Earticle

초록

영어

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 57Co and 57Ni 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.

목차

ABSTRACT
 1. INTRODUCTION
 2. MATERIALS AND METHODS
 3. RESULTS AND DISCUSSION
 4. CONCLUSION
 REFERENCES

키워드

저자

• SIWAN NOH [ Department of Nuclear Engineering, Hanyang University, ]
• JAI‐KI LEE [ Department of Nuclear Engineering, Hanyang University, ] Corresponding author
• CHANG‐HO SHIN [ ITRS, Hanyang University ]
• TAE JE KWON [ Department of Nuclear Engineering, Hanyang University, ]
• JONG KYUNG KIM [ Department of Nuclear Engineering, Hanyang University, ]
• YOUNG‐SEOK LEE [ National Fusion Research Institute ]

참고문헌

발행기관

간행물

표지보기 관심저널 등록

• 간행물명

  방사선방어학회지 [Journal of Radiation Protection and Research]

• 간기

  계간

• pISSN

  2508-1888

• 수록기간

  1976~2026

• 등재여부

  KCI 등재,SCOPUS

• 십진분류

  KDC 559 DDC 629