Tritium safety issues for TFCX

Author: Reilly, H. J.
Published: United States : [publisher not identified], 1985
Springfield, Va.: National Technical Information Service, [approximately 1985]
Physical Description: microfiche : negative ; 11 x 15 cm
Additional Creators: Merrill, B. J. and Piet, S. J.

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Summary

Estimated tritium releases from the Tokamak Fusion Core Experiment are compared to the expected limits. A reaction kinetics model is described that predicts the conversion of tritium to the oxide form in free space. An analysis of the required capacity of the Emergency Tritium Cleanup System is also presented. The conclusions of this work are expected to be applicable to other experimental fusion devices that are now being considered.

Report Numbers

DE85014621; EGG-M-20684; CONF-850405-14

Other Subject(s)

Collection

NTIS collection.

Note

DOE contract number: AC07-76ID01570
OSTI Identifier 5466517
Research organization: EG and G Idaho, Inc., Idaho Falls (USA).

View MARC record | catkey: 47355812

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Tritium safety issues for TFCX

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