American National Standard
American National Standard

Author: American Nuclear Society. Standards Committee Working Group ANS-57.1

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ANS 57.1-1992 (R2019) sets forth the required functions of fuel handling systems at light water reactor nuclear power plants. It provides minimum design requirements for equipment and tools to handle nuclear fuel and control components safely.

American National Standard
American National Standard

Author: American Nuclear Society. Standards Committee Working Group ANS-57.2

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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.

American National Standard
American National Standard

Author: American Nuclear Society. Standards Committee Working Group ANS-57.10

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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.

American National Standard
American National Standard

Author: American Nuclear Society. Working Group ANS-58.9

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ANS 58.9-1981 (R2020) provides criteria for the designer which interpret the requirements of Title 10, Code of Federal Regulations, Part 50, "Licensing of Production and Utilization Facilities," Appendix A, "General Design Criteria for Nuclear Power Plants," with respect to design against single failures in safety-related Light Water Reactor (LWR) fluid systems. Means of treating both active and passive failures are addressed for safety-related fluid systems following various initiating events. Current acceptable practice is used as a basis for these criteria.