Modeling of silicon carbide duplex cladding designs for high burnup light water reactor fuel

Societe Francaise d'Energie Nucleaire - International Congress on Advances in Nuclear Power Plants - ICAPP 2007, "The Nuclear Renaissance at Work"

Volumn 3, Issue , 2008, Pages 1465-1473

  Carpenter, David ^a   Kohse, Gordon ^a   Kazimi, Mujid ^a  

^a Massachusetts Institute of Technology   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CHEMICAL-; CURRENT PEAKS; FISSION GAS RELEASE; FUEL RODS; FUEL TEMPERATURES; HEAT RATES; HIGH BURN-UP; HIGHER TEMPERATURES; INCREASED TEMPERATURES; INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS; LIGHT WATER; LWR FUEL; MECHANICAL BEHAVIORS; NUCLEAR RENAISSANCE; OPERATING CONDITIONS; POWER DENSITIES; RADIATION ENVIRONMENTS; SIC FIBERS; ULTIMATE STRENGTH; ZIRCALOY;

ARCHITECTURAL DESIGN; CHEMICAL REACTIONS; CHEMICAL RESISTANCE; CODES (STANDARDS); CODES (SYMBOLS); ELECTRIC POWER PLANTS; FIBER OPTICS; FISSION PRODUCTS; FUELS; LIGHT WATER REACTORS; METAL CLADDING; MOLECULAR BEAM EPITAXY; NONMETALS; NUCLEAR ENERGY; NUCLEAR ENGINEERING; NUCLEAR FUELS; NUCLEAR INDUSTRY; NUCLEAR POWER PLANTS; NUCLEAR REACTORS; PELLETIZING; POWER PLANTS; PRESSURIZED WATER REACTORS; RATE CONSTANTS; SILICON; SILICON ALLOYS; SILICON CARBIDE; STRESSES; SULFATE MINERALS; TEXTILE FINISHING; TUBES (COMPONENTS); WATER COOLED REACTORS; ZIRCONIUM; ZIRCONIUM ALLOYS;

LEAKAGE (FLUID);

EID: 52349085981     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (22)

1. R. YANG, B. CHENG, Jeff DESHON, K. EDSINGER, and O. OZER, "Fuel R&D to Improve Fuel Reliability," Journal of Nuclear Science and Technology, 43, 9, 951 (2006)
2. CEGA, NP-MHTGR, Material Models of Pyrocarbon and Pyrolytic Silicon Carbide, CEGA Corporation, San Diego (1993).
3. L. H. ROVNER and G. R. HOPKINS, "Ceramic materials for fusion," Nuclear Technology, 29, 274 (1976).
4. G. A. BERNA, C. E. BEYER, K. L. DAVIS, and D. D. LANNING "FRAPCON-3: A Computer Code for the Calculation of Steady-State, Thermal-Mechanical Behavior of Oxide Fuel Rods for High Burnup, Vol. 2", NUREG/CR-6534, PNNL-11513, prepared for the U.S. Nuclear Regulatory Commission by Pacific Northwest Laboratory, Richland (1997).
5. Y. LONG, "Modeling the performance of high burnup thoria and urania PWR fuel," Ph.D. Thesis, Massachusetts Institute of Technology, Cambridge (2002).
6. H. ICHIKAWA and T. ISHIKAWA, "Silicon carbide fibers (organometallic pyrolysis)," Comprehensive Composite Materials, Pergamon (2000).
7. M.C. OSBORNE, C. R. HUBBARD, L. L. SNEAD, and D. STEINER, "Neutron irradiation effects on the density, tensile properties and microstructural changes in Hi-Nicalon and Sylramic SiC fibers," Journal of Nuclear Materials, 253, 1-3, 67 (1998).
8. L. L. SNEAD, S. J. ZINKLE, and D. P. WHITE, "Thermal conductivity degradation of ceramic materials due to low temperature, low dose neutron irradiation," Journal of Nuclear Materials, 340, 2-3, 187 (2005).
9. J. LI, L. PORTER, and S. YIP, "Atomistic modeling of finite-temperature properties of crystalline β-SiC; II. Thermal conductivity and effects of point defects," Journal of Nuclear Materials, 255, 2-3, 139 (1998).
10. G. E. YOUNGBLOOD, D. J. SENOR, and R. H. JONES, "Effects of irradiation and post-irradiation annealing on the thermal conductivity/ diffusivity of monolithic SiC and f-SiC/SiC composites," Journal of Nuclear Materials, 329-333, 1, 507 (2004).
11. L. L. SNEAD, "Limits on irradiation-induced thermal conductivity and electrical resistivity in silicon carbide materials," Journal of Nuclear Materials, 329-333, 1, 524 (2004).
12. L. L. SNEAD, T. HINOKI, and Y. KATOH, "Strength of neutron irradiated silicon carbide and silicon carbide composite," Fusion Materials Volume 33, Semi-Annular Progress Report for Period Ending December 31, 2002, Oak Ridge National Laboratory (2003).
13. N. MIRIYALA, P. K. LIAW, C. J. MCHARGUE, and L. L. SNEAD, "The mechanical behavior of a Nicalon/SiC composite at room temperature and 1000C," Journal of Nuclear Materials, 253, 1-3, 1 (1998).
14. R. H. JONES, D. STEINER, H. L. HEINISCH, G. A. NEWSOME, and H. M. KERCH, "Radiation resistant ceramic matrix composites," Journal of Nuclear Materials, 245, 2-3, 87 (1997).
15. f/SiC composites up to 25 dpa," Journal of Nuclear Materials, 219, 2, 70 (1995).
16. S. NOGAMI, A. HASEGAWA, L. L. SNEAD, et al., "Effect of pre-implantation and neutron irradiation on mechanical properties of SiC/SiC composites," Journal of Nuclear Materials, 329-333, 1, 577 (2004).
17. K. A. SCHWETZ, "Silicon Carbide Based Hard Materials," Handbook of Ceramic Hard Materials, Riedel, Ralph (ed.), Wiley-VCH (2000).
18. R. S. ZIMMERMAN and D. F. ADAMS, "Static tensile and tensile creep testing of five ceramic fibers at elevated temperatures," NASA Contractor Report 177525, NASA Ames Research Center (1989).
19. R. J. BROOK (ed.), Concise Encyclopedia of Advanced Ceramic Materials, MIT Press, Cambridge (1991).
20. H. HIRAYAMA, T. KAWAKUBO A. GOTO, and T. KANEKO, "Corrosion Behavior of Silicon Carbide in 290°C Water," Journal of the American Ceramic Society, 11, 11, 2049 (1989).
21. W. KIM, H. S. HWANG J. Y. PARK, and W. RYU, "Corrosion behaviors of sintered and chemically vapor deposited silicon carbide ceramics in water at 360°C," Journal of Materials Science Letters, 22, 8, 581 (2003).
22. R. MANZEL and C. T. WALKER, "High burnup fuel microstructure and its effect on fuel rod performance," Proceedings of the 2000 International Topical Meeting on LWR Fuel Performance, April 10-13, Park City, Utah, (2000).