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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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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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.
Norbert Eickelpasch, Reinhard W. Seepolt, Johann Müllauer, Werner Spalthoff
Nuclear Technology | Volume 60 | Number 3 | March 1983 | Pages 362-366
Technical Paper | LWR Control Materials—I and II / Fission Reactor | doi.org/10.13182/NT83-A33123
Articles are hosted by Taylor and Francis Online.
The control rods of the KRB-I 250-MW(electric) boiling water reactor contain Vipac B4C powder in Type 304 stainless steel tubes as a neutron-absorbing material Because of an increase in the reactor coolant 3H activity, defective control rods were suspected. The hot cell examination of a highly exposed control rod revealed B4C losses. The mechanism of failure was shown to be B4C swelling and stress corrosion cracking of the absorber tubes, followed by B4C washout. The B4C volume swelling is ΔV(%) = 0.851x + 0.0449x2 [x = 10B decays in 1021(n,α)/cm3]. The tube cracking starts at 30 to 35% and the B4C washout at 50 to 55% local 10B burnup in the tubes.
