Mechanical strength of CTP triplex SIC fuel clad tubes after irradiation in MIT research reactor under PWR coolant conditions

Ceramic Engineering and Science Proceedings

Volumn 30, Issue 10, 2010, Pages 47-55

  Feinroth, Herbert ^a   Ales, Matthew ^a   Barringer, Eric ^a   Kohse, Gordon ^b   Carpenter, David ^b   Jaramillo, Roger ^c  

^a Ceramic Tubular Products   (United States)

^b MASSACHUSETTS INSTITUTE OF TECHNOLOGY   (United States)

^c OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

BARRIER LAYERS; BORIC ACIDS; COOLANT CONDITIONS; HERMETICITY; HOOP STRENGTH; HYDROGEN OVERPRESSURE; LITHIUM HYDROXIDE; MECHANICAL STRENGTH; NEW SPECIMEN; OAK RIDGE NATIONAL LABORATORIES; PREIRRADIATION; PRESSURIZED WATER; REACTOR FUELS; SIC/SIC COMPOSITES; TEST APPARATUS; TUBULAR PRODUCTS;

CERAMIC PRODUCTS; COOLANTS; FAILURE ANALYSIS; IMPACT STRENGTH; INORGANIC ACIDS; IRRADIATION; LITHIUM; NEUTRON BEAMS; NEUTRON FLUX; NUCLEAR FUELS; NUCLEAR REACTOR ACCIDENTS; RESEARCH REACTORS; SILICON CARBIDE; TUBES (COMPONENTS);

PRESSURIZED WATER REACTORS;

EID: 77951994516     PISSN: 01966219     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (3)

1. H. Feinroth, B. Hao, L Fehrenbacher, M. Patterson, "Progress in Developing an Impermeable High Temperature Ceramic Composite for Advanced Reactor Clad and Structural Applications" Paper 1176, International Conference on Advanced Nuclear Power Plants, Hollywood, Florida, 2002.
2. Denwood F. Ross, William R. Hendrick, "Strength Testing of Monolithic and Duplex Silicon Carbide Cylinders in Support of Use as Nuclear Fuel Cladding" The 30th International Conference on Advanced Ceramics & Composites (2006 ICACC) January, 2006 - Cocoa Beach, Florida
3. L. Snead, Y. Katoh, S. Connery, "Swelling of SiC at Intermediate and High Irradiation Temperatures" Journal of Nuclear Materials, 367-370 677-684 (2007)