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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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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.
Daniel Cubicciotti, Bal Raj Sehgal
Nuclear Technology | Volume 67 | Number 2 | November 1984 | Pages 191-207
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33510
Articles are hosted by Taylor and Francis Online.
The vaporization of core materials other than fission products during a postulated severe light water reactor accident is treated by chemical thermodynamics. The core materials considered were (a) the control rod materials, silver, cadmium, and indium; (b) the structural materials, iron, chromium, nickel, and manganese; (c) cladding material, zirconium and tin; and (d) the fuel, uranium oxide. Thermodynamic data employed for the solid and gaseous elements and oxides were based on measurements, while the data for the gaseous hydroxides were generally based on estimates from literature. Thermodynamic criteria were derived to determine whether the metallic element or the solid oxide was the stable condensed phase for the accident environmental conditions. Equations for the partial pressures for all gaseous species were also derived. The relevant environmental conditions were provided by the pressurized water reactor and boiling water reactor heat-up thermal-hydraulic codes. The volatilities of the core materials were found to decrease roughly in the following order: cadmium, indium, tin, iron, silver, manganese, nickel, chromium, uranium, and zirconium. Cadmium and indium would provide the largest mass of core material that can be transported out of the core.