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강 섬유보강 콘크리트의 고속단체에 의한 충돌 및 관통 해석
손석권(S. K. Son),장석준(S. J. Jang),윤현도(H. D. Yun),김용환(Y. H. Kim) 대한기계학회 2014 대한기계학회 춘추학술대회 Vol.2014 No.5
This paper employed finite element method to study the dynamic response of steel fiber reinforced concrete(SFRC) subject to impact loading. The material properties and non-linear stress strain curve of SFRC were obtained by uniaxial compression test and deflection test. The scabbing diameters on the rear surface of SFRC target predicted by proposed method show well agreement with the experimental results This results can be developed for designing the protection of military structures and other facilities against high-velocity projectiles.
STELLA-2 소듐 시험 시설 고온 배관 계통의 설계 및 건전성 평가
손석권(Seok-Kwon Son),이형연(Hyeong-Yeon Lee),주용선(Yong-Sun Ju),어재혁(JaeHyuk Eoh),김종범(Jong-Bum Kim),정지영(Ji-Young Jeong) 대한기계학회 2016 大韓機械學會論文集A Vol.40 No.9
본 연구에서는 한국원자력연구원이 개발 중인 소듐 열유동 종합효과 시험장치(STELLA-2)의 주요 배관 계통을 대상으로 고온 설계를 수행하고, 두 가지 설계기술기준에 따라 배관의 건전성 평가를 수행하였다. 배관 설계기술기준으로는 일반 압력배관에 관한 ASME B31.1과 프랑스의 원자력등급 배관 설계기술기준인 RCC-MRx RD-3600을 적용하였으며, 이들 기술기준의 보수성을 정량적으로 비교 및 분석하였다. STELLA-2 소듐시설에서는 모의 잔열제거계통(Model DHRS), 모의 중간열전달계통(Model IHTS) 및 펌프 모의계통(PSLS)에 배관이 설치되는데, 두 설계기술기준을 따라 이들 배관 계통에 대해 건전성 평가를 수행한 결과 설계 건전성이 확인되었으며, 설계 기술기준 간 비교분석 결과 유지하중에 대해서는 ASME B31.1이, 열하중에 대해서는 RCC-MRx RD-3600이 더 보수적인 것으로 평가되었다. In this study, elevated temperature design and integrity evaluation have been conducted using two different piping design codes for the high-temperature piping systems of sodium integral effect test loop for safety simulation and assessment(STELLA-2) being developed by KAERI(Korea Atomic Energy Research Institute). The design code of ASME B31.1 for power piping and French nuclear grade piping design guideline, RCC-MRx RD-3600 were applied, and conservatism of those codes was quantified based on the piping integrity evaluation results. The piping system of Model DHRS, Model IHTS and PSLS are to be installed in STELLA-2. The integrity evaluation results for the three piping systems according to the two design codes showed that integrity of the piping system was confirmed. As a code comparison result, ASME B31.1 was shown to be more conservative for sustained loads while RD-3600 was more conservative for thermal loads compared to B31.1.
열시효가 Mod.9Cr-1Mo강의 재료강도 및 파괴 거동에 미치는 영향
이형연,김우곤,손석권,홍석우,석창성,Lee, Hyeong-Yeon,Kim, Woo-Gon,Son, Seok-Kwon,Hong, Suk Woo,Seok, Chang Sung 대한기계학회 2016 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.4 No.2
발전소 내열강의 물성치는 고온 가동시간이 누적됨에 따라 열시효의 영향을 받는다. 본 연구에서는 제 4 세대 원자력시스템의 재료로 널리 채택되고 있는 Mod.9Cr-1Mo (ASME Grade 91)강을 대상으로 항복강도, 인장강도 및 파괴거동에 열시효가 미치는 영향에 대해 조사 및 분석하였다. 국내에서 가동 중인 초초임계(USC) 화력발전소의 배관계통에서 채취한, 73,716 시간의 가동 이력을 겪은 Gr.91 강 재료가 재료 실험을 위해 사용되었고, 동 시험결과와 가동 이력을 겪지 않은 신재의 시험결과를 비교 분석하였다. 또한 ASME 코드의 물성치와 RCC-MRx 의 물성치와 비교 분석하였고, 이들 설계기술기준 물성치의 보수성은 신재 및 가동 이력을 겪은 재료의 시험결과와 비교 분석을 통해 정량화하였다. The material properties of heat resistant materials at power plants are affected by thermal aging as operating time is accumulated. In this study, the influence of thermal aging on yield strength, tensile strength and fracture behavior for Mod.9Cr-1Mo (ASME Grade 91) steel which is a material widely adopted for Generation IV nuclear energy system has been investigated and analyzed. Service exposed Gr.91 steel materials sampled from a piping system of an ultra-supercritical (USC) plant in Korea with accumulated operation time of 73,716 hours were used for material testing. The test results of the service exposed material specimens were compared with those of the virgin Gr.91 steel specimens. Those test data were compared with the material properties of ASME code and RCC-MRx code. Conservatisms of the material properties in the design codes have been quantified based on the comparisons of those from virgin and service exposed material specimens.
Design of large-scale sodium thermal-hydraulic integral effect test facility, STELLA-2
이제환,어재혁,윤정,손석권,김형모 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.9
The STELLA program was launched to support the PGSFR development in 2012 and for the 2nd stage, the STELLA-2 facility was designed to investigate the integral effect of safety systems including the comprehensive interaction among PHTS, IHTS and DHRS. In STELLA-2, the long-term transient behavior after accidents can be observed and the overall safety aspect can also be evaluated. In this paper, the basic design concept from engineering basis to specific design is described. The design was aimed to meet similarity criteria and requirements based on various non-dimensional numbers and the result satisfied the key features to explain the reasoning of safety evaluation. The result of this study was used to construct the facility and the experiment is on-going. In general, the final design meets the similarity criteria of the multidimensional physics inside the reactor pool. And also, for the conservation of natural circulation phenomena, the design meets the similarity requirements of geometry and thermo-dynamic behavior
ASME B31.1을 따른 크리프 영역 장기간 가동 고온 배관의 설계 비보수성 기술 현안
이형연(Hyeong-Yeon Lee),손석권(Seok-Kwon Son),정지영(Ji-Young Jeong) 대한기계학회 2019 大韓機械學會論文集A Vol.43 No.7
압력배관의 설계에 ASME B31.1이 널리 사용되고 있지만, 이는 고온 배관에 적용 시 명시적으로 크리프 영향을 고려하지 못하기 때문에 장기간 고온 크리프 환경에 노출되는 배관에 적용될 경우 비보수적 설계를 초래할 우려가 있다. 이에 따라 본 연구에서는 일련의 고온 유지시간에 대한 민감도 분석을 통해 ASME B31.1의 보수성을 분석하였다. 동 분석을 위해 명시적으로 크리프 영향을 고려하는 원자력등급의 고온 배관설계 기술기준인 RCC-MRx를 사용하여 다양한 고온 유지시간에 따른 설계평가를 수행하고, ASME B31.1의 결과와 비교 분석하였다. 분석 결과 RCC-MRx 평가에서는 크리프 영역의 고온에서 유지시간이 점진적으로 증가하면 크리프-피로 파손이 발생하였지만, ASME B31.1에서는 고온 유지시간에 무관하게 건전성을 유지하는 것으로 나타났다. 따라서 장기간 크리프 환경에 노출되는 배관 설계에서는 ASME B31.1이 비보수적 설계를 초래할 수 있는 것으로 나타났다. ASME B31.1 is widely used in the design of power piping, but it does not explicitly consider creep effects. Therefore, there are concerns over non-conservative design for power piping undergoing long-term operation at high temperatures within the creep range. In this study, sensitivity analyses were conducted over a range of hold times at high temperatures to quantify the conservative qualities of ASME B31.1. For the analyses, a high-temperature nuclear esign code of RCC-MRx that explicitly considers creep was applied, and the two evaluation results were compared. Analysis using RCC-MRx showed that creep-fatigue failure occurred as the hold time at high temperature gradually increased, but integrity was maintained regardless of the hold time in the case of evaluations using ASME B31.1. It was therefore shown that ASME B31.1 might cause non-conservative design in the case of pipes subjected to long-term operation within the creep range.
상변화 물질을 적용한 급속 축냉기술에 관한 수치해석 연구
변재기,권영철,박상배,손석권,곽동걸,신종근 한국기계기술학회 2017 한국기계기술학회지 Vol.19 No.6
Recently, uncertainty of demand and supply for energy has expanded as energy market change rapidly. Rapid accumulation storing of cold heat is a method for decreasing the gap between demand and supply of time, quantity and quality of heat energy. It is stored rapidly when electric power is on. And cold heat energy in heat is phase change material (PCM) heat storage is used when electric power is off. Porous media for cold heat is PCM. The present study has been conducted for improving performance of cold heat storage in refrigerator using characteristics on laten heat and phase change of PCM. This study provide basic data to improve performance of cold heat using characteristic of PCM. Also, this study predicts and measures specific points in PCM heat storage during process of phase change.