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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.
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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Fusion Science and Technology
Latest News
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.
M. Sawan, L. El-Guebaly, P. Wilson
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 763-770
Technical Paper | Nuclear Analysis and Experiments | doi.org/10.13182/FST07-A1582
Articles are hosted by Taylor and Francis Online.
Detailed three-dimensional nuclear analyses have been carried out for the chamber of a power plant concept that utilizes the Z-Pinch driven inertial confinement technology with a target yield of 3 GJ and repetition rate of 0.1 Hz per chamber. The elliptical chamber concept was modeled with the double-layered Recyclable Transmission Lines (RTL). Thick liquid jets are utilized to breed tritium, absorb energy, and shield the chamber wall. Two liquid breeder options were considered; the molten salt Flibe and the LiPb eutectic (Li17Pb83). The chamber wall is made of the low activation ferritic steel alloy F82H. While both breeders have the potential for achieving tritium self-sufficiency, the thermal power is ~6.5% higher with LiPb. However, a 55% thicker jet zone is required with LiPb to provide adequate chamber wall shielding. A thicker chamber wall is required with LiPb to reduce the nuclear energy leakage below 1%. The chamber wall does not need replacement except for the top part around the jet nozzles. Helium production in the chamber wall protected by LiPb is much lower than that with Flibe. Rewelding is possible only in the lower part of chamber wall below the pool.