Proposal of an Improved Concept Design for the Deep Geological Disposal System of Spent Nuclear Fuel in Korea

• 발행기관: 한국방사성폐기물학회
• 저자명: Jongyoul Lee Inyoung Kim HeeJae Ju Heuijoo Choi Dongkeun Cho
• 간행물 정보: 『Journal of Nuclear Fuel Cycle and Waste Technology (JNFCWT)』Vol.18 No.Special, 1~19쪽, 전체 19쪽
• 주제분류: 공학 > 공학일반
• 파일형태: PDF
• 발행일자: 2020.11.30

국문 초록

Based on the current high-level radioactive waste management basic plan and the analysis results of spent nuclear fuel characteristics, such as dimensions and decay heat, an improved geological disposal concept for spent nuclear fuel from domestic nuclear power plants was proposed in this study. To this end, disposal container concepts for spent nuclear fuel from two types of reactors, pressurized water reactor (PWR) and Canada deuterium uranium (CANDU), considering the dimensions and interim storage method, were derived. In addition, considering the cooling time of the spent nuclear fuel at the time of disposal, according to the current basic plan-based scenarios, the amount of decay heat capacity for a disposal container was determined. Furthermore, improved disposal concepts for each disposal container were proposed, and analyses were conducted to determine whether the design requirements for the temperature limit were satisfied. Then, the disposal efficiencies of these disposal concepts were compared with those of the existing disposal concepts. The results indicated that the disposal area was reduced by approximately 20%, and the disposal density was increased by more than 20%.

키워드

Spent nuclear fuel Disposal container Deep geological disposal system Disposal scenario Disposal efficiency