ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
May 2025
Latest News
IAEA to help monitor plastic pollution in the Galapagos Islands
The International Atomic Energy Agency announced that its Nuclear Technology for Controlling Plastic Pollution (NUTEC Plastics) initiative has partnered with Ecuador’s Oceanographic Institute of the Navy (INOCAR) and Polytechnic School of the Coast (ESPOL) to build microplastic monitoring and analytical capacity to address the growing threat of marine microplastic pollution in the Galapagos Islands.
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.