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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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Fusion Science and Technology
Latest News
Construction begins on Kairos’s fluoride salt–cooled test reactor
Earlier today, on a site in Oak Ridge, Tenn., that was formerly home to the K-33 Gaseous Diffusion Plant, Kairos Power marked the start of construction on its low-power demonstration reactor. Named Hermes, the 35-MWt test reactor claims status as the first Gen IV reactor to be approved for construction by the Nuclear Regulatory Commission and the first non–light water reactor to be permitted in the United States in more than 50 years.
Alexander Antipenkov, Christian Day, Hans-Dieter Adami
Fusion Science and Technology | Volume 54 | Number 1 | July 2008 | Pages 35-38
Technical Paper | Iter and Fusion | doi.org/10.13182/FST08-A1760
Articles are hosted by Taylor and Francis Online.
The ferrofluidic seal is being investigated as an internal rotary seal for tritium compatible mechanical roots type vacuum pumps. After its successful testing with helium and integration into a small (250 m3/h) test roots pump, the seal, made as a cartridge, has been integrated into a special test unit and is currently being tested with tritium in order to define the leak rates and the possible degradation of the ferrofluid under long term exposure to tritium radiation. The tritium pressure from one side of the seal is 0.125 MPa, the nitrogen pressure from the other side is 0.075 MPa, the rotation speed is maintained at 1500 rpm. The tritium leak through the cartridge contributes to the tritium concentration in the nitrogen, which is continuously measured by an ionisation chamber; the pressure in both chambers is continuously registered by precise pressure gauges. The experimental program is discussed.