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

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자료유형: 학술저널

저자정보: Noh, Si-Wan (Department of Nuclear Engineering, Hanyang University) Lee, Jai-Ki (Department of Nuclear Engineering, Hanyang University) Shin, Chang-Ho (ITRS, Hanyang University) Kwon, Tae-Je (Department of Nuclear Engineering, Hanyang University) Kim, Jong-Kyung (Department of Nuclear Engineering, Hanyang University) Lee, Young-Seok (National Fusion Research Institute)

저널정보: 대한방사선방어학회 방사선방어학회지 방사선방어학회지 제37권 제2호

발행연도: 2012.1

수록면: 63 - 69 (7page)

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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 $^{57}Co$ and $^{57}Ni$ 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.

#Activated Corrosion Product #FISPACT #Fusion DEMO Reactor #MCNPX

참고문헌 (11)

참고문헌 신청

Kim HJ / 2011 / Strategic plans for the fusion DEMO program of Korea / Fusion Sci. Technol 60(2):433~440

Pelowitz DB / 2008 / MCNPX 2.6.0 user’s manual. LA‐CP‐07‐1473

Forrest RA / 2007 / FISPACT‐2007: User manual. UKAEA FUS 534

Hazelton RF / 1987 / Characteristics of fuel CRUD and its impact on storage, handling, and shipment of spent fuel

Korea Hydro / 2000 / Final safety analysis report for Younggwang Unit 5 & 6