Ex-vessel fuel characterization results in the reactor building
Forced circulation during and after the Three Mile Island Unit 2 (TMI-2) accident distribution reactor fuel into the systems and components in the reactor building (RB) and auxiliary and fuel handling building (AFHB). The majority of the distributed fuel remained in the reactor coolant system in the RB, and some fuel traveled to the makeup and purification and waste disposal systems in the AFHB. Efforts began in 1985 and continued through 1987 to determine the location and amounts of ex-vessel fuel. The fuel characterization measurements were performed using three methods: gamma spectroscopy, visual inspection, and sampling. Gamma spectroscopy involves the detection of gamma radiation from tracer isotopes /sup 144/Ce or /sup 154/Eu to calculate the fuel quantity. Gamma spectroscopy was used in closed systems that were not directly accessible. Visual inspection with miniature cameras was used to determine the volume of fuel debris in accessible areas. Sampling was used in conjunction with both methods to either determine or verify the isotopic ratio to be used in the fuel calculations.
- OSTI ID:
- 5619282
- Report Number(s):
- CONF-881011-
- Journal Information:
- Trans. Am. Nucl. Soc.; (United States), Vol. 57; Conference: Joint meeting of the European Nuclear Society and the American Nuclear Society, Washington, DC, USA, 30 Oct - 4 Nov 1988
- Country of Publication:
- United States
- Language:
- English
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