Zobrazeno 1 - 10
of 20
pro vyhledávání: '"George M. Jacobsen"'
Autor:
Amanda M. Johnsen, James A. Turso, Andrew Bascom, George M. Jacobsen, Eugene A. Olevsky, Hangbok Choi, Xialu Wei
Publikováno v:
Nuclear Technology. 208:27-36
Zirconium silicide (Zr3Si2) is a heavy reflector material particularly effective for application to a Gas-cooled Fast Reactor (GFR) such as the General Atomics Energy Multiplier Module (EM2) and Fa...
Publikováno v:
Journal of Nuclear Materials. 522:184-191
Silicon carbide matrix reinforced with silicon carbide fiber (SiC-SiC) composite is an advantageous material for many high temperature applications due to retention of room temperature strength above 1100 °C, which is the current operational limit f
Autor:
Christian P. Deck, Luis H. Alva, Xinyu Huang, Nathaniel Truesdale, Kirill Shapovalov, George M. Jacobsen
Publikováno v:
Journal of Nuclear Materials. 500:280-294
The authors report mechanical strength of nuclear grade silicon carbide fiber reinforced silicon carbide matrix composite (SiCf-SiCm) tubing under several different stress states. The composite tubing was fabricated via a Chemical Vapor Infiltration
Publikováno v:
Journal of Nuclear Materials. 487:91-95
This paper reports on a nuclear-grade joining material for bonding of silicon carbide-based components. The joint material is fabricated via a hybrid preceramic polymer, chemical vapor infiltration process. The joint is comprised entirely of β-SiC a
Publikováno v:
Transactions of the American Nuclear Society - Volume 121.
Autor:
H.E. Khalifa, Christina Back, George M. Jacobsen, Christian P. Deck, Joshua Stone, Robert W. Schleicher
Publikováno v:
Journal of Nuclear Materials. 466:682-697
Silicon carbide (SiC) fiber, SiC matrix composites (SiC/SiC) are being considered as a cladding material for light water reactors in order to improve safety performance. Engineered, multi-layer cladding designs consisting of both monolithic SiC (mSiC
Autor:
Christina Back, H.E. Khalifa, Sheeder Jonathan David, George M. Jacobsen, Christian P. Deck, Joshua Stone, O. Gutierrez, Zhang Jiping
Publikováno v:
Journal of Nuclear Materials. 466:667-681
Silicon carbide (SiC) is being investigated for accident tolerant fuel cladding applications due to its high temperature strength, exceptional stability under irradiation, and reduced oxidation compared to Zircaloy under accident conditions. An engin
Publikováno v:
Journal of Nuclear Materials. 466:698-711
Nuclear grade silicon carbide fiber (SiCf) reinforced silicon carbide matrix (SiCm) composite is a promising candidate material for accident tolerance fuel (ATF) cladding. A major challenge is ensuring the mechanical robustness of the ceramic claddin
Publikováno v:
Journal of Nuclear Materials. 457:227-240
The use of silicon carbide (SiC) composites as structural materials in nuclear applications necessitates the development of a viable joining method. One critical application for nuclear-grade joining is the sealing of fuel within a cylindrical claddi
Publikováno v:
Journal of Nuclear Materials. 452:125-132
Silicon carbide (SiC) and silicon carbide fiber reinforced composites (SiC/SiC f ) are currently being evaluated as a high temperature material for use in nuclear reactors. While methods to determine the mechanical properties of SiC/SiC f on planar t