PRELIMINARY ESTIMATION OF ACTIVATED CORROSION PRODUCTS IN THE COOLANT SYSTEM OF FUSION DEMO REACTOR

Title & Authors
PRELIMINARY ESTIMATION OF ACTIVATED CORROSION PRODUCTS IN THE COOLANT SYSTEM OF FUSION DEMO REACTOR
Noh, Si-Wan; Lee, Jai-Ki; Shin, Chang-Ho; Kwon, Tae-Je; Kim, Jong-Kyung; Lee, Young-Seok;

Abstract
The second phase of the national program for fusion energy development in Korea starts from 2012 for design and construction of the fusion DEMO reactor. Radiological assessment for the fusion reactor is one of the key tasks to assure its licensability and the starting point of the assessment is determination of the source terms. As the first effort, the activities of the coolant due to activated corrosion product (ACP) were estimated. Data and experiences from fission reactors were used, in part, in the calculations of the ACP concentrations because of lack of operating experience for fusion reactors. The MCNPX code was used to determine neutron spectra and intensities at the coolant locations and the FISPACT code was used to estimate the ACP activities in the coolant of the fusion DEMO reactor. The calculated specific activities of the most nuclides in the fusion DEMO reactor coolant were 2-15 times lower than those in the PWR coolant, but the specific activities of $\small{^{57}Co}$ and $\small{^{57}Ni}$ were expected to be much higher than in the PWR coolant. The preliminary results of this study can be used to figure out the approximate radiological conditions and to establish a tentative set of radiological design criteria for the systems carrying coolant in the design phase of the fusion DEMO reactor.
Keywords
Activated Corrosion Product;FISPACT;Fusion DEMO Reactor;MCNPX;
Language
English
Cited by
1.
A Study on the Site Plot Plan and Building Schematics of a Fusion DEMO Plant, Fusion Science and Technology, 2013, 64, 3, 473
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