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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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Latest News
Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Katsumi Yoshida, Toyohiko Yano, Takayoshi Iseki
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 607-611
Fusion Materials | doi.org/10.13182/FST01-A11963304
Articles are hosted by Taylor and Francis Online.
The interfacial strength of SiC/SiC composites fabricated by hot-pressing (HP) and chemical vapor infiltration (CVI) method was measured by push-in test, and the effect of interfacial strength on the fracture behavior of SiC/SiC composites was investigated. Maximum strength and fracture energy of the CVI-SiC/SiC composite was higher than those of the HP-SiC/SiC composite due to lower interfacial shear sliding strength and higher fiber strength. The SiC/SiC composite hot-pressed at 1750 °C had a higher interfacial shear sliding strength and lower fiber strength, resulting in low maximum strength and fracture energy. The SiC/SiC composite hot-pressed at 1650 °C showed a lower maximum strength and higher fracture energy in spite of a lower interfacial shear sliding strength and higher fiber strength. In this case, the delamination between fiber and the matrix occurs easily.