Logo
Login Sign Up
Current Revision

ASME BPVC.III.1.NB-2025

2025 ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB, Class 1 Components
Best Price Guarantee
5-10 Days

$1,030.00


Sub Total (1 Item(s))

$ 0.00

Estimated Shipping

$ 0.00

Total (Pre-Tax)

$ 0.00


View in Library
or
American Society of Mechanical Engineers Logo

ASME BPVC.III.1.NB-2025

2025 ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NB, Class 1 Components

PUBLISH DATE 2025
ASME BPVC.III.1.NB-2025
The purpose of ASME BPVC.III.1.NB-2025 is to define the mandatory rules and requirements for the material, design, fabrication, examination, testing, and overpressure protection of Class 1 components in nuclear power facilities.
What It Is Used For This document is a major subsection of the ASME Boiler and Pressure Vessel Code (BPVC) Section III, Division 1, which governs the construction of nuclear facility components. It is used by manufacturers, constructors, designers, and regulatory bodies worldwide to ensure the highest level of structural integrity and safety for the most critical parts of a nuclear reactor system. The "Class 1" designation means these are components whose failure would lead to a loss of reactor coolant or a primary coolant boundary rupture. They operate under the most severe conditions and require the most stringent quality assurance and design methods. Its primary uses are:
  • Reactor System Components: It applies directly to pressure-retaining components that form the primary boundary of the reactor coolant system, which typically includes the:
    • Reactor Vessel (or Reactor Pressure Vessel).
    • Major primary piping.
    • Pressurizers and Steam Generators (for certain reactor types).
    • Pumps and Valves directly connected to the reactor coolant system.
  • Design-by-Analysis (DBA): Unlike most industrial codes that rely on simple design-by-rule formulas, Subsection NB mandates advanced stress analysis techniques to evaluate all potential failure modes, including primary stresses, secondary stresses, and peak stresses, often requiring a comprehensive Fatigue Analysis to account for thermal and pressure cycles over the plant's lifetime.
  • Quality and Integrity: It establishes detailed requirements for all phases of construction, including non-destructive examination (NDE), welding procedures (referencing Section IX), and testing to assure the structural integrity of the items throughout their service life.
In short, BPVC.III.1.NB is the technical rulebook for constructing the heart of a nuclear power plant—the equipment and systems that are absolutely essential for maintaining containment and controlling the nuclear fission process.
SDO ASME: American Society of Mechanical Engineers
Document Number BPVC.III.1.NB
Publication Date July 1, 2025
Language en - English
Page Count
Revision Level
Supercedes
Committee
Loading...

Failed to load document history.

Publish Date Document Id Type View