Current status and recent research achievements in SiC/SiC composites

Abstract

The development and maturation of the silicon carbide fiber-reinforced silicon carbide matrix (SiC/SiC) composite system for fusion applications has seen the evolution from fundamental development and understanding of the material system and its behavior in a hostile irradiation environment to the current effort which essentially is a broad-based program of technology, directed at moving this material class from a laboratory curiosity to an engineering material. This paper lays out the recent international scientific and technological achievements in the development of SiC/SiC composite material technologies for fusion application and will discuss future research directions. It also reviews the materials system in the larger context of progress to maturity as an engineering material for both the larger nuclear community and for general engineering applications.

Estimation of Routine Discharge of Radionuclides on Power Reactor Experimental Rde

“…TRISO fuel particle configuration [1,7] From Fig 1, four coating layers of TRISO particle act as pressure vessel with high integrity that is very strong against fission products. The main purpose of the high density IPyC coating, on which SiC coating is deposited, is to have high integrity and prevent chlorine (Cl2) and hydrogen chloride (HCl) againts being absorbed by fuel kernels during the deposition process of SiC [2][3][4]7,9,13] . Therefore, IPyC plays an important role during the fabrication.…”

“…As upholstery, high density OPyC shrinks during irradiation time, which also produces compressive stress in SiC dimension, and is partly compensating for the components of the tensile stress caused by the internal gas pressure. OPyC coatings are also effective in maintaining the fission gas in the fuel particles in case of SiC fabrication defect that fails to work up to about 1800 °C [2][3][4]7,[12][13][14] .…”

“…The silicon carbide layer has the ability to confine fission products and it can also withstand very high temperature. Barrier of fission products release of RDE-10 MWth consists of the pressure boundary, building, suppression pool and filters [1][2][3][4][5][6][7][8] .…”

“…Release mechanism includes fuel, core, building ventilation, helium purification, gaseous radioactive waste system, and neutron activation of circulating air through the Reactor Cavity of Cooling System (RCCS) [2][3][4][5][6][7] . Mechanistic approach for a source term development is required to setup technical basis and to take appropriate benefit of radionuclide retention capabilities of each of the multiple barriers in radionuclides transport.…”

Investigation of thermal transport in composites and ion beam irradiated materials for nuclear energy applications

“…However, issues associated with brittleness are mitigated when used in a composite form where SiC fibers (SiC f ) are embedded in SiC matrix (SiC m ). 84 Mechanical strength of the composite is enhanced by introducing a thin pyrolytic carbon interphase layer that acts as a barrier for crack propagation under embrittlement conditions. 85 While the properties of bulk SiC and its radiation behavior were extensively studied, the behavior of this ceramic matrix composite (CMC) is an active area of research.…”