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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 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Baiquan Deng, Zaixin Li, Jinhua Huang, Tao Yuan
Fusion Science and Technology | Volume 46 | Number 4 | December 2004 | Pages 548-560
Technical Paper | doi.org/10.13182/FST04-A590
Articles are hosted by Taylor and Francis Online.
A summary of the tritium system design activities for the engineering outline design of a fusion experimental reactor [Fusion Experimental Breeder-E (FEB-E)] is presented. This paper is divided into three sections. First, the geometry, loading features, and tritium concentrations in liquid lithium of tritium breeding zones in blankets are described. Then, a tritium flowchart corresponding to the tritium fuel cycle system is constructed, and the SWITRIM code is developed for calculation of the inventories in the ten subsystems. Results show that the necessary initial tritium storage to start up the reactor with fusion power of 143 MW is ~317 g. Finally, a tritium leakage analysis under different operation circumstances is performed. It is found that the potential danger of tritium leakage could result from the exhausted gas of the divertor system. It is important to elevate the tritium burnup fraction and reduce the tritium throughput.