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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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Latest News
Blades-in turbine inspections at Quad Cities set new benchmark for Constellation
When Constellation decided to install replacement Alstom low-pressure turbines at three of its boiling water reactor plants more than 15 years ago, one benefit was knowing the new turbines should operate reliably—and without major inspections—for several years.
Masashi Shimada, Yasuhisa Oya, Dean A. Buchenauer, Yuji Hatano
Fusion Science and Technology | Volume 72 | Number 4 | November 2017 | Pages 652-659
Technical Paper | doi.org/10.1080/15361055.2017.1347468
Articles are hosted by Taylor and Francis Online.
Irradiation effects on heat-load and heat removal, thermo-mechanical properties, and tritium behavior in neutron-irradiated tungsten and tungsten alloy are being investigated under US-Japan PHENIX (Plasma facing components evaluation by tritium Plasma, HEat and Neutron Irradiation eXperiments) collaboration (2013–2018) to demonstrate feasibility and safety of helium-cooled divertor concept for a fusion demonstration (DEMO) and future fusion reactors. The PHENIX Task 3 is aimed at improved understanding of irradiation response on tritium retention and permeation in tungsten and tungsten alloys under divertor-relevant high-flux plasma for a Fusion Nuclear Science Facility (FNSF) and DEMO. This paper describes the challenge in elucidating tritium behavior in neutron-irradiated plasma facing components (PFCs), the PHENIX plans for neutron-irradiation and post irradiation examination, and progress in tritium behavior in neutron-irradiated tungsten.
