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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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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Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
H. Y. Khater, M. E. Sawan
Fusion Science and Technology | Volume 21 | Number 3 | May 1992 | Pages 2112-2116
Blanket Shield and Neutronic | doi.org/10.13182/FST92-A30032
Articles are hosted by Taylor and Francis Online.
Activation analysis has been performed for the D-3He fueled reactor ARIES-III. The activity, decay heat and biological hazard potential (BHP) have been calculated for the low activation steel (modified HT-9) first wall and shield as a function of time following the reactor shutdown. The total activity produced in the reactor at shutdown is 1549 MCi. The total activity produced in the reactor organic coolant following 30 full power years of operation without reprocessing is 458 Ci. The modified HT-9 shield qualifies for shallow land burial as Class A low level waste. The biological dose rate after shutdown at the back of the outboard shield is too high to allow hands-on maintenance. Burning all the tritium in the plasma chamber results in increasing the radioactivity generated in ARIES-III by 65% to 85% at different times following the reactor shutdown.
