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U.S. Department of Energy
Office of Scientific and Technical Information

TFTR nuclear radiation analyses

Technical Report ·
OSTI ID:5345798

This report presents results from studies of the radiation environment expected in and around the Tokamak Fusion Test Reactor (TFTR) Facility. The TFTR is scheduled for operation by 1981 and will be located on the Princeton Forrestal Campus. The conceptual design and planned operation of the TFTR device and facility have been significantly affected by the anticipated production of neutrons and gamma rays during the pulsing of the device with deuterium or deuterium-tritium fuel. It is expected that reactor grade plasmas having fusion power densities >1 W/cm/sup 3/ will be generated, and that many of the associated engineering problems which are typical of those to be encountered in future power producing fusion reactors will be addressed. On the other hand, in view of the experimental nature of the device, the number of deuterium-tritium pulses will be limited so that stifling radiation effects will not be encountered. The radiation analyses used for the TFTR conceptual design are described in this report. Presentations are given of the: (1) analytical methods and their application to the design of the radiation shielding, (2) composition, dimensions, and arrangement of the device shielding and of the walls of the facility, (3) modes of operation and the associated radiation environments, (4) neutron activations of the device auxiliary components, cooling water, and Test Cell air as a function of irradiation history and time after shutdown, (5) radiation levels throughout the facility and site out to the site boundary.

Research Organization:
Westinghouse Electric Corp., Pittsburgh, Pa. (USA). Fusion Power Systems Dept.
DOE Contract Number:
EY-76-C-02-3073
OSTI ID:
5345798
Report Number(s):
WFPS-TME-022
Country of Publication:
United States
Language:
English