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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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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Nuclear Technology
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.
Eriko Jotaki, Satoshi Itoh
Fusion Science and Technology | Volume 32 | Number 3 | November 1997 | Pages 487-492
Technical Paper | doi.org/10.13182/FST97-A10
Articles are hosted by Taylor and Francis Online.
A new data acquisition and analysis system for unexpected, rapid changes in plasma parameters has been developed. The scheme is designed for the high-temperature plasmas of long-time tokamak operation. The post trigger samples of conventional computer-automated measurement and control modules are utilized during a sudden event. The scheme of the method is described. This method is applied to the long discharges of the TRIAM-1M tokamak. The system works well for an unexpected and rapid termination of a discharge and could provide desired data. It is demonstrated that a new system with proper monitoring can track the unexpected, rapid changes in plasma parameters.
