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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Risk-informed, performance-based design in INL’s MARVEL reactor
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 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 speaker: Doug Gerstner, a nuclear safety engineer at Idaho National Laboratory, who presented “Application of a Qualitative RIPB Approach for the MARVEL Microreactor at INL.”
Watch the full webinar here.
János Végh, Csaba Major, Csaba Horváth, Zoltán Hózer, Ferenc Adorján, Iván Lux, Kristóf Horváth
Nuclear Technology | Volume 139 | Number 2 | August 2002 | Pages 156-166
Technical Paper | Nuclear Plant Operations and Control | doi.org/10.13182/NT02-A3310
Articles are hosted by Taylor and Francis Online.
The main design features, services, and human-machine interface characteristics are described of the CERTA VITA on-line plant information system developed and installed by KFKI AEKI at the Nuclear Safety Directorate (NSD) of the Hungarian Atomic Energy Authority (HAEA) in cooperation with experts from the NSD. The Center for Emergency Response, Training, and Analysis (CERTA) located at the headquarters of NSD, Budapest, Hungary, was established in 1997. The center supports the NSD installation, radiological monitoring, and advisory team in case of nuclear emergencies, with appropriate hardware and software for communication, diagnosis, prognosis, and prediction. The vital information transfer and analysis (VITA) system represents an important part of the CERTA, as it provides for the continuous remote inspection of the four VVER-440/V213 units of the Hungarian Paks nuclear power plant (NPP). The on-line information system maintains a continuous data link with the NPP through a managed leased line that connects CERTA to a gateway computer located at the Paks NPP. The present scope of the system is a result of a 4-yr development project: In addition to the basic safety parameter display functions, the VITA system now includes an on-line break parameter estimation module, an extensive training package based on simulated transients, and on-line data transfer capabilities to feed accident diagnosis/analysis codes.