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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
L. El-Guebaly, P. Wilson, D. Henderson, L. Waganer, R. Raffray, ARIES Team
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 405-409
Technical Paper | Fusion Energy - Tritium and Safety and Environment | doi.org/10.13182/FST03-A368
Articles are hosted by Taylor and Francis Online.
Heavy ion beam driven inertial fusion energy (IFE) power plants employ liquid wall materials to protect the structure against the energetic x-rays, ions, and debris emitted from the target following each shot. The objective of this assessment is to identify the radiological issues of the candidate liquid wall materials (Pb, LiPb, Sn, and Flibe) using the ARIES-IFE radiation chamber environment. The issues to be addressed include the radioactivity level and liquid waste minimization for waste management. Specifically, the liquids are evaluated with regard to the Class C limitation for waste disposal, a top-level requirement for all ARIES power plant designs. Two extreme cases were analyzed; the worst case is separation of the liquid wall material (highest radiation exposure) and the breeder (lowest radiation exposure), and the best case is the mixing of the two liquid streams. Both tangential and porous wall injection schemes were examined. Pb and LiPb are more radioactive than Sn and Flibe. For the liquid breeder system, the porous wall injection scheme with mixed liquid flows results in the lowest waste disposal rating and smallest waste stream achieved in our study.
