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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2023)
February 6–9, 2023
Amelia Island, FL|Omni Amelia Island Resort
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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Nuclear Science and Engineering
February 2023
Nuclear Technology
Fusion Science and Technology
January 2023
Latest News
Framatome, Ultra Safe partner to manufacture TRISO and FCM fuel
Framatome and Ultra Safe Nuclear announced on January 26 that they intend to form a joint venture to manufacture commercial quantities of tristructural isotropic (TRISO) particles and Ultra Safe’s proprietary fully ceramic microencapsulated (FCM) fuel.
The companies have signed a nonbinding agreement to integrate their resources to bring commercially viable, fourth-generation nuclear fuel to market for Ultra Safe’s micro-modular reactor (MMR) and other advanced reactor designs.
L. Chen, W. Zhao, G. Zhong, C. Watts, James P. Gunn, X. Liu, Y. Lian, DLP Team
Fusion Science and Technology | Volume 73 | Number 4 | May 2018 | Pages 568-578
Technical Note | doi.org/10.1080/15361055.2017.1415614
Articles are hosted by Taylor and Francis Online.
The thermal performance of the divertor Langmuir probe conceptual design developed for the ITER divertor, which consists of a shielded probe bolted to a copper heat sink, has been predicted by the finite element analysis package ANSYS to have a high risk of damage due to poor heat transfer ability. In order to mitigate this risk, three alternative designs focusing on improving heat conduction have been proposed, and the power-handling abilities, damage risk, and interface challenges of the three designs have been compared. First simulation results indicate that a design involving casting a tungsten probe sensor into a copper heat sink could provide adequate heat-handling capacity. Elasto-plastic stress analysis will be needed to evaluate the thermal stresses at W/Cu interface in our future work. Langmuir probe prototypes will be prepared and high heat flux tests will be performed on electron beam facilities at the Southwestern Institute of Physics to verify the probe functionality once analysis has identified a suitable candidate design.