RADIATION DAMAGE PARAMETERS FOR SiC/SiC COMPOSITE STRUCTURE IN FUSION NUCLEAR ENVIRONMENT
نویسنده
چکیده
The radiation effects in the fiber, matrix, and interface components of the SiC/SiC composite material are important input for lifetime assessment. Neutronics calculations were performed to determine the radiation damage parameters in the fiber/matrix and the candidate interface materials. The radiation damage parameters were calculated for both the carbon and silicon sublattices. The radiation damage parameters were evaluated for representative candidate breeding blankets. The breeder and/or coolant such as Pb83Li17, Flibe and Li2O affect the radiation damage parameters by impacting the neutron spectrum. The results provide an essential input for SiC/SiC composite lifetime assessment. The impact of the unique features of inertial fusion systems on damage parameters are identified.
منابع مشابه
Damage production and accumulation in SiC structures in inertial and magnetic fusion systems
0022-3115/$ see front matter 2010 Elsevier B.V. A doi:10.1016/j.jnucmat.2010.12.077 ⇑ Corresponding author. Tel.: +1 608 263 5093; fax E-mail address: [email protected] (M.E. Sawan Radiation damage parameters in SiC/SiC composite structures are determined in both magnetic (MFE) and inertial (IFE) confinement fusion systems. Variations in the geometry, neutron energy spectrum, and pulsed natur...
متن کاملNon - destructive inspection of SiCf / SiC composites structure
Fiber reinforced ceramic matrix composite is an attractive candidate as a structural material for future fusion power plants because of their light weight, high temperature capability, high strength and toughness. Ceramic matrix composite made of silicon carbide matrix and fibers (SiCf/SiC) is promising for nuclear and fusion technology due to its excellent radiation resistance, especially expo...
متن کاملX-ray fluorescence microtomography on a SiC nuclear fuel shell
TRISO fuel particles, used in high-temperature gas-cooled reactors (HTGR) are composite structures with a nuclear fuel kernel surrounded by alternating layers designed to contain fission products and compensate for radiation damage. As shown in Figure 1, a typical fuel particle contains an inner kernel of nuclear fuel, a low-density buffer layer of pyrocarbon, a dense layer of pyrocarbon coatin...
متن کاملUWFDM-1394 Structural Materials Damage in Fusion and Fission Systems
Calculations were performed to quantify the damage parameters in the leading candidate structural and plasma facing materials when used in magnetic and inertial confinement fusion systems and when irradiated in fission reactors. The structural materials considered are ferritic steel, austenitic steel, vanadium alloy and SiC/SiC composite. Plasma facing materials included beryllium, tungsten, an...
متن کاملComputation of the NMR Parameters of H-Capped (10,0) and (5,5) Single-Walled SiC Nanotubes
Geometrical structure, nuclear magnetic resonance (N1,1It) chemical shielding tensors, and chemical shiftsof silicon and carbon nucler are investigated for twn infinite size zigzag and armchair single-walled siliconcarbide nanotabes (SiCNTs). Geometrical structures of SieNTs, Sit bonds and bond angles of St and Cvertices in both zigzag and armchair nanotubes, Indicate that bond lengths are appr...
متن کامل