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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
Transport by Barge and Road: Shipping Crystal River’s Segmented RPV to Disposal
The Optimized Segmentation process patented by Orano Decommissioning Services was successfully implemented for the first time at the Crystal River Unit 3 (CR-3) decommissioning project in Florida [1]. Using this approach, Orano was able to avoid the time- and resource-intensive process of packaging components into numerous standardized waste containers and significantly reduced the required segmentation activities.
I. N. Sviatoslavsky, A. R. Raffray, M. E. Sawan, X. Wang
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 535-539
Technical Paper | Fusion Energy - First Wall, Blanket, and Shield | doi.org/10.13182/FST05-A739
Articles are hosted by Taylor and Francis Online.
A multi-institutional study HAPL (High Average Power Laser) is investigating a relatively near term conceptual design of a laser driven inertial confinement reactor. A primary focus of the study is the protection of the first wall (FW) from the target emanations. This paper gives a brief analysis of one of several possible blankets that can be integrated with the chosen FW protection scheme. The structural material is conventional ferritic steel (FS) F82H cooled with liquid lithium. The maximum average temperature is constrained to 550°C. The chamber radius is 6.5 m at midplane, tapering to 2.5 m at the ends, and is surrounded by a cylindrical vacuum vessel. The first wall (FW) is 0.35 cm FS, which has a 0.1 cm thick layer of tungsten bonded to it facing the target. The FW is cooled with Li admitted at the bottom of the blanket, flows through a gap between 0.25-0.5 cm to the top, then returns through the center of the blanket channel to the bottom. There are 60 laser beam ports situated around the chamber. The tritium breeding ratio (TBR) is 1.124. A Brayton cycle is envisaged with an efficiency in the range of 42-44%.