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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
NRC restores expiration dates for renewed Turkey Point licenses
The Nuclear Regulatory Commission announced this week that it has restored the expiration dates of the Turkey Point nuclear power plant's units 3 and 4 subsequent license renewals (SLR) to July 19, 2052, and April 10, 2053, respectively.
Stephanie G. Smith, Ronald E. Johnson, Joan M. Miller
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1420-1424
Tritium Storage, Distribution, and Transportation | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30611
Articles are hosted by Taylor and Francis Online.
Extensive experience with the refilling of the Amersham Mk IV 1.85 PBq uranium pots has shown that helium-3 resident in the uranium matrix causes “blanketing” of the metal surface and subsequent operational problems. This paper reviews the operational procedures and results observed at Ontario Hydro's dispensing facilities. Experimental work performed to investigate the effect of this helium-3 on the reuse of the Amersham Mk IV pots demonstrated the necessity of an operational ability to evacuate the uranium pot at stages during the tritium transfer, without affecting the quantitative transfer measurement.