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RISS 인기검색어
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- 저자 : 어재혁(Jae-Huyk Eoh) (검색결과 2 건)
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이형연(Hyeong-Yeon Lee),이재한(Jae-Han Lee),이태호(Tae-Ho Lee),어재혁(Jae-Huyk Eoh),김태준(Tae-Joon Kim),이용범(Yong-Bum Lee) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.4
Overall introduction of the 'STELLA'(Sodium Integral Effect Test Loop for Safety Simulation and Assessment), a large scale sodium test facility for the performance validation tests of heat exchangers and mechanical pump to be used in demonstration fast reactor has been presented. The development of the STELLA facility is composed of two phases. In phase I of the STELLA project, performance validation tests and validation of the computer codes of the three heat exchangers (IHX, DHX, AHX) are to be carried out. In addition, performance tests of mechanical pump are to be conducted. In phase Ⅱ of the STELLA project, performance validation tests on passive decay heat removal circuit (PDRC) characteristics and integral effect tests due to various accident scenarios (e.g. loss of PHTS pump flowrate and loss of steam generator feedwater coolant) are to be carried out. In the phase Ⅱ work, reactor vessel (RV) along with main components within RV and PDRC are to be installed, and the STELLA facility will be at the end used for a safety validation of a demonstration fast reactor. In this paper, high temperature design aspects and design evaluations of sodium test facilities operating at creep regime of around 550℃ has been described.
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이형연(Hyeong-Yeon Lee),김종범(Jong-Bum Kim),어재혁(Jae-Huyk Eoh),이용범(Yong-Bum Lee) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.11
본 논문에서는 소듐냉각 고속로(sodium-cooled fast reactor, SFR)의 열교환기 고온 설계와 관련하여 2028년까지 건설 예정인 실증로, KALIMER-600 그리고 SFR 소듐 열유체 종합 실증시험시설인 STELLA(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) 의 열교환기에 대해 현재의 설계 현황에 대해 기술하고 고온 설계 관련 예비해석을 수행하고, 기술 현안을 정리하였다. 현재 한국원자력연구원이 개발 중인 STELLA 시험장치 내 열교환기(DHX, AHX)의 고온 설계 및 제작과 관련하여 설계 단계에서의 상세한 설계 평가 및 예상되는 설계, 제작 부문의 기술 현안의 도출 및 해결이 요구된다. 고온 열교환기 설계 및 평가와 관련하여 ASME-NH와 프랑스의 RCC-MR RB-3900(열교환기)을 적용한 평가 및 해석 결과의 비교 분석이 향후 수행될 예정이다. The main heat exchangers in the Korean Generation Ⅳ demonstration sodium-cooled fast reactor are IHX(Intermediate heat exchanger), DHX(Decay heat exchanger), SG(Steam Generator) and AHX(Auxiliary heat exchanger). The tube shapes in current design of the IHX and DHX are straight while those of SG and AHX are helical. In KAERI, a large scale sodium test facility of the ‘STELLA’(Sodium Integral Effect Test Loop for Safety Simulation and Assessment) is under construction for the performance validation tests of heat exchangers as well as mechanical pump. In this study, high temperature design aspects of IHX, DHX and AHX are described, and preliminary stress analyses on the IHX and DHX operating at creep regime have been carried out. The materials of the shell and tube in IHX and DHX are Mod.9Cr-1Mo (ASME Grade 91) steel while the materials for tube and shell of AHX are 316SS and 304SS, respectively. Technical issues of creep-fatigue damage evaluation and actual welding for Gr.91 steel are highlighted.
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