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Title: Testing of a prototype PWR design gamma thermometer for use as a local power monitor in the thimble tube of a nuclear reactor

Conference · · IEEE Trans. Nucl. Sci.; (United States)
OSTI ID:7122621

Out-of-pile tests were performed on a 0.185-in. OD gamma thermometer (GT) designed for insertion in existing thimble tubes of W pressurized water reactors (PWR). The experimental measurements were conducted with the GT inserted in a simulated thimble tube. The measurements were performed to examine the effect on the sensitivity, response time, and repeatability of the GT output signal when surrounded by an air- and a water-filled thimble tube with random and controlled physical contact between the two units. The results showed that the linearity of the instrument is not affected when operated in an airor water-filled thimble tube. However, the response time of the GT to a step change in power increased from 9 s to about 30 s for water and dry thimble tube conditions respectively. Results are also presented which show that the sensitivity, mV/W/cm/sup 3/, of the GT with and without controlled physical contact between the inner surface of the simulated thimble tube and the outer surface of the GT did not vary significantly.

Research Organization:
Technology for Energy Corporation One Energy Center, Pellissippi Parkway Knoxville, Tennessee 37922
OSTI ID:
7122621
Report Number(s):
CONF-831015-; TRN: 84-011331
Journal Information:
IEEE Trans. Nucl. Sci.; (United States), Vol. 31:1; Conference: Nuclear science symposium, San Francisco, CA, USA, 19 Oct 1983
Country of Publication:
United States
Language:
English