[논문]원자력 사고 안전성 향상을 위한 SiCf/SiC 복합소재 개발 동향

김대종; 이지수; 천영범; 이현근; 박지연; 김원주

doi:10.7234/composres.2022.35.3.161

원자력 사고 안전성 향상을 위한 SiCf/SiC 복합소재 개발 동향
A Review of SiCf/SiC Composite to Improve Accident-Tolerance of Light Water Nuclear Reactors 원문보기

Composites research = 복합재료, v.35 no.3, 2022년, pp.161 - 174

김대종 (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) , 이지수 (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) , 천영범 (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) , 이현근 (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) , 박지연 (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute) , 김원주 (Materials Safety Technology Development Division, Korea Atomic Energy Research Institute)

초록
AI-Helper

SiC 섬유강화 복합체는 경수형 원자로의 안전성을 획기적으로 향상시킬 수 있는 사고저항성 핵연료 피복관 소재이다. 지르코늄 합금 피복관 및 금속기반 사고저항성 핵연료 피복관에 비해, 중대 사고 환경에서도 우수한 구조적 안정성을 가지고 부식 속도가 매우 낮아, 사고 시 원자로의 온도를 낮추고 사고 진행을 늦출 수 있다. 본 논문에서는 현재 개발되고 있는 사고저항성 SiC 복합체 핵연료 피복관의 개념 및 가동/사고환경에서의 다양한 특성, 상용화를 위해 해결해야 할 다양한 이슈에 대해서 소개하고자 한다.

Abstract ▼ AI-Helper

SiC fiber-reinforced SiC matrix composite is a promising accident-tolerant fuel cladding material to improve the safety of light water nuclear reactors. Compared to the current zirconium alloy fuel cladding as well as metallic accident-tolerant fuel cladding, SiC composite fuel cladding has exceptional accident-tolerance such as excellent structural integrity and extremely low corrosion rate during severe accident of light water nuclear reactors, which reduces reactor core temperature and delays core degradation processes. In this paper, we introduce the concept, technical issues, and properties of SiC composite accident-tolerant fuel cladding during operation and accident scenarios of light water nuclear reactors.

주제어

표/그림 (24)

그림 Fig. 1. Cumulative energy due to decay heat and Zr-based cladding oxidation heat [8]
그림 Fig. 2. Neutron scattering and absorption cross-section for pure elements [20]
그림 Fig. 3. Neutron irradiation-induced swelling of C_f/C and nuclear-grade SiC_f/SiC [21]
표 Table 1. Nuclear-grade SiC fibers [25,26]
그림 Fig. 4. PyC layer thickness dependence of the strength of SiC_f/SiC [29]
그림 Fig. 5. CVI-SiCf/SiC tubes with various textures: filament winding, 2D braiding, and 3D braiding [38]
그림 Fig. 6. Swelling of CVD SiC and nuclear-grade CVI-SiC_f/SiC [49]
그림 Fig. 7. Cross section of triplex SiC composite cladding (CVD SiC-SiC_f/SiC-CVD SiC) after neutron irradiation [51]
그림 Fig. 8. Influence of fiber angle of CVI-SiC_f/SiC tubes on (a) axial tensile strength and (b) hoop tensile strength [57]
그림 Fig. 9. Flexural strength of nuclear grade CVI-SiC_f/SiC composite after neutron irradiation [58]
그림 Fig. 10. Microstructure of various SiC in pressurized water at 360°C: (a) RBSC, (b) sintered SiC, and (c) CVD SiC [59,60]
그림 Fig. 11. Influence of dissolved hydrogen (35 cc/kg H₂O) on hydrothermal corrosion of CVD SiC in the pressurized high temperature water (360°C, 20 MPa) [62]
그림 Fig. 12. Hydrothermal corrosion of SiCf/SiC-CVD SiC multi-layered tubesydHy in the pressurized high temperature water (DH = 35 cc/kg H₂O, 360°C, 20 MPa) [64]
그림 Fig. 13. Influence of crystallinity of SiC composite fabricated by a CVI process [65]
그림 Fig. 14. Weight changes of various CVD SiC after 127 days in MITR PWR loop (green: water, blue: water + radiolysis, red: water + radiolysis + neutron damage (1 dpa)) [66]
그림 Fig. 15. Thermal conductivity of unirradiated Hi-Nicalon Type S fiber-reinforced SiC/SiC composite tubes and plate [72]
그림 Fig. 16. Thermal conductivity of irradiated Hi-Nicalon Type S fiber-reinforced SiC/SiC composite tubes and plate after neutron irradiation: (a) low heat flux and (b) high heat flux irradiation [72]
그림 Fig. 17. Thermal shock behavior of Ni-Nicalon Type S fiber-rein-forced SiC composite [73]
그림 Fig. 18. Cracking during quenching from 1200°C to room temperature water
그림 Fig. 19. Tensile stress-strain mechanical behavior of as-fabricated SiC/SiC tube and quenched SiC/SiC tube after 1500°C exposure under steam for 100 s [75]
그림 Fig. 20. Hoop strength of various triplex SiC composite tubes after thermal shock from 1200°C to RT [76]
그림 Fig. 21. Weight change of SiC in hot steam environments
그림 Fig. 22. Weight change of duplex SiC composite tubes (inner SiC_f/SiC-outer CVD SiC) with or without TiCrN in 1600°C hot steam (original data)
그림 Fig. 23. Diametral ring compressive strength of duplex SiC composite tubes with or without TiCrN after hot steam oxidation at 1600°C for up to 25 hours (original data)

AI 본문요약
AI-Helper

후속연구

원자력 에너지가 유럽 녹색 분류체계(EU Texsonomy)에 포함되고, 원자력 발전의 안전성 향상을 위해 사고저항성 핵연료 기술을 요구함에 따라, 빠른 시일 내에 대응가능한 사고저항성 코팅이 적용된 지르코늄 합금 피복관이 적용될 것으로 보인다. 그러나 코팅 지르코늄 합금 피복관의 부족한 사고저항성으로 인해, 대부분의 국가에서 차세대 사고저항성 핵연료 피복관 소재로 SiC 복합체를 선정하였다.

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저자의 다른 논문 :

표제어: PCR

동의어: Packet Collision Rate

용어 설명 출처 목록 (6)

용어 설명: PCR은 세균 특이성이 있는 primer를 이용하여 적은 수의 세균이 있을지라도 쉽게 검출할 수 있는 유용한 방법이며, 이를 이용하여 구강 내 치면세균막이나 타액에서 직접 세균을 검출할 수 있게 되었다[8].

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