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ASME BPVC.III.5-2025

2025 ASME Boiler and Pressure Vessel Code, Section III, Division 5, High Temperature Reactors
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ASME BPVC.III.5-2025

2025 ASME Boiler and Pressure Vessel Code, Section III, Division 5, High Temperature Reactors

PUBLISH DATE 2025
ASME BPVC.III.5-2025
The purpose of ASME BPVC.III.5-2025 is to define the specialized construction rules for High Temperature Reactors (HTRs) and their components that operate at temperatures high enough for time-dependent material failure mechanisms, such as creep, to become significant.
What It Is Used For This document, ASME Section III, Division 5, is essential for the design and construction of advanced reactor concepts, which often use non-light-water coolants (like gas or liquid metal) that operate at temperatures far exceeding the limits of conventional nuclear construction codes (Division 1). Division 5 addresses the unique challenges of operating in the creep regime. Its primary uses are:
  • Construction of High-Temperature Components: It governs the design of vessels, piping, pumps, valves, and core components where the metal temperatures exceed the limits of Division 1 (typically 700 ∘ F (370 ∘ C) for ferritic steel and 800 ∘ F (425 ∘ C) for stainless steel). Reactor types covered include High-Temperature Gas-Cooled Reactors (HTGRs) and Liquid Metal Reactors (LMRs).
  • Creep Analysis and Time-Dependent Design: It includes specific metallic design criteria to guard against elevated temperature failure modes like creep rupture, excessive deformation, and creep-fatigue interaction. This requires designers to consider not just stress, but also the total operating time and temperature in their calculations.
  • Nonmetallic Core Components: It contains specialized rules (such as Subsection HH for nonmetallic core components) for the use of materials like graphite, which is commonly used in high-temperature gas-cooled reactor cores. These rules account for the probabilistic nature of nonmetallic material strength and the effects of irradiation.
  • Advanced Design Methodology: It incorporates sophisticated analysis techniques, including Elastic, Perfectly Plastic (EPP) analysis, to accurately predict component behavior and ensure structural integrity over the plant's entire intended service life, often extending beyond 40 years.
In essence, BPVC.III.5 is the enabling code for advanced nuclear power technology, allowing next-generation reactors to be constructed safely and efficiently at elevated temperatures for improved efficiency and industrial process heat applications.
SDO ASME: American Society of Mechanical Engineers
Document Number BPVC.III.5
Publication Date July 1, 2025
Language en - English
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