American National Standard Design Criteria For Safe Shutdown Following Selected Design Basis Events In Light Water Reactors

This standard provides design criteria for systems that perform the safety-related functions necessary to shut down a reactor and maintain it in a safe shutdown condition for selected design-basis events, i.e., any design-basis events that do not require operation of engineered safety features. For design-basis events that require operation of engineered safety features, this standard can be selectively applied because of plant features specifically designed for these conditions. For systems that serve multiple functions, the design criteria associated with the most limiting function shall be applied. The following safety-related functions are required for safe shutdown and are addressed in this standard (1) reactor core reactivity control, (2) reactor core heat removal, (3) reactor coolant pressure boundary integrity provided by (a) temperature control, (b) pressure control, and (c) inventory control.

Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Key fluid mechanics, heat transfer, and nuclear engineering concepts are carefully explained, and supported with worked examples, tables, and graphics. Intended for use in one or two semester courses, the text is suitable for both undergraduate and graduate students. A complete Solutions Manual is available for professors adopting the text.

ANS 54.1-2020 defines safety objectives; sodium fast reactor design criteria (SFRDCs); selection criteria for licensing-basis events; and criteria for the classification of structures, systems, and components (SSCs) that can be used by designers and regulators of SFR nuclear power plants. It is intended to provide the necessary guidance to the designer in order to "bridge" the existing light water reactor-focused general design criteria (GDCs) contained in Appendix A to 10 CFR 50 and other regulatory requirements to the development of their respective principal design criteria, while retaining the underlying safety principles of the GDCs.

This standard provides design criteria for the process of consolidating light water reactor spent nuclear fuel in either a wet or dry environment. The process utilizes the equipment and systems used to perform consolidation, handle fuel rods and nonfuel-bearing components as well as handle broken fuel rods. This standard also contains requirements for facility or installation interfaces, nuclear safety, structural design, thermal design, accountability, safeguards, decommissioning, and quality assurance. The standard is not concerned with the storage of the spent fuel either before or after the consolidation process.

ANS 54.1-2020 defines safety objectives; sodium fast reactor design criteria (SFRDCs); selection criteria for licensing-basis events; and criteria for the classification of structures, systems, and components (SSCs) that can be used by designers and regulators of SFR nuclear power plants. It is intended to provide the necessary guidance to the designer in order to "bridge" the existing light water reactor-focused general design criteria (GDCs) contained in Appendix A to 10 CFR 50 and other regulatory requirements to the development of their respective principal design criteria, while retaining the underlying safety principles of the GDCs.

This standard addresses the design basis for the protection of light water reactor nuclear power plants from the potentially adverse effects of postulated pipe ruptures.