Measurement of TFTR D-T radiation shielding efficiency

Conference · Sat Dec 31 04:00:00 EST 1994

OSTI ID:196861

Kugel, H W; Ascione, G; Elwood, S ^[1]

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1. Princeton Univ., NJ (United States); and others

High power D-T fusion reactor designs presently exhibit complex geometric and material density configurations. Simulations of the radiation shielding required for safe operation and full compliance with all regulatory requirements must include sufficient margin to accommodate uncertainties in material properties and distributions, uncertainties in the final configurations, and uncertainties in approximations employing the homogenization of complex geometries. Measurements of radiation shielding efficiency performed in a realistic D-T tokamak environment can provide empirical guidance for simulating safe, efficient, and cost effective shielding systems for future high power fusion reactors. In this work, the authors present the results of initial measurements of the TFTR radiation shielding efficiency during high power D-T operations with record neutron yields. The TFTR design objective is to limit the total dose-equivalent at the nearest PPPL property lines from all radiation pathways to 10 mrem per calendar year. Compliance with this design objective over a calendar year requires measurements in the presence of typical site backgrounds of about 80 mrem per year.

• OSTI ID: 196861
• Report Number(s): CONF-940664--
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
PULSED D-T REACTORS
RADIATION DOSE DISTRIBUTIONS
SHIELDING
TFTR TOKAMAK