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ASME BPVC.XI.2-2025

2025 ASME Boiler and Pressure Vessel Code, Section XI, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor Facilities
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ASME BPVC.XI.2-2025

2025 ASME Boiler and Pressure Vessel Code, Section XI, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor Facilities

PUBLISH DATE 2025
ASME BPVC.XI.2-2025
The purpose of ASME BPVC.XI.2-2025 is to establish the mandatory Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor Facilities. This division provides a risk-informed, performance-based framework for maintaining the safety of advanced and non-light-water reactors during operation.
What It Is Used For This document, ASME Section XI, Division 2, is a modern, "technology-neutral" addition to the Code, developed primarily to address the operational and in-service inspection (ISI) needs of advanced reactor designs (such as Liquid Metal, Gas-Cooled, and Molten Salt reactors) whose components experience degradation mechanisms different from those in traditional Light-Water Reactors (LWRs). Its primary uses are:
  • Risk-Informed Inservice Management: It mandates the creation of a Reliability and Integrity Management (RIM) Program that systematically evaluates all Structures, Systems, and Components (SSCs) based on their risk and reliability goals. This focuses resources on the components most critical to safety and plant availability.
  • Technology Neutrality: Unlike Division 1 (which is focused on LWRs), Division 2's RIM approach can be applied to all reactor types, including advanced, small modular, and non-light-water designs. This is achieved by requiring the owner to identify and manage the degradation mechanisms specific to their reactor technology (e.g., creep, corrosion from liquid metals, or irradiation effects on novel materials).
  • Monitoring and NDE (MANDE): It requires the determination and implementation of Monitoring and Non-Destructive Evaluation (MANDE) strategies, with the scope and frequency of inspections driven by the SSC’s expected degradation rate and its allocated reliability target.
  • Life Cycle Management: The RIM Program is designed to be a "living program" applied over the entire operating life of the plant, continuously updated based on operational experience and new inspection data to assure continued long-term safety.
In summary, BPVC.XI.2 is the advanced operational code that ensures passive component reliability and integrity in next-generation nuclear facilities by using a modern, risk-based approach tailored to the unique technical challenges of advanced reactor designs.
SDO ASME: American Society of Mechanical Engineers
Document Number BPVC.XI.2
Publication Date July 1, 2025
Language en - English
Page Count
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Publish Date Document Id Type View
July 1, 2025 ASME BPVC.XI.2-2025 Revision