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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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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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Fusion Science and Technology
November 2024
Latest News
Siting of Canadian repository gets support of tribal nation
Canada’s Nuclear Waste Management Organization (NWMO) announced that Wabigoon Lake Ojibway Nation has indicated its willingness to support moving forward to the next phase of the site selection process to host a deep geological repository for Canada’s spent nuclear fuel.
Kim Burns, Ed Love, Monte Elmore
Fusion Science and Technology | Volume 71 | Number 4 | May 2017 | Pages 544-548
Technical Paper | doi.org/10.1080/15361055.2017.1291038
Articles are hosted by Taylor and Francis Online.
Currently there are large uncertainties associated with the source of tritium in a Pressurized Water Reactor (PWR) Reactor Coolant System (RCS). The measured amount of tritium in the coolant cannot be separated out empirically into its individual sources. Therefore, all sources of tritium in the RCS of a PWR must be understood theoretically. One potential source of tritium in the RCS is due to tritium production in secondary sources. Neutron sources provide a flux of neutrons that are used to support reactor startup. Primary startup neutron source rods made of 252Cf are inserted into the reactor during the first cycle of a new nuclear reactor. The primary neutron sources are used to produce enough neutrons through spontaneous fission to create a sufficient neutron flux to be seen by the ex-core neutron detectors and facilitate reactor startup. Antimony-Beryllium secondary startup neutron sources are also inserted in the first reactor cycle to provide a neutron source for startups in future cycles. The Beryllium in the secondary sources is a source of tritium when irradiated in a neutron flux. This paper will discuss tritium produced within the secondary sources.