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Conference Spotlight
2025 ANS Winter Conference & Expo
November 8–12, 2025
Washington, DC|Washington Hilton
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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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Latest News
FPoliSolutions demonstrates RISE, an RIPB systems engineering tool
The American Nuclear Society’s Risk-informed, Performance-based Principles and Policy Committee (RP3C) has held another presentation in its monthly Community of Practice (CoP) series. Former RP3C chair N. Prasad Kadambi opened the October 3 meeting with brief introductory remarks about the RP3C and the need for new approaches to nuclear design that go beyond conventional and deterministic methods. He then welcomed this month’s speakers: Mike Mankosa, a project engineer at FPoliSolutions, and Cesare Frepoli, the company’s president, who together presented “Introduction to RISE: A Digital Framework for Maintaining a Risk-Informed Safety Case for Current and Next Generation Nuclear Power Plants.”
Watch the full webinar here.
Xiang Wang (Harbin Eng Univ), Chunyu Liu, Rafael Macián-Juan (Technical Univ of Munich)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 460-468
The Dual Fluid Reactor is a molten salt fast reactor developed by IFK (Institut fuer Festkoerper-Kernphysik) based on the Gen-IV Molten-Salt Reactor (MSR) and the Liquid-Metal Cooled Reactor (SFR, LFR) concepts. This analysis report focuses on the comparison between previ-ous coupled calculations of the system with the default fuel salt of U-Pu mixture and new one with a transurani-um (TRU) fuel salt option. An approach to the dynamics and stability analysis of the DFR by using the well-developed linear method with their improved modifica-tions is proposed. The coupled one-dimensional neutron-ics and thermal-hydraulic model will be established with this method. With this model the steady state and the dy-namics analysis of the system under various operational conditions are presented. The stability of the system will be also analyzed with the results in the parametric studies. The results are compared with Molten Salt Breeder Reac-tor (MSBR) and Molten Salt Fast Reactor (MSFR), which can be decisive for the future application of the DFR.
