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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.
M. Roedig, V. Barabash, R. Eaton, T. Hirai, I. Kupriyanov, J. Linke, X. Liu, A. Schmidt, Zh. Wang
Fusion Science and Technology | Volume 62 | Number 1 | July-August 2012 | Pages 16-20
PFC and FW Materials Issues | Proceedings of the Fifteenth International Conference on Fusion Reactor Materials, Part A: Fusion Technology | doi.org/10.13182/FST12-A14105
Articles are hosted by Taylor and Francis Online.
In order to qualify new beryllium grades for ITER, several Russian and Chinese materials were tested in the electron beam facility JUDITH-1 and compared to the reference material S65C. In a former campaign, samples from these materials were loaded in thermal shock experiments with single shots and multiple shots. The present work is an extension of this work to other loading scenarios.Four actively cooled mock-ups were produced in Russia and in China (two by each party). These mock-ups consisted of a water-cooled CuCrZr body with four tiles from different beryllium grades. Both parties used their own joining techniques, but each of the mock-ups also contained beryllium tiles from the other party, as well as from S65C.Each tile was loaded by the following scenarios on different surface areas:• simulation of vertical displacement events (VDEs) at 40 MJ/m2, 1 shot, heated area a = 10 × 10 mm2, 50-ms ramp-up, 165-ms steady state• disruption simulation at 3 MJ/m2, 1 shot, heated area a = 5 × 5 mm2, t = 5 ms• repetitive test with 1000 shots at 80 MW/m2 (2 MJ/m2), a = 10 × 10 mm2, t = 25 ms. This loading condition is similar to one that was proposed by Sandia National Laboratory for the comparison of different beryllium grades.Finally, one mock-up by each party underwent a thermal fatigue test with 1000 cycles at 2 MW/m2, 15 s heating, and 15 s cooling (heated area: whole sample surface). Heavy melting was observed in the area of the VDE loading, but no detachment of any of the tiles was found. Following the high-heat-flux experiments in the electron beam facility, post-mortem examinations were performed by optical photography and scanning electron microscopy on the surfaces as well as by metallography. From these analyses, no fundamental differences were found for the damage in the different beryllium grades.