system. No incidents occurred during this time that resulted in any significant injuries, radiation exposures or environmental contamination. A plan is included for continued operation of the SM-1 facility after July 1, 1960, when SM-1 will become the responsibility of the U. S. Army Corps of Engineers. (auth)
- Research Organization:
- Alco Products, Inc., Schenectady, NY (United States)
- DOE Contract Number:
- AT(30-3)-326
- NSA Number:
- NSA-15-003644
- OSTI ID:
- 4142038
- Report Number(s):
- APAE-2(Rev.1)
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-61
- Country of Publication:
- United States
- Language:
- English
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