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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
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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.
Hiroyuki Nakaharai, Takahiro Chuman, Takehiko Yokomine, Shinji Ebara, Akihiko Shimizu
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 364-368
Technical Paper | Fusion Energy - Tritium and Safety and Environment | doi.org/10.13182/FST03-A361
Articles are hosted by Taylor and Francis Online.
The safety analysis on LOVA is among the last task left in ITER R&D. On the assumption of LOVA after ICE, it is corollary that activated dusts are under wet condition. The transport behavior of dust under the wet condition is not known well in comparison with dry case even in the conventional engineering systems. Moreover, in the case of LOVA after ICE a shock wave is assumed to generate in the vacuum vessel. The purpose of this experimental study is to investigate the dust behavior under the wet condition including the interaction between shock wave and dust by supposition of LOVA. In this experiment, entrainment ratio and adhesion ratio of dust are measured and discussed. Thereby we understood the behavior of dust in the wet condition and report it.