Published 1985 | Version v1
Book

Fuel debris assessment for Three Mile Island unit 2 (TMI-2) reactor recovery by gamma-ray and neutron dosimetry

  • 1. Westinghouse Hanford Co., Richland, WA

Description

Neutron and gamma-ray dosimetry are being used for non-destructive assessment of the fuel distribution throughout the Three Mile Island - 2 (TMI-2) reactor core region and primary cooling system. To date, the fuel content of TMI-2 makeup and purification demineralizer A has been quantified with Si(Li) continuous gamma-ray spectrometry and solid state track recorder (SSTR) neutron dosimetry. To overcome an intense gamma-ray field (approx. =2000 R/hr), a shielded Si(Li) Compton recoil gamma-ray spectrometer was used to measure gamma-ray spectra at different locations in the demineralizer A cubicle. Adequate signal was obtained from a 29 day exposure of 235U-mica SSTR neutron dosimeters in the demineralizer A cubicle. Results obtained from these gamma-ray and neutron dosimetry data were 1.3 +- 0.6 kg and 1.7 +- 0.6 kg, respectively, for the fuel content of TMI-2 demineralizer A

Additional details

Publishing Information

Publisher
American Society of Metals.
Imprint Place
Metals Park, OH (USA)
Imprint Title
NDE in the nuclear industry
Journal Page Range
p. 129-133.

Conference

Title
6. international conference on nondestructive evaluation in the nuclear industry.
Dates
27 Nov - 2 Dec 1983.
Place
Zurich (Switzerland).