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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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
H. B. Xu, R. Guo, Z. Cao, M. Li, X. L. Liu, B. Zhang, HL-2A Team
Fusion Science and Technology | Volume 79 | Number 2 | February 2023 | Pages 162-167
Technical Paper | doi.org/10.1080/15361055.2022.2131162
Articles are hosted by Taylor and Francis Online.
Pellet injection (PI) is the preferred fueling method in the future fusion reactor. It is particularly important to study the flow field characteristics of the frozen fuel extrusion process for the future steady operation of the pellet injector. In order to study the influence of groove depth on extrusion flux and conveying capacity, the flow field characteristics of a repetitive pellet injector with a single-screw extruder in the China Fusion Engineering Test Reactor (CFETR) was numerically simulated with POLYFLOW software. Thus, information about pressure field, viscous heating, and velocity field distribution was obtained. The results indicate that to a certain extent, increasing the groove depth (while maintaining the gaps between the screw and extrusion cylinder) is beneficial for the conveying capacity and pressure building capacity. The results of the numerical simulations show that at a screw speed of 120 rpm, screw outer diameter of 20 mm, screw length of 230 mm, screw groove depth of 6 mm, and screw prism gap of 0.3 mm, solid hydrogen can be stably extruded, and the velocity of the extruded ice at the nozzle is 0.15 m/s, which meets the design requirement of the CFETR PI system. These results also provide good references for structure design and performance optimization of the CFETR pellet injector.