ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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The development of modern nuclear reactor technologies relies heavily on complex software codes and computer simulations to support the design, construction, and testing of physical hardware systems. These tools allow for rigorous testing of theory and thorough verification of design under various use or transient power scenarios.
Educational Session|Panel|Sponsored by Risk Management
Tuesday, August 11, 2020|12:00–1:30PM EDT
Gene Kelly (Exelon)
Timothy Crook (MCR Group)
Robby Christian (INL)
There are substantial benefits and good reasons for incorporating and crediting FLEX equipment in industry PRA models, for all hazard types (not just seismic and external flooding). Reactor safety is improved by allowing operators the flexibility to use FLEX in a variety of scenarios - not just in beyond design basis external event scenarios, which are the subject of the previously issued Mitigation Strategies under Order EA-12-049. The benefits of crediting FLEX - both in procedures and in PRA models, and for risk applications (such as RICT and SDP cases) - outweigh any potential regulatory uncertainties. The NRC’s recent enforcement policy found in Inspection Manual Chapter (IMC) 0609 Appendix A was recently reconsidered for FLEX equipment deficiencies, both in how these are screened, and in how the cases would be quantified (i.e., which hazard models are used) when performing more detailed significance analysis. FLEX component reliabilities and associated deployment actions (HRA) are evolving and being closely studied and evaluated by industry and the NRC. In the meantime, our models should reasonably reflect the as-built/as-operated plant, as required by the ASME Standard and Regulatory Guide 1.200. The option to deploy FLEX strategies is an important defense in depth measure in any/all scenarios when an extended loss of power is present, and is an improvement in reactor safety. It’s acknowledgement in PRA models should not be discouraged or unduly challenged.
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Reference — FLEX Speaker Bios
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