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Division Spotlight
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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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Fusion Science and Technology
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.
K. Takahashi et al.
Fusion Science and Technology | Volume 63 | Number 1 | May 2013 | Pages 156-159
doi.org/10.13182/FST13-A16894
Articles are hosted by Taylor and Francis Online.
Nuclear analysis of the ITER equatorial EC launcher consisting of an unique blanket shield structure and a port plug installing millimeter (mm) wave components, neutron shields, cooling water lines, etc. has been carried out. The analysis results are used to determine heat and/or particle loads on its components and to evaluate the possibility of “hands-on maintainability” (personnel accessibility) to the launcher back-end. A significant radiation leak at the gaps between the port walls and port plug frame of the launcher was revealed. Another significant neutron leakage is through the port wall consisting of only stainless steel but without light isotopes such as water. The shut down dose rates was estimated at the port interspace behind the launcher at the same level of the required value of 100 Sv/h. This analysis offers the potential to modify the launchers shielding layout to minimize the above leakage and further reduce the shut down dose rates in the regions of personnel access.