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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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
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.
Dan Gabriel Cepraga, Gilio Cambi, Manuela Frisoni, Franca Carloni
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 691-696
Neutronics Experiments and Analysis | doi.org/10.13182/FST98-A11963695
Articles are hosted by Taylor and Francis Online.
Decay heat plays an important role in fusion plant safety. To validate the codes, data and calculation procedures used in decay heat prediction, an international benchmark exercise was launched. The calculated results have been compared with experimental ones, obtained from a series of experiments performed using the Fusion Neutronics Source (FNS) at the Japan Atomic Energy Research Institute (JAERI), Tokai, Japan. This paper presents the decay heat results for two of the most relevant fusion-related materials, the AISI 316 steel and the copper samples, obtained using the ENEA activation code ANITA-4/F and discuss their comparison with the experimental ones.
