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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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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Retrieval of nuclear waste canisters from a borehole
Borehole disposal of spent nuclear fuel (SNF) and high-level waste (HLW) uses off-the-shelf directional drilling technology developed and commercialized by the oil and gas sectors. It is a technology that has been gaining traction in recent years in the nuclear industry. Disposal can be done in one or more boreholes (including an array) drilled into suitable sedimentary, igneous, or metamorphic host rocks. Waste is encapsulated in specialized corrosion-resistant canisters, which are placed end to end in disposal sections of relatively small-diameter boreholes that have been cased and fluid-filled. After emplacement, the vertical access hole is plugged and backfilled as an engineered barrier.
S. Suzuki, M. Akiba, M. Araki, K. Yokoyama
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 1858-1862
Plasma-Facing Component | doi.org/10.13182/FST92-A29989
Articles are hosted by Taylor and Francis Online.
JAERI has been intensively developing plasma facing components for next step large fusion machines, such as ITER (International Thermonuclear Experimental Reactor). It is one of the most important issues to develop divertor plates in the engineering design activity of ITER. The divertor plates are exposed severe heat loads and particle fluxes from fusion plasma. In the operation condition of ITER, the divertor plates are required to withstand a peak heat flux of 15∼30 MW/m2. In the present study, monoblock divertor modules have been manufactured and tested in an electron beam test facility in JAERI, which consist of carbon reinforced carbon composite (CFC) materials brazed on an OFHC copper tube directly. Thermal cycling experiments have been carried out with a peak heat flux of 15 MW/m2. It has successfully been demonstrated that the present design of the ITER divertor plate can endure a stationary heat load of 15 MW/m2 for more than 1000 cycles.