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Advanced Reactor Research
The NRC's advanced reactor research applies principally to six of the
reactors listed above. They are as follows: AP1000, ACR-700, ESBWR, PBMR,
GT-MHR and IRIS.
Several technical topics and activities were identified and linked to
nine key research areas:
- framework (including the development of regulatory decision-making tools based on the risk-informed, performance-based principles)
- accident analysis (including probabilistic risk assessment (PRA) methods and assessments, human factors, and instrumentation and control)
- reactor/plant systems analysis (including thermal-fluid dynamics, nuclear analysis, and severe accident and source term analysis)
- fuels analysis and testing
- materials analysis (including graphite behavior and high-temperature metal performance)
- structural analysis (including containment/confinement performance and external challenges)
- consequence analysis (including dose calculations, and environmental impact studies)
- nuclear materials safety (including enrichment, fabrication, and transport) and waste safety (including storage, transport, and disposal), and
- nuclear safeguards and security
Not all the research described within this document will be done by the
NRC. Information can and will be obtained through domestic and international
cooperation, as well as through research and development conducted by
promoters of the designs.
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