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Division Spotlight
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.
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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March 2025
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February 2025
Latest News
RP3C Community of Practice’s fifth anniversary
In February, the Community of Practice (CoP) webinar series, hosted by the American Nuclear Society Standards Board’s Risk-informed, Performance-based Principles and Policies Committee (RP3C), celebrated its fifth anniversary. Like so many online events, these CoPs brought people together at a time when interacting with others became challenging in early 2020. Since the kickoff CoP, which highlighted the impact that systems engineering has on the design of NuScale’s small modular reactor, the last Friday of most months has featured a new speaker leading a discussion on the use of risk-informed, performance-based (RIPB) thinking in the nuclear industry. Providing a venue to convene for people within ANS and those who found their way online by another route, CoPs are an opportunity for the community to receive answers to their burning questions about the subject at hand. With 50–100 active online participants most months, the conversation is always lively, and knowledge flows freely.
O. K. Tallent, James C. Mailen, David O. Campbell, S. R. Buxton
Nuclear Technology | Volume 60 | Number 3 | March 1983 | Pages 395-405
Technical Paper | LWR Control Materials—I and II / Chemical Processing | doi.org/10.13182/NT83-A33126
Articles are hosted by Taylor and Francis Online.
Dissolution tests using ThO2 microspheres, ThO2 pellets, and Zircaloy tubing were performed to establish conditions that can be used for the selective dissolution of thoria from Zircaloy cladding. Although additional work is needed in several areas, the following conditions are tentatively recommended for use in process demonstration tests: 0.02 to 0.04 M HF in refluxing 8 to 12 M HNO3 with sufficient Al3+, or (preferably) Zr4+, added to prevent major corrosion of the stainless steel dissolver vessel. If Zr4+ is used, the concentration required is approximately the same molarity as the fluoride concentration.
