INITIAL RADIATION SURVEY. SECTION III. Test Results DL-S-172 (T-612084).

Published: [Place of publication not identified] : [publisher not identified], 1958.
[Oak Ridge, Tennessee] : [U.S. Atomic Energy Commission], 1958.
Physical Description: microopaque : positive ; 8 x 13 cm

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Summary

The radiation level in the concrete reactor plant container compartments during shutdown after the plant has been operating at power was determined. The maximum radiation detected in the 1AC concrete enclosure was in the vicinity of the 1A loop heat exchanger. The 1C loop was out of service and isolated during the power run, therefore, lower radiation would be expected in that vicinity. The lowest radiation detected in the 1BD was found near the 1D loop heat exchanger which is identical to the 1A loop. The highest radiation detected in the 1BD was in the vicinity of the 1B loop hent exchanger. The radiation level on the south side of the 1BD chamber was lower than found along the south side of the 1AC chamber although the 1C loop had not been in service. (auth)

Report Numbers

AECU-3954

Other Subject(s)

Collection

U.S. Atomic Energy Commission depository collection.

Note

NSA number: NSA-13-003412
OSTI Identifier 4309162
Research organization: Duquesne Light Co., Shippingport, Penna.

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