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소듐냉각고속로 원형로 중간열전달계통 고온배관의 파단전누설 예비평가
이사용,김낙현,구경회,김성균,김윤재,Lee, Sa Yong,Kim, Nak Hyun,Koo, Gyeong Hoi,Kim, Sung Kyun,Kim, Yoon Jea 한국압력기기공학회 2016 한국압력기기공학회 논문집 Vol.12 No.1
Recently, the research and development of Sodium-cooled Fast Reactors (SFRs) have made progresses. However, liquid sodium, the coolant of an SFR, is chemically unstable and sodium fire can be occurred when liquid sodium leaks from sodium pipe. To reduce the damage by the sodium fire, many fire walls and fire extinguishers are needed for SFRs. LBB concept in SFR might reduce the scale of sodium fire and decrease or eliminate fire walls and fire extinguishers. Therefore, LBB concept can contribute to improve economic efficiency and to strengthen defense-in depth safety. The LBB assessment procedure has been well established, and has been used significantly in light water reactors (LWRs). However, an LBB assessment of an SFR is more complicated because SFRs are operated in elevated temperature regions. In such a region, because creep damage may occur in a material, thereby growing defects, an LBB assessment of an SFR should consider elevated temperature effects. The procedure and method for this purpose are provided in RCC-MRx A16, which is a French code. In this study, LBB assessment was performed for PGSFR IHTS hot-leg pipe according to RCC-MRx A16 and the applicability of the code was discussed.
탄소강 배관 재료의 DSA 거동에 미치는 노치 영향 평가
이사용(Sa Yong Lee),김진원(Jin Weon Kim),김홍덕(Hong Deok Kim) 대한기계학회 2012 大韓機械學會論文集A Vol.36 No.3
본 연구에서는 탄소강 배관 재료의 동적변형시효 거동에 미치는 노치에 의한 응력과 변형 집중효과를 파악하기 위해서, 표준 시편과 노치 시편을 이용하여 다양한 온도와 시험 속도에서 인장시험을 수행하였다. 또한, 시편의 형상에 따른 응력과 변형률 상태의 차이를 파악하기 위해서, 각 시편에 대한 유한요소 시뮬레이션을 수행하였다. 노치 시편을 이용한 인장시험 결과에서도 표준 시편에서 관찰된 것과 같은 동적변형시효의 증거인 serration과 인장강도의 증가 현상이 관찰되었다. 동일한 시험 속도에서 인장시험이 수행된 경우에 표준 시편에 비해 노치 시편에서 동적변형시효 현상이 고온에서 나타났다. 유한요소 해석 결과에 의하면 표준 시편에 비해 노치 시편에서 동적변형시효가 고온에서 나타나는 것은 노치부에서 응력과 변형의 집중으로 인한 높은 변형률 속도에 기인하는 것으로 확인되었다. In this study, tensile tests were performed using standard and notched-bar specimens under two different displacement rates and various temperatures, in order to investigate the effects of the stress and strain concentration at the notched section on the dynamic strain aging (DSA) behavior of carbon steel piping material. In addition, finite element simulations were conducted to evaluate quantitatively the stress and strain states for both types of specimen under uniaxial tensile loading. The results showed that serration and an increase in tensile strength, which are considered to be evidence of DSA in carbon steels, can be observed from tensile tests for notched-bar specimens. It was also found that the temperature region of DSA observed in the notched-bar specimens was higher than the DSA region observed in the standard tensile specimens tested under the same displacement rate. The results of finite element analysis showed that this behavior is associated with the high strain rate at the notched section, which is caused by the stress and strain concentration.
소듐냉각고속로 잔열제거계통 강제대류 소듐-공기 열교환기의 구조개념 설계
김낙현,이사용,김성균,Kim, Nak Hyun,Lee, Sa Yong,Kim, Sung Kyun 한국압력기기공학회 2016 한국압력기기공학회 논문집 Vol.12 No.1
The FHX (Forced-draft sodium-to-air Heat Exchanger) employed in the ADHRS (active decay heat removal system) is a shell-and-tube type counter-current flow heat exchanger with M-shape finned-tube arrangement. Liquid sodium flows inside the heat transfer tubes and atmospheric air flows over the finned tubes. The unit is placed in the upper region of the reactor building and has function of dumping the system heat load into the final heat sink, i.e., the atmosphere. Heat is transmitted from the primary cold sodium pool into the ADHRS sodium loop via DHX (decay heat exchanger), and a direct heat exchange occurs between the tube-side sodium and the shell-side air through the FHX tube wall. This paper describes the DHRS and the structural design of the FHX.