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Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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
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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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.
Mahmoud Z. Youssef, Insoo Jun
Fusion Science and Technology | Volume 15 | Number 2 | March 1989 | Pages 887-892
ITER Nuclear Design | doi.org/10.13182/FST89-A39806
Articles are hosted by Taylor and Francis Online.
In the initial design of TIBER-II inboard (I/B) shield, multilayers of tungsten shield and coolant were deployed with a total thickness of 48 cm. It was thought during the design process to replace W by PCA. The motivations are: (1) accumulated activation level in the I/B shield at shutdown is larger in the W-shield in comparison to the PCA-shield, and (2) concerns regarding cost/fabrication. This design change required an I/B shield thickness of ∼58 cm to reach the same performance level of the 48 cm W-shield. In this paper a detailed comparison between the two types of shield is given regarding the accumulated radioactivity, biological hazard potential (BHP), and afterheat levels at shutdown and various times thereafter. In addition, a substantial part of the present work is devoted to studying the impact of the present neutron cross-section uncertainties in the prediction of the radiation damage parameters in the S/C magnet. In this regard, an extensive cross-section sensitivity/uncertainty analysis was performed to assess the required increase in the I/B shield thickness in both cases to account for these uncertainties. It was shown that the economic penalty of such an increase is 13–17 M$ in the W-shield case as opposed to 10–14 M$ in the case of the PCA-shield.