중대사고연구현황및향후계획 2015. 7. 17 송진호 한국원자력연구원 원자력안전해석심포지엄, 2015. 7.16-17, 대천한화리조트파로스 1
중대사고연구개발경과 MIDAS ISAAC TROI 중대사고연구기반구축 1997-2002 중대사고실증실험및평가기술개발 (~24 억 / 년 ) SONATA 용융물실험장치 국내원전중대사고관리전략 구체적인연구성과 2003-2007 중대사고관리최적방안수립및중대사고대처설비개발 (~28 억 / 년 ) MIDAS/ISAAC 경수로및중수로중대사고해석코드개발 TROI ( 실제핵연료물질이용증기폭발실험 ) 수소연소소염망개발 미 일중심, 중대사고연구약화국내연구소강상태 2007-2011 대과제없어짐 - 격납건물수소및핵분열생성물거동평가기 술개발 (~5 억 / 년 ) - 노심용융물위해도실증실험및쟁점해결기술개발 (~15 억 / 년 ) 중대사고핵심쟁점연구실제용융물이용실험기술심화 COSMOS, HERMES OECD/SERENA 국내최초국제공동연구 2012-2016 중대사고대처기술개발 후쿠시마사고이후실제적이고효과적인중대사고대처기술개발 중대사고연구국제선도 원천기술수준까지심화 SMART 중대사고해석수출원전중대사고대처설비개발 : VESTA 중대사고종합해석코드개발 2
주요성과 : 국제수준노심용융물실험시설 Develop Experimental Technique Using Molten Corium (2000 2014) Cold Crucible Technology Capacities: TROI (20 30 kg), VESTA-S (2 10 kg), VSETA (~ 300 kg) Wide range of Corium Compositions can be handled UO 2 +ZrO 2, UO 2 +ZrO 2 +U+Zr+SS Corium Research Platform TROI Corium Water Interaction Test Facility: Hosted OECD/SERENA Steam Explosion Experimental Program and Successful Completion (2007 2012) VESTA Test Facility for Corium-Structure Interaction Physical and Chemical Analysis of corium debris: SEM, EPMA, XRD 3
Steam Explosion OECD/SERENA Operating Agents: CEA and KAERI 4 Year Project (2007-2012) Participating organizations: 12 members AECL, CEA, IKE, IRSN, JNES, JSI, KAERI, KINS, KMU, KTH, PSI, Tractbel, UWM, VTT, USNRC TROI facility: KAERI KROTOS facility: CEA 4
Corium-Structure Interaction VESTA VESTA facility: - Jet Impingement Test - Capacity ~ 300 kg of corium Small Scale Facility - Corium/Structure Interaction at various composition ~ 10 kg 5
Core Catcher Development for EU-APR1400 6 50 40 260 52 8 200 20 50 1 50 60 15
CEPECS CEPECS: Test facility of the half-width, full height, and unit cell to examine the cooling performance of a natural circulation - Develop Core Catcher to comply with European Utility Requirement -Critical Heat Flux, Flow Instability, Natural Circulation Flow Rate - Flow Regime, Void Fraction Distribution - Preliminary analysis by CUPID compute code 7
중대사고대처기술개발 (2012-2016) 세부 1: 노심용융물냉각성능평가 ( 불확실성저감 ) 기술중대사고심층방어및대처 세부 3: 사고방사선원항저감기술 방사선원항저감 세부 2: 격납건물장기건전성확보기술세부 4: 휘발성방사성물질화학특성평가및안정화 ( 원자력화학연구부 ) 중대사고인프라구축, 인력양성 세부 5: 폭발위해도평가및저감기술 ( 대학주도과제 ) 8
PWR/BWR 관통부파손실험 Simulate Penetration Failure during Molten Corium Relocation for BWR Use VESTA Facility, Use of Real Material and Fukushima Specimen Data will be disclosed to the international society High concentrations of Fe, Ni and Cr Non-melted crust layer Metallic Ingot Oxidic Ingot Uniform and nearly the same with the initial charging compositions Initial charging compositions (UO 2 : Zr : ZrO 2 : SUS304 : B 4 C = 60 : 10 : 15 : 14 : 1 (wt.%)) Severe Accident & PHWR Safety Research Division 9
LIFE 실험실 : 격납건물환경모의 LIFE (Laboratory for Innovative Mitigation of Threats from Fission Products and Explosions): 격납건물건전성평가종합실험동 (LIFE) 건축 : - 연구원자체예산으로구축 중대사고시격납건물조건모의시설 : 수소, 에어로졸, 수증기, 압력및온도.. 격납건물안전계통성능및중대사고관리전략검증 : PAR, Spray, 여과배기설비등 Severe Accident & PHWR Safety Research Division 10
격납건물안전계통성능실험인프라 중대사고조건모의실험용기 SPARC (SPray-Aerosol-Recombiner- Combustion): ( 내경 3.4 m, 높이, 9.5 m, 1.5 MPa, 450 K) 제작 / 설치 : 독일의 THAI, 스위스의 PANDA 에수준으로 수소제어및안전설비, 계측장치구축후 PAR 성능실험에활용예정 중대사고조건국산 PAR 성능평가필요 : AECL, AREVA, NIS 제품에대해 OECD/THAI-1, 2 진행됨. THAI-3 진행중캐나다 RTF 설비에서 AECL PAR 성능실험 에어로졸 수소제어연구분야국제적인연구시설로활용도모 Severe Accident & PHWR Safety Research Division 11
여과배기설비성능검증실험시설구축 격납건물후기손상방지 : 대량방사성물질방출억제 - 체르노빌사고이후유럽에설치됨 - 후쿠시마사고이후일본, 동유럽, 벨기에등여과배기설비설치예정 - 우리나라월성 1 호기설치완료, 후속원전검토중 - 일본 BWR 은재가동시, PWR 은 5 년안에설치요구 - 미국은 BWR 설치하지않음. PWR 은검토중 - 장기간운전성능 (72 시간 ) 확보, 요드및유기요드제염성능향상연구진행중, 최적운전전략수립필요 EU 는 PASSAM, MIRE 프로젝트수행중 - 영과배기설비선능검증실험장치구축예정 : 올해말목표 Severe Accident & PHWR Safety Research Division 12
환경변화및차기단계기획방향 (2017 ~) 가동원전 (PWR, PHWR): 국제안전협약방사성물질방출제한구체화, 국내외중대사고관리전략법제화추진, 원자력안전기술에대한국민적신뢰구축필요 SMART 원자로 : 한 - 사우디협력, 2018 예비검토, 이후시범건설 SFR 중대사고쟁점 : 150 Mwe 실증로, 2018 표준설계, 2022 건설허가 Alternate Source Term: FP Transport in Fuel and Sodium Coolibility and Re-criticality 아시아지역협력 : 원천기술 ( 독자코드, 실증실험 ) 개발로리더쉽확보 Severe Accident & PHWR Safety Research Division
Severe Accident Acceptance Criteria USA Safety Goal Policy (1986) Individual members of the public: no significant additional risk to life and health. Societal risks to life and health: comparable to or less than the risks of generating electricity by viable competing technologies and not be a significant addition to other societal risks. Quantitative Health Objectives USA: - The risk to an average individual: should not exceed 0.1% of the sum of other prompt fatality risks - The risk to the population in the area: should not exceed 0.1% of the sum of all other cancer fatality risks Subsidiary quantitative objectives CDF < 1.0E-4 per reactoryear (prevention) LERF < 1.0E-5 per reactoryear (mitigation) 14
환경변화 : 일본신안전법 : 정량적안전목표설정, 세슘의양으로, 가동원전도적용 Taken from Enforcement of the New Regulatory Requirements for Commercial Nuclear Power Reactors, July 8, 2013, Nuclear Regulation Authority 15
환경변화 : 중장기적인가동원전안전성강화 ( 예 : 프랑스 ) Taken from Jean-Christophe Niel, French approach to European Stress Test, NRC Commission meeting on lessons learned from Fukushima - July 31st 2014 16
(1) Defense in Depth: RCS Integrity 사고관리전략피동형대응설비개발현황, 기술쟁점 Depressurization /RCS Injection 중대사고전용안전감압설비 (APR1400, EPR) 중대사고조건생존성 후쿠시마원전 SRV 작동불량 ( 전원, 기계적고장 ) 대체펌프, 소방차등.. Discharge head, Mobile DG, Battery ERVC 중력충수혹은펌프 - AP1000 - 고출력원전열제거능력 - 노외증기폭발 필수기기가용성원자로계통온도, 압력, 수위계측 UPS, Innovative Technology (power harvesting and/or SA tolerant I&C: 개발미미 ) Severe Accident & PHWR Safety Research Division
(2) Defense in Depth: Containment Integrity 사고관리전략피동형대응설비개발현황, 기술쟁점 원자로격실침수 Cavity Flooding System or alternate water source with pump Water source, power supply to the pump Top flooding may be not enough to quench the exvessel corium 수소제어 PARs and Igniters 중대사고조건성능확보 격납건물냉각 PCCS AP1000 등 Water/Air Cooling 노외노심용융물냉각 격납건물배기 Core Catcher, Filtered Containment Venting 필수기기가용성격납건물압력, 수소농도, 원자로격실수위, 원자로파손여부 중대사고조건성능확보, 장기운전 72 시간 UPS, Innovative Technology (power harvesting and/or SA tolerant I&C) Severe Accident & PHWR Safety Research Division
(3) Defense in Depth: Mitigate Bypass Scenarios CFBRB 3.5% ISO. FAIL 0.02% BYPASS 8.3% NO CF 48.6% BMT 30.8% LCF 1.7% ECF 7.1% 사고관리전략피동형대응설비개발현황, 기술쟁점 증기발생기침수 Use of pump, Water source, power supply, Mobile DG, Turbine driven AFW 대기방출밸브대형물탱크연결 FCVS 혹은 PCCS 탱크연결배관및밸브 Performance under SA environment, 대처설비없음 필수기기가용성증기발생기및물탱크수위 UPS, Innovative (power harvesting and/or SA tolerant) Severe Accident & PHWR Safety Research Division
중대사고현상규명및대처체계구축로드맵 추진경과 원자로열수력및안전연구부회회원들사이국내중대사고규제기술개발 ( 규제 ), 국내원전중대사고대처능력향상기술개발 ( 산 ), 국제수준의중대사고 진행예측및대응방안개발 ( 학, 연 ) 등을위해국가차원의 중대사고현상 규명및대처체계구축을위한연구로드맵작성 필요성에대한공감대형성됨 유럽 2000 년대에 SARP (Severe Accident Research Priority) 라는중대사고 현상규명및대처설비개발을위한연구개발로드맵개발. 일본은후쿠시마 사고이후원자력학회중심중대사고대처체계구축위한연구로드맵개발. 국내관련전문가들이모여준비회의를하고추진전략을토의함. 산학연각 분야에고유한필요성이있으며, 동시에객관성을가지는것이바람직하므로, 원자력학회의특별위원회형태로추진건의하기로함. Severe Accident & PHWR Safety Research Division 20
중대사고현상규명및대처체계구축로드맵 추진전략및향후전망 활동목표 : 중대사고현상규명및대처체계구축을위한연구로드맵작성 활동기간 : 2015. 3 2016. 2 활동방안 : 일차계통방호, 격납건물방호, 사고방사선원항저감의세분야로 나누어산학연의전문가들 ( 안 ) 를중심으로활동중 분야별로정기적인회의및세미나를개최하여로드맵을작성함. 추계원자력학회에서초안을발표및의견청취를하며, 국내외전문가자문을 받아내년 1 월최종안학회이름으로발표함. 미래부, 원자력안전위원회, 산업부의안전연구방향정립에로드맵이반영될 수있도록각부처에적극건의 Severe Accident & PHWR Safety Research Division 21
Protect People, Safe and Economic Nuclear Power 22