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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
Pekka Jauho, Lasse Mattila
Nuclear Technology | Volume 16 | Number 3 | December 1972 | Pages 472-478
Technical Paper | Reactor | doi.org/10.13182/NT72-A31216
Articles are hosted by Taylor and Francis Online.
A versatile computer program is used to investigate the effects of variation in several essential reactor plant operation parameters, such as coolant leakage rates, reactor power history, and the amount and date of organized release, on the distribution of tritium in the primary system process waters of a WWER-type pressurized water power reactor plant. All the primary process waters ultimately reach a tritium saturation activity of ∼1.5 µCi/cm3 if no organized release is employed. An annual organized release of about one primary circuit water volume is needed to keep the maximum process water tritium activities encountered during an operation year below 0.5 µCi/cm3. The date of the annual release period usually has a rather slight effect on process water maximum activities. Hence, the date for release may be chosen so that, for example, the accompanying release of fission and corrosion product activities is minimized.