ASME BPVC Section II, Part C: Specifications for Welding Rods, Electrodes, and Filler Metals, 2023
ASME BPVC Section II, Part C – 2023 compiles welding consumable specifications used in the fabrication of pressure-retaining components under the ASME Boiler and Pressure Vessel Code. Aligned with American Welding Society (AWS) standards, this section ensures consistency in filler metal classification, procurement, and application.
Highlights:
- Incorporates AWS specifications (SFA-5.1 to SFA-5.39) for ferrous and nonferrous welding consumables
- Covers carbon steel, stainless steel, aluminum, nickel, copper, titanium, and specialty alloys
- Details for flux cored, metal cored, submerged arc, electroslag, and gas-shielded welding processes
- Includes brazing filler metal and flux specifications
- Establishes procurement, testing, and certification requirements for compliance and traceability
- Appendices cover lot classification, testing frequencies, labeling, packaging, and documentation
- Fully cross-referenced with ASME Section IX for welding procedure and performance qualification
- Reflects updates to AWS standards and ongoing international harmonization efforts
Who It’s For:
Welding engineers, QA/QC inspectors, fabricators, and material procurement professionals responsible for code-compliant pressure equipment fabrication.
BPVC.II.C-2023
ASME BPVC Section II, Part C: Specifications for Welding Rods, Electrodes, and Filler Metals, 2023
ASME BPVC Section II, Part C – 2023 compiles welding consumable specifications used in the fabrication of pressure-retaining components under the ASME Boiler and Pressure Vessel Code. Aligned with American Welding Society (AWS) standards, this section ensures consistency in filler metal classification, procurement, and application.
Highlights:
- Incorporates AWS specifications (SFA-5.1 to SFA-5.39) for ferrous and nonferrous welding consumables
- Covers carbon steel, stainless steel, aluminum, nickel, copper, titanium, and specialty alloys
- Details for flux cored, metal cored, submerged arc, electroslag, and gas-shielded welding processes
- Includes brazing filler metal and flux specifications
- Establishes procurement, testing, and certification requirements for compliance and traceability
- Appendices cover lot classification, testing frequencies, labeling, packaging, and documentation
- Fully cross-referenced with ASME Section IX for welding procedure and performance qualification
- Reflects updates to AWS standards and ongoing international harmonization efforts
Who It’s For:
Welding engineers, QA/QC inspectors, fabricators, and material procurement professionals responsible for code-compliant pressure equipment fabrication.
BPVC.II.C-2023
ASME BPVC Section III, Division 1, Subsection NB: Rules for Class 1 Nuclear Facility Components, 2023
ASME BPVC Section III, Division 1, Subsection NB provides mandatory construction rules for Class 1 pressure-retaining components in nuclear power facilities. Recognized globally, this standard defines the technical and quality requirements essential for safe and compliant performance in high-integrity nuclear environments.
Highlights:
- Material qualification and certification, including welding consumable selection
- Design-by-analysis and allowable stress design criteria
- Requirements for vessels, piping, valves, and pump components
- Fabrication processes including mechanical joints, welding, and heat treatment
- Nondestructive examination (NDE) methods and acceptance criteria
- Protocols for hydrostatic, pneumatic, and special pressure testing
- Overpressure protection and relief system certification standards
- Stamping, marking, and documentation rules for code compliance
New in the 2023 Edition:
- Enhanced fracture toughness requirements
- Updated material specifications and qualification rules
- Clarified guidance on fabrication, examination, and inspection procedures
Who It’s For:
Nuclear engineers, QA/QC inspectors, fabricators, and regulatory compliance personnel involved in the design, manufacture, and validation of ASME Section III Class 1 components.
BPVC.III.1.NB-2023
ASME BPVC Section III, Division 1, Subsection NB: Rules for Class 1 Nuclear Facility Components, 2023
ASME BPVC Section III, Division 1, Subsection NB provides mandatory construction rules for Class 1 pressure-retaining components in nuclear power facilities. Recognized globally, this standard defines the technical and quality requirements essential for safe and compliant performance in high-integrity nuclear environments.
Highlights:
- Material qualification and certification, including welding consumable selection
- Design-by-analysis and allowable stress design criteria
- Requirements for vessels, piping, valves, and pump components
- Fabrication processes including mechanical joints, welding, and heat treatment
- Nondestructive examination (NDE) methods and acceptance criteria
- Protocols for hydrostatic, pneumatic, and special pressure testing
- Overpressure protection and relief system certification standards
- Stamping, marking, and documentation rules for code compliance
New in the 2023 Edition:
- Enhanced fracture toughness requirements
- Updated material specifications and qualification rules
- Clarified guidance on fabrication, examination, and inspection procedures
Who It’s For:
Nuclear engineers, QA/QC inspectors, fabricators, and regulatory compliance personnel involved in the design, manufacture, and validation of ASME Section III Class 1 components.
BPVC.III.1.NB-2023
ASME BPVC Section III, Division 1, Subsection NC: Rules for Class 2 Components, 2023
ASME BPVC.CC.NC-2023 compiles active and approved code cases offering alternatives, interpretations, and early implementations for ASME Section III—governing pressure-retaining components in nuclear facilities. This volume supports compliance, innovation, and flexibility across Class 1, 2, 3, MC, CS, and CC nuclear systems.
Highlights:
- Includes hundreds of current code cases for nuclear components and assemblies
- Covers fabrication, materials, examination, inspection, and repair alternatives
- Incorporates updates through Supplement 7 to the 2021 edition, revised for the 2023 cycle
- Indexes organized by code case number, subject, material, and component class
- Tracks case status including approvals, annulments, supersessions, and reinstatements
- Applies to Division 1 through 5 of Section III, including fission/fusion reactors, spent fuel transport, and high-temperature nuclear designs
- Provides guidance on proposing new code cases and obtaining official ASME interpretations
- Addresses advanced welding processes, fatigue analysis, stress evaluation, and inspection under nuclear conditions
Who It’s For:
Nuclear engineers, manufacturers, QA/QC professionals, and regulators managing compliance and alternative approaches to ASME Section III requirements.
BPVC.CC.NC-2023
ASME BPVC Section III, Division 1, Subsection NC: Rules for Class 2 Components, 2023
ASME BPVC.CC.NC-2023 compiles active and approved code cases offering alternatives, interpretations, and early implementations for ASME Section III—governing pressure-retaining components in nuclear facilities. This volume supports compliance, innovation, and flexibility across Class 1, 2, 3, MC, CS, and CC nuclear systems.
Highlights:
- Includes hundreds of current code cases for nuclear components and assemblies
- Covers fabrication, materials, examination, inspection, and repair alternatives
- Incorporates updates through Supplement 7 to the 2021 edition, revised for the 2023 cycle
- Indexes organized by code case number, subject, material, and component class
- Tracks case status including approvals, annulments, supersessions, and reinstatements
- Applies to Division 1 through 5 of Section III, including fission/fusion reactors, spent fuel transport, and high-temperature nuclear designs
- Provides guidance on proposing new code cases and obtaining official ASME interpretations
- Addresses advanced welding processes, fatigue analysis, stress evaluation, and inspection under nuclear conditions
Who It’s For:
Nuclear engineers, manufacturers, QA/QC professionals, and regulators managing compliance and alternative approaches to ASME Section III requirements.
BPVC.CC.NC-2023
ASME BPVC Section III, Division 1, Subsection NCD: Rules for Class 2 and Class 3 Components, 2023
ASME BPVC 2023 Section III, Division 1, Subsection NCD defines the mandatory requirements for the design, construction, inspection, and certification of Class 2 and Class 3 pressure-retaining components in nuclear power plants. Developed under ANSI-accredited consensus procedures, it ensures safety, integrity, and regulatory compliance in moderate- and low-risk nuclear systems.
Highlights:
- Material qualification and welding consumable certification
- Design-by-analysis criteria for vessels, piping, valves, and pump components
- Standards for fabrication, brazing, mechanical joints, and heat treatment
- Nondestructive examination (NDE) techniques and personnel qualifications
- Hydrostatic and pneumatic testing protocols
- Relief device and overpressure protection certification
- ASME marking, stamping, and documentation requirements
Key 2023 Revisions:
- Advanced manufacturing: NCD-2121(a) supports unlisted product forms per Appendix XXVIII
- Testing modernization: NCD-2321.2 removes full-size specimen mandate, aligns with SA-370
- Inservice monitoring: NCD-3124 permits use of Section XI Division 2 RIM programs
- Expanded NDE pathways: NCD-5540 includes CP-189 alongside SNT-TC-1A for personnel qualifications
Who It’s For:
Nuclear engineers, QA/QC professionals, code inspectors, and manufacturers engaged in Class 2 and Class 3 component compliance under ASME Section III.
BPVC.III.1.NCD-2023
ASME BPVC Section III, Division 1, Subsection NCD: Rules for Class 2 and Class 3 Components, 2023
ASME BPVC 2023 Section III, Division 1, Subsection NCD defines the mandatory requirements for the design, construction, inspection, and certification of Class 2 and Class 3 pressure-retaining components in nuclear power plants. Developed under ANSI-accredited consensus procedures, it ensures safety, integrity, and regulatory compliance in moderate- and low-risk nuclear systems.
Highlights:
- Material qualification and welding consumable certification
- Design-by-analysis criteria for vessels, piping, valves, and pump components
- Standards for fabrication, brazing, mechanical joints, and heat treatment
- Nondestructive examination (NDE) techniques and personnel qualifications
- Hydrostatic and pneumatic testing protocols
- Relief device and overpressure protection certification
- ASME marking, stamping, and documentation requirements
Key 2023 Revisions:
- Advanced manufacturing: NCD-2121(a) supports unlisted product forms per Appendix XXVIII
- Testing modernization: NCD-2321.2 removes full-size specimen mandate, aligns with SA-370
- Inservice monitoring: NCD-3124 permits use of Section XI Division 2 RIM programs
- Expanded NDE pathways: NCD-5540 includes CP-189 alongside SNT-TC-1A for personnel qualifications
Who It’s For:
Nuclear engineers, QA/QC professionals, code inspectors, and manufacturers engaged in Class 2 and Class 3 component compliance under ASME Section III.
BPVC.III.1.NCD-2023
ASME BPVC Section III, Division 1, Subsection NE: Rules for Class MC Components, 2023
ASME BPVC Section III, Division 1, Subsection NE – 2023 provides mandatory requirements for the design, construction, inspection, and certification of Class MC (Metal Containment) components in nuclear facilities. These components form part of the primary containment structure, ensuring isolation of radioactive materials during normal operation and postulated events.
This subsection applies to metal containment vessels and their appurtenances, such as access openings, nozzles, and penetrations. It supports the construction of structures required to withstand pressure and environmental loads in high-integrity nuclear safety systems.
Highlights:
- Requirements for material selection, qualification, and documentation
- Design-by-analysis criteria and structural integrity limits for containment boundaries
- Fabrication rules including welding, forming, brazing, and joint design
- Nondestructive examination (NDE) methods and personnel qualification
- Hydrostatic and pneumatic testing procedures to verify leak-tightness and pressure integrity
- Criteria for overpressure protection, relief devices, and pressure monitoring
- Documentation and stamping requirements for ASME Code certification
Who It’s For:
Essential for nuclear engineers, containment designers, quality assurance specialists, and regulatory compliance personnel responsible for the construction and certification of Class MC components in nuclear containment systems.
BPVC.III.1.NE-2023
ASME BPVC Section III, Division 1, Subsection NE: Rules for Class MC Components, 2023
ASME BPVC Section III, Division 1, Subsection NE – 2023 provides mandatory requirements for the design, construction, inspection, and certification of Class MC (Metal Containment) components in nuclear facilities. These components form part of the primary containment structure, ensuring isolation of radioactive materials during normal operation and postulated events.
This subsection applies to metal containment vessels and their appurtenances, such as access openings, nozzles, and penetrations. It supports the construction of structures required to withstand pressure and environmental loads in high-integrity nuclear safety systems.
Highlights:
- Requirements for material selection, qualification, and documentation
- Design-by-analysis criteria and structural integrity limits for containment boundaries
- Fabrication rules including welding, forming, brazing, and joint design
- Nondestructive examination (NDE) methods and personnel qualification
- Hydrostatic and pneumatic testing procedures to verify leak-tightness and pressure integrity
- Criteria for overpressure protection, relief devices, and pressure monitoring
- Documentation and stamping requirements for ASME Code certification
Who It’s For:
Essential for nuclear engineers, containment designers, quality assurance specialists, and regulatory compliance personnel responsible for the construction and certification of Class MC components in nuclear containment systems.
BPVC.III.1.NE-2023
ASME BPVC Section III, Division 1, Subsection NF: Rules for Supports, 2023
ASME BPVC Section III, Division 1, Subsection NF – 2023 provides construction requirements for component supports used in nuclear power plant systems governed by ASME Section III. These supports maintain the structural stability and functional alignment of Class 1, 2, and 3 piping and equipment under normal, transient, and postulated accident conditions.
Subsection NF defines design, material, fabrication, testing, and documentation standards for both standard and special supports. It ensures integrity, safety, and compliance for load-bearing structures subjected to mechanical, thermal, and seismic forces.
Highlights:
- Rules for the design and analysis of component supports including restraint, flexibility, and loading criteria
- Material specifications, qualification requirements, and traceability for metallic and nonmetallic components
- Welding, forming, and joining standards for fabrication and assembly
- Inspection and testing protocols including dimensional checks, load verification, and NDE
- Documentation requirements for design reports, material records, and ASME certification
- Supports integration with Class 1, 2, and 3 systems across piping, valves, and equipment
Who It’s For:
A must-have for structural engineers, nuclear designers, QA/QC personnel, and code compliance teams responsible for the qualification, construction, and certification of nuclear component supports.
BPVC.III.1.NF-2023
ASME BPVC Section III, Division 1, Subsection NF: Rules for Supports, 2023
ASME BPVC Section III, Division 1, Subsection NF – 2023 provides construction requirements for component supports used in nuclear power plant systems governed by ASME Section III. These supports maintain the structural stability and functional alignment of Class 1, 2, and 3 piping and equipment under normal, transient, and postulated accident conditions.
Subsection NF defines design, material, fabrication, testing, and documentation standards for both standard and special supports. It ensures integrity, safety, and compliance for load-bearing structures subjected to mechanical, thermal, and seismic forces.
Highlights:
- Rules for the design and analysis of component supports including restraint, flexibility, and loading criteria
- Material specifications, qualification requirements, and traceability for metallic and nonmetallic components
- Welding, forming, and joining standards for fabrication and assembly
- Inspection and testing protocols including dimensional checks, load verification, and NDE
- Documentation requirements for design reports, material records, and ASME certification
- Supports integration with Class 1, 2, and 3 systems across piping, valves, and equipment
Who It’s For:
A must-have for structural engineers, nuclear designers, QA/QC personnel, and code compliance teams responsible for the qualification, construction, and certification of nuclear component supports.
BPVC.III.1.NF-2023
ASME BPVC Section III, Division 1, Subsection NG: Rules for Core Support Structures, 2023
ASME BPVC 2023 Section III, Division 1, Subsection NG outlines the mandatory requirements for the design, construction, inspection, and testing of core support structures in nuclear power plants. As part of the globally recognized ASME Boiler and Pressure Vessel Code, this subsection ensures the structural integrity and operational safety of critical nuclear components.
Highlights:
- Requirements for material selection, qualification, and certification for nuclear-grade components
- Design criteria including design-by-analysis methods, stress limits, and load combinations
- Standards for fabrication techniques including welding, brazing, and mechanical joints
- Acceptance criteria and procedures for nondestructive examination (NDE)
- Hydrostatic and pneumatic test protocols to validate structural reliability
- Guidelines for overpressure protection, relief device approval, and data documentation
Who It’s For:
Nuclear engineers, fabricators, QA/QC professionals, and regulatory specialists responsible for the integrity and compliance of core support structures under ASME nuclear safety standards.
BPVC.III.1.NG-2023
ASME BPVC Section III, Division 1, Subsection NG: Rules for Core Support Structures, 2023
ASME BPVC 2023 Section III, Division 1, Subsection NG outlines the mandatory requirements for the design, construction, inspection, and testing of core support structures in nuclear power plants. As part of the globally recognized ASME Boiler and Pressure Vessel Code, this subsection ensures the structural integrity and operational safety of critical nuclear components.
Highlights:
- Requirements for material selection, qualification, and certification for nuclear-grade components
- Design criteria including design-by-analysis methods, stress limits, and load combinations
- Standards for fabrication techniques including welding, brazing, and mechanical joints
- Acceptance criteria and procedures for nondestructive examination (NDE)
- Hydrostatic and pneumatic test protocols to validate structural reliability
- Guidelines for overpressure protection, relief device approval, and data documentation
Who It’s For:
Nuclear engineers, fabricators, QA/QC professionals, and regulatory specialists responsible for the integrity and compliance of core support structures under ASME nuclear safety standards.
BPVC.III.1.NG-2023
ASME BPVC Section III, Division 3: Containment Systems for Transportation and Storage of Spent Nuclear Fuel and High-Level Radioactive Material, 2023
ASME BPVC Section III, Division 3 – 2023 specifies mandatory construction requirements for containment systems used in the transportation and storage of spent nuclear fuel and high-level radioactive waste. This section supports regulatory compliance and public safety for radioactive material handling by providing robust rules for structural integrity, containment, shielding, and thermal performance.
It applies to casks, canisters, and related components intended for road, rail, and stationary storage, under both normal and accident conditions.
Highlights:
- Design-by-analysis criteria for radioactive material containment systems under extreme thermal, mechanical, and environmental loads
- Material selection, qualification, and fracture toughness requirements
- Fabrication standards for welding, joining, and forming of structural materials
- Mandatory nondestructive examination (NDE) protocols including radiographic and ultrasonic testing
- Validation tests including hydrostatic, leakage, drop, puncture, fire, and immersion evaluations
- Documentation and marking requirements including Code stamping, data reports, and ASME certification
- Applicable to both storage-only and dual-purpose (storage/transport) cask systems
Who It’s For:
Essential for nuclear fuel cycle engineers, cask designers, QA inspectors, and regulatory personnel involved in the design, construction, and approval of containers for radioactive material transport and storage under ASME compliance.
BPVC.III.3-2023
ASME BPVC Section III, Division 3: Containment Systems for Transportation and Storage of Spent Nuclear Fuel and High-Level Radioactive Material, 2023
ASME BPVC Section III, Division 3 – 2023 specifies mandatory construction requirements for containment systems used in the transportation and storage of spent nuclear fuel and high-level radioactive waste. This section supports regulatory compliance and public safety for radioactive material handling by providing robust rules for structural integrity, containment, shielding, and thermal performance.
It applies to casks, canisters, and related components intended for road, rail, and stationary storage, under both normal and accident conditions.
Highlights:
- Design-by-analysis criteria for radioactive material containment systems under extreme thermal, mechanical, and environmental loads
- Material selection, qualification, and fracture toughness requirements
- Fabrication standards for welding, joining, and forming of structural materials
- Mandatory nondestructive examination (NDE) protocols including radiographic and ultrasonic testing
- Validation tests including hydrostatic, leakage, drop, puncture, fire, and immersion evaluations
- Documentation and marking requirements including Code stamping, data reports, and ASME certification
- Applicable to both storage-only and dual-purpose (storage/transport) cask systems
Who It’s For:
Essential for nuclear fuel cycle engineers, cask designers, QA inspectors, and regulatory personnel involved in the design, construction, and approval of containers for radioactive material transport and storage under ASME compliance.
BPVC.III.3-2023
ASME BPVC Section III, Division 4: Fusion Energy Devices, 2023
The ASME Boiler and Pressure Vessel Code (BPVC) Section III, Division 4 – 2023 provides comprehensive construction rules for components in fusion energy devices, marking a major step toward codifying safety and engineering standards in fusion power development. This section applies to structural and pressure-retaining components subject to the unique operational and environmental demands of fusion facilities.
Highlights:
- Construction requirements for magnetic confinement systems, vacuum vessels, in-vessel components, and pressure boundaries
- General design rules including design-by-analysis for fusion systems
- Coverage of electrical/mechanical penetration assemblies, port structures, and cryostat interfaces
- Material selection, testing, and welding provisions specific to fusion applications
- Classification guidance for fusion plant systems and jurisdictional boundaries
- Requirements for inspection, certification, documentation, and quality assurance
- Fully integrates with other BPVC sections (e.g., Sections II, V, VIII, IX) for cross-discipline consistency
Who It’s For:
Nuclear engineers, fusion researchers, designers, and code compliance officials working on fusion-based facilities and components that demand codified reliability and structural integrity under evolving technologies.
BPVC.III.4-2023
ASME BPVC Section III, Division 4: Fusion Energy Devices, 2023
The ASME Boiler and Pressure Vessel Code (BPVC) Section III, Division 4 – 2023 provides comprehensive construction rules for components in fusion energy devices, marking a major step toward codifying safety and engineering standards in fusion power development. This section applies to structural and pressure-retaining components subject to the unique operational and environmental demands of fusion facilities.
Highlights:
- Construction requirements for magnetic confinement systems, vacuum vessels, in-vessel components, and pressure boundaries
- General design rules including design-by-analysis for fusion systems
- Coverage of electrical/mechanical penetration assemblies, port structures, and cryostat interfaces
- Material selection, testing, and welding provisions specific to fusion applications
- Classification guidance for fusion plant systems and jurisdictional boundaries
- Requirements for inspection, certification, documentation, and quality assurance
- Fully integrates with other BPVC sections (e.g., Sections II, V, VIII, IX) for cross-discipline consistency
Who It’s For:
Nuclear engineers, fusion researchers, designers, and code compliance officials working on fusion-based facilities and components that demand codified reliability and structural integrity under evolving technologies.
BPVC.III.4-2023
ASME BPVC Section III, Division 5: High Temperature Reactors, 2023
The ASME Boiler and Pressure Vessel Code (BPVC) Section III, Division 5 – 2023 outlines construction rules for nuclear facility components used in high temperature reactor (HTR) systems. Developed for advanced fission and fusion reactors, this section addresses unique design, material, and fabrication challenges posed by elevated temperature environments, including creep, fatigue, and environmental degradation. It applies to Class A and Class B metallic pressure boundaries, core supports, and components made from graphite and composite materials.
Highlights:
- Covers materials, design, fabrication, inspection, and testing for elevated temperature reactors
- Subdivides content by metallic and nonmetallic materials, temperature range, and component class
- Defines qualification of graphite/composite core components and high-temperature alloys
- Provides creep–fatigue rules and inelastic analysis requirements
- Integrates design-by-analysis criteria for pressure vessels, piping, pumps, and valves
- Details responsibilities, certification, and data reporting for code activities
- Includes overpressure protection and quality assurance provisions
- Incorporates mandatory and nonmandatory appendices for strain limits, material guidelines, and fatigue evaluation
- Harmonized with other BPVC Sections including II, V, IX, and XI for materials, NDE, welding, and inspection
Who It’s For:
Nuclear design engineers, advanced reactor developers, QA professionals, and regulators focused on the construction and qualification of components for high temperature nuclear systems operating under ASME code compliance.
BPVC.III.5-2023
ASME BPVC Section III, Division 5: High Temperature Reactors, 2023
The ASME Boiler and Pressure Vessel Code (BPVC) Section III, Division 5 – 2023 outlines construction rules for nuclear facility components used in high temperature reactor (HTR) systems. Developed for advanced fission and fusion reactors, this section addresses unique design, material, and fabrication challenges posed by elevated temperature environments, including creep, fatigue, and environmental degradation. It applies to Class A and Class B metallic pressure boundaries, core supports, and components made from graphite and composite materials.
Highlights:
- Covers materials, design, fabrication, inspection, and testing for elevated temperature reactors
- Subdivides content by metallic and nonmetallic materials, temperature range, and component class
- Defines qualification of graphite/composite core components and high-temperature alloys
- Provides creep–fatigue rules and inelastic analysis requirements
- Integrates design-by-analysis criteria for pressure vessels, piping, pumps, and valves
- Details responsibilities, certification, and data reporting for code activities
- Includes overpressure protection and quality assurance provisions
- Incorporates mandatory and nonmandatory appendices for strain limits, material guidelines, and fatigue evaluation
- Harmonized with other BPVC Sections including II, V, IX, and XI for materials, NDE, welding, and inspection
Who It’s For:
Nuclear design engineers, advanced reactor developers, QA professionals, and regulators focused on the construction and qualification of components for high temperature nuclear systems operating under ASME code compliance.
BPVC.III.5-2023
ASME BPVC Section III, Subsection NCA: General Requirements for Divisions 1 and 2, 2023
The ASME Boiler and Pressure Vessel Code (BPVC) Section III, Subsection NCA–2023 defines general requirements for the design, construction, certification, and inspection of Class 1, 2, and 3 nuclear facility components. It supports both Division 1 and Division 2 construction and forms the administrative and quality system backbone for all nuclear components governed by Section III.
Highlights:
- Establishes classification, responsibilities, and quality assurance for materials, fabricators, designers, and inspectors
- Provides scope definitions and boundary conditions for Division 1 and 2 applications
- Includes requirements for Certificates of Authorization, ASME Code Stamping, and data report documentation
- Defines criteria for quality system programs (QSP) for metallic, nonmetallic, and polyethylene material organizations
- Details responsibilities of Certificate Holders, Design Authorities, and Authorized Inspection Agencies
- Specifies recordkeeping requirements including lifetime and non-permanent quality records
- Integrates requirements for authorized inspections and duties of inspectors
- Includes a glossary, nameplate specifications, and certification mark applications
Who It’s For:
Nuclear engineers, code compliance officers, quality assurance personnel, and material organizations involved in the ASME certification and documentation process for nuclear facility components under Division 1 and Division 2.
BPVC.III.NCA-2023
ASME BPVC Section III, Subsection NCA: General Requirements for Divisions 1 and 2, 2023
The ASME Boiler and Pressure Vessel Code (BPVC) Section III, Subsection NCA–2023 defines general requirements for the design, construction, certification, and inspection of Class 1, 2, and 3 nuclear facility components. It supports both Division 1 and Division 2 construction and forms the administrative and quality system backbone for all nuclear components governed by Section III.
Highlights:
- Establishes classification, responsibilities, and quality assurance for materials, fabricators, designers, and inspectors
- Provides scope definitions and boundary conditions for Division 1 and 2 applications
- Includes requirements for Certificates of Authorization, ASME Code Stamping, and data report documentation
- Defines criteria for quality system programs (QSP) for metallic, nonmetallic, and polyethylene material organizations
- Details responsibilities of Certificate Holders, Design Authorities, and Authorized Inspection Agencies
- Specifies recordkeeping requirements including lifetime and non-permanent quality records
- Integrates requirements for authorized inspections and duties of inspectors
- Includes a glossary, nameplate specifications, and certification mark applications
Who It’s For:
Nuclear engineers, code compliance officers, quality assurance personnel, and material organizations involved in the ASME certification and documentation process for nuclear facility components under Division 1 and Division 2.
BPVC.III.NCA-2023
ASME BPVC Section III: Nuclear Facility Component Appendices, 2023
The ASME Boiler and Pressure Vessel Code (BPVC) Section III Appendices – 2023 Edition consolidates mandatory and nonmandatory appendices supporting the design and construction of nuclear facility components under Section III. This volume provides supplemental data, methods, and qualifications for materials, stresses, and personnel essential to advanced nuclear systems.
Highlights:
- Mandatory Appendices on fatigue design, stress analysis, flange connections, and plastic deformation limits
- Detailed methods for stress intensification, flexibility factors, and experimental verification
- Tables for stress intensity, fatigue strength, and mechanical properties for metallic materials
- Rules for bolted joints, polyethylene piping, and HIP-formed pressure parts
- Certification guidance for personnel, design report templates, and material qualification
- Nonmandatory Appendices for seismic analysis, weld examination, valve discharge systems, and design tolerances
- Appendix-based cross-referencing to Section III Subsections and external standards
- Supports compliance with ASME nuclear construction and inspection requirements
Who It’s For:
Engineers, designers, QA/QC managers, and code regulators involved in the analysis, testing, and certification of ASME Section III nuclear components. Complements Subsections NB through NG by offering expanded technical resources.
BPVC.III.A-2023
ASME BPVC Section III: Nuclear Facility Component Appendices, 2023
The ASME Boiler and Pressure Vessel Code (BPVC) Section III Appendices – 2023 Edition consolidates mandatory and nonmandatory appendices supporting the design and construction of nuclear facility components under Section III. This volume provides supplemental data, methods, and qualifications for materials, stresses, and personnel essential to advanced nuclear systems.
Highlights:
- Mandatory Appendices on fatigue design, stress analysis, flange connections, and plastic deformation limits
- Detailed methods for stress intensification, flexibility factors, and experimental verification
- Tables for stress intensity, fatigue strength, and mechanical properties for metallic materials
- Rules for bolted joints, polyethylene piping, and HIP-formed pressure parts
- Certification guidance for personnel, design report templates, and material qualification
- Nonmandatory Appendices for seismic analysis, weld examination, valve discharge systems, and design tolerances
- Appendix-based cross-referencing to Section III Subsections and external standards
- Supports compliance with ASME nuclear construction and inspection requirements
Who It’s For:
Engineers, designers, QA/QC managers, and code regulators involved in the analysis, testing, and certification of ASME Section III nuclear components. Complements Subsections NB through NG by offering expanded technical resources.
BPVC.III.A-2023