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Launching into tomorrow: NRIC guides new era of research and deployment
In June 2025, the Department of Energy announced the Reactor Pilot Program, an authorization pathway that allowed reactor developers to partner with the DOE to get first-of-a-kind (FOAK) reactors built and tested. Soon after, the DOE rolled out a complementary Fuel Line Pilot Program, which aimed to fast-track fuel projects. In all, 20 projects were accepted into the new programs.
Arndt B. Lindner, Dieter H. Wach
Nuclear Technology | Volume 143 | Number 2 | August 2003 | Pages 197-207
Technical Paper | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies | doi.org/10.13182/NT03-A3409
Articles are hosted by Taylor and Francis Online.
Operational benefits and enlarged functionality of modern technology, but also the physical and the technological aging of conventional instrumentation and control (I&C) systems, are motivations for modernization of I&C systems in nuclear power plants (NPPs). In case of safety-relevant I&C systems, the licensing authorities require the demonstration of sufficient safety of the systems.In several countries ongoing research and development projects are directed to provide a scientific basis and engineering solutions for cost-effective assessment of software-based I&C systems important to safety in NPPs. International initiatives have been started to develop a harmonized safety assessment methodology. The Institute for Safety Technology (ISTec) has been engaged in national and international programs as well as in establishing a two-phase qualification approach, which comprises a generic plant-independent qualification of hardware and software components and a plant-specific system qualification phase.In both generic qualification and plant-specific system qualification, ISTec has been involved as an independent third-party assessor for the relevant state authority. This paper reports experiences from the ISTec involvement in the assessment projects, e.g., in the assessment of the I&C important to safety in the new German High-Flux Research Reactor (FRM-2) in Munich and in the assessments of I&C modernization in NPPs of foreign countries (Bohunice, Slovak Republic; Paks, Hungary; and others). Conclusions are drawn from the experiences with respect to the practicability of the two-phase qualification concept and from the major findings in the plant-specific I&C assessments.