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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
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 News 40 under 40
Welcome to the inaugural Nuclear News 40 Under 40! A year in the making, this list was a difficult undertaking for the NN staff, there being so many qualified and enthusiastic candidates to review. The task was further complicated by the great diversity of roles that exist within the nuclear community—from academia to labs and from utilities to government positions. Whatever their specific niche, those selected represent the exceptional talent, vision, and drive that is transforming the nuclear sector across the community. These 40 young professionals have shown remarkable commitment, innovation, and leadership in advancing nuclear science and technology, paving the way for a future in which nuclear power and applications will continue to play a vital role in addressing global challenges.
E. Wakai, T. Kikuchi, T. Yokomine, M. Yamamoto, M. Soldaini, A. Polato
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 246-251
IFMIF | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14142
Articles are hosted by Taylor and Francis Online.
International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activity (IFMIF/EVEDA) was started in 2007 in the joint program between Japan (JA) and the European Union (EU). IFMIF has mainly three facilities, i.e., test facility, lithium target facility, and accelerator facility. In this program, there are three subjects of the JA team in the test facility such as the design of the post irradiation examination (PIE) facility, the design and validation of the high flux test module, and the evaluation of the small size specimen technique. In this paper, the test matrix of the IFMIF was evaluated. All test matrixes depend on the requirement of a database preparation schedule and the irradiation volume of irradiation modules such as high flux test module (HFTM), medium flux test module (MFTM) and low flux test module (LFTM), but the engineering design of HFTM is mainly proceeding. Accordingly, the lists of the experiments of small size specimens set in the HFTM to be performed in the PIE laboratories have been carefully analyzed. In the design of HFTM, two types of HFTM are proposed for RAFM steel irradiation by the EU KIT team and for the advanced materials by the JA team, and the difference was summarized.