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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
T. Kawabe, S. Hirayama, Y. Kozaki, K. Yoshikawa, N. Asami, Y. Fukai, K. Hattori, H. Hojo, T. Honda, H. Ida, T. Kitajima, S. Koda, K. Komatsu, R. Kumazawa, F. Matsuoka, T. Miyasugi, N. Morino, H. Nakashima, H. Nakata, S. Sato, Y. Uede, T. Watanabe, M. Yamada, Y. Yamamoto, H. Yamato
Fusion Science and Technology | Volume 10 | Number 3 | November 1986 | Pages 1102-1110
Nuclear Technology Experiments and Facilities | doi.org/10.13182/FST86-A24880
Articles are hosted by Taylor and Francis Online.
Conceptual design study of 14-MeV neutron source (FEF) of compact DT plasma based on the mirror confinement has been carried out to clarify the critical issues both in plasma physics and engineering. Characteristic feature of FEF-II are (i) use of RF pondermotive force for MHD stability, (ii) use of water for radiation shield of SC coil and (iii) use of end electrode system including plasma direct energy conversion. Several sets of plasma parameters are obtained under the variety of conditions from the most pessimistic case where the charge exchange (CX) loss of ions is dominant to the most optimistic case where the CX loss is negligible. The engineering feasibility has been studied for the pessimistic case. It was found that most of the engineering are feasible in the optimistic case, and that even in the pessimistic case by increasing plasma parameters there is possibility to meet engineering requirement.
