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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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
Vogtle-3 shuts down for valve issue
One of the new Vogtle units in Georgia was shut down unexpectedly on Monday last week for a valve issue that has since been investigated and repaired. According to multiple local news outlets, Georgia Power reported on July 17 that Unit 3 was back in service.
Southern Company spokesperson Jacob Hawkins confirmed that Vogtle-3 went off line at 9:25 p.m. local time on July 8 “due to lowering water levels in the steam generators caused by a valve issue on one of the three main feedwater pumps.”
Hirokazu Yamada, Kunihiko Tsuchiya, Masaru Nakamichi, Hiroshi Kawamura
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 602-606
Fusion Materials | doi.org/10.13182/FST01-A11963303
Articles are hosted by Taylor and Francis Online.
The effects of neutron irradiation on tensile properties of the Cu alloys to type 316 stainless steel (SS316LN-IG) joints fabricated by friction welding method were examined. Additionally, irradiation tests of Al2O3-dispersed copper alloy (Al-25) and SS316LN-IG were conducted. The Al-25/ SS316LN-IG joints were irradiated in the Japan Materials Testing Reactor (JMTR), and tension tests and metallographical observation of these joints have been performed as the post irradiation examination (PIE). In the tension tests of Al-25/SS316LN-IG joints, all irradiated specimens fractured at the copper sides. In the tension tests at 293K, tensile strength of the Al-25/ SS316LN-IG joints irradiated at each temperature was almost similar to that of the base metal (Al-25) irradiated in the same condition. On the other hand, tensile strength of Al-25/ SS316LN-IG joints was smaller than that of Al-25 in the tension tests at the same temperature as each irradiation temperature. In this study, useful data of the irradiated Al-25/ SS316LN-IG joints fabricated by friction welding method were obtained to design fusion reactors.