Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Rapid measurement of the gaseous {sup 41}Ar released from a nuclear reactor

Journal Article · · Transactions of the American Nuclear Society
OSTI ID:436805
;  [1];  [2]
  1. National Tsing Hua Univ., Hsinchu (Taiwan, Province of China)
  2. Taiwan Power Company, Taipei (Taiwan, Province of China)
A method of monitoring in situ the dose rate contributed from the gaseous radionuclide {sup 41}Ar was developed using a portable gamma-ray spectrometer. The instrument was immersed in a sealed chamber filled with {sup 41}Ar to determine the calibration factor for the dose rate converted from the photopeak count rate. The calibrated spectrometer was applied in situ to measure the noble gas {sup 41}Ar dose rate both inside and outside the containment of a research reactor operating at full power. The continuously monitored dose rate from {sup 41}Ar was contour-mapped around the nuclear reactor facility, and the nonuniform distribution of {sup 41}Ar was correlated with the prevailing diffusion as well as dispersion conditions.
OSTI ID:
436805
Report Number(s):
CONF-9606116--
Journal Information:
Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 74; ISSN TANSAO; ISSN 0003-018X
Country of Publication:
United States
Language:
English