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Calibration of SSTR neutron dosimetry for TMI-2 applications

Conference ·
OSTI ID:6547521

Application of neutron dosimetry for assessment of fuel distribution throughout the Three Mile Island-2 (TMI-2) reactor-core region and the primary-coolant system is advanced. Neutron dosimetry in the reactor cavity, i.e. the cavity between the pressure vessel and the biological shield, could provide data for the assessment of the core fuel distribution. A more immediate task entails locating and quantifying the amount of fuel debris in the ex-core primary coolant system; in the range of 1 to 1000 kg. Solid-state track-recorder (SSTR) neutron dosimetry is considered for such exploratory scoping experiments at TMI-2. The sensitivity of mica-/sup 235/U (asymptotically thick) SSTR has been ascertained for such environments. It has been demonstrated that the SSTR method has adequate sensitivity to properly respond and detect fuel quantities of the order of 1 kg in the ex-core primary coolant system. 21 figures.

Research Organization:
Hanford Engineering Development Lab., Richland, WA (USA)
DOE Contract Number:
AC06-76FF02170
OSTI ID:
6547521
Report Number(s):
HEDL-SA-2790; CONF-820762-1; ON: DE83004073
Country of Publication:
United States
Language:
English