Assessment of Silicon Carbide Composites for Advanced Salt-Cooled Reactors

Katoh, Yutai¹  Wilson, Dane F¹  Forsberg, Charles W¹ 

[1] ORNL

关键词: COOLANTS;    CORROSION;    CREEP;    FABRICATION;    FLUORIDES;    FUEL ASSEMBLIES;    IRRADIATION;    NEUTRONS;    RADIATION EFFECTS;    RECOMMENDATIONS;    SILICON CARBIDES;    THERMODYNAMICS;    VIABILITY;   

DOI  :  10.2172/982717
RP-ID  :  ORNL/TM-2007/168
PID  :  OSTI ID: 982717
Others  :  Other: AF3620800
Others  :  NEAF265
Others  :  TRN: US1004554

学科分类：物理（综合）

美国|英语

来源: SciTech Connect

【 摘 要 】

The Advanced High-Temperature Reactor (AHTR) is a new reactor concept that uses a liquid fluoride salt coolant and a solid high-temperature fuel. Several alternative fuel types are being considered for this reactor. One set of fuel options is the use of pin-type fuel assemblies with silicon carbide (SiC) cladding. This report provides (1) an initial viability assessment of using SiC as fuel cladding and other in-core components of the AHTR, (2) the current status of SiC technology, and (3) recommendations on the path forward. Based on the analysis of requirements, continuous SiC fiber-reinforced, chemically vapor-infiltrated SiC matrix (CVI SiC/SiC) composites are recommended as the primary option for further study on AHTR fuel cladding among various industrially available forms of SiC. Critical feasibility issues for the SiC-based AHTR fuel cladding are identified to be (1) corrosion of SiC in the candidate liquid salts, (2) high dose neutron radiation effects, (3) static fatigue failure of SiC/SiC, (4) long-term radiation effects including irradiation creep and radiation-enhanced static fatigue, and (5) fabrication technology of hermetic wall and sealing end caps. Considering the results of the issues analysis and the prospects of ongoing SiC research and development in other nuclear programs, recommendations on the path forward is provided in the order or priority as: (1) thermodynamic analysis and experimental examination of SiC corrosion in the candidate liquid salts, (2) assessment of long-term mechanical integrity issues using prototypical component sections, and (3) assessment of high dose radiation effects relevant to the anticipated operating condition.