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Division Spotlight
Mathematics & Computation
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.
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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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.
A. Kimura
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 480-484
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST03-A382
Articles are hosted by Taylor and Francis Online.
The US/Japan collaboration (Japan-US Program of Irradiation Tests for Fusion Research: JUPITER) has been effective in accumulating an irradiation database and in understanding the mechanism of irradiation effects of reduced activation ferritic steels (RAFS). The irradiation data obtained up to now indicates rather high feasibility of ferritic steel for application to fusion reactors, because of their high resistance to degradation of material performance by both the displacement damage and helium. The martensitic structure of the RAFS consists of a kind of lattice defects before the irradiation, such as dislocations, lath boundaries, precipitates and carbides, which strongly reinforce the resistance to displacement damages through absorption and annihilation of the point defects generated by the irradiation. Transmutation helium can be trapped at those defects in the martensitic structure so that the formation of helium clusters at grain boundaries, which causes intergranular embrittlement, is suppressed. The martensitic structure of the RAFS is considered to be appropriate for fusion structural material. Efforts to increase high temperature strength have been made for RAFS.
