Codes & Standards
3HCSI supports the interpretation and application of the Boiler & Pressure Vessel Code and related ASME standards, offering workshops, webinars and training modules on regulatory updates, safety requirements and best practice, for both the nuclear sector and conventional pressure applications.
at a glance
- 8 reference codes, from BPVC Section III to B31.12
- Focus on nuclear energy (Section III, Section XI, OM Code) and hydrogen (B31.12)
- Access contact: NORMADOC
- Over 2 million international standards available
Setting a Worldwide Standard.
When the founders of ASME, leading industrialists and technical innovators of the nineteenth century, met for the first time in 1880, the central theme was the need for standardised tools and mechanical components, as well as uniform working practices at the dawn of the industrial age. The founders agreed that engineering standards would ensure safety, reliability and operational efficiency in machine design and mechanical manufacturing. ASME published its first standard, the Code for the Conduct of Trials of Steam Boilers, in 1884, followed, in 1914, the first edition of the Rules for the Construction of Stationary Boilers, the forerunner of the current Boiler and Pressure Vessel Code, setting in motion a process of development that today comprises hundreds of codes and standards.
We were there at the start of the nuclear power industry.
ASME has played a crucial role in supporting the nuclear industry since its inception, when the codes, standards and compliance programmes originally developed for fossil-fuel power stations were applied to the construction of nuclear power stations. In 1963, ASME published Section III of the BPVC, the first code specifically for nuclear power stations; the dedicated certification programme followed a few years later, extending accreditation to nuclear components. When, in 1969, the US Atomic Energy Commission published its proposed amendments to the regulations, effectively establishing minimum quality requirements for the design, manufacture, acceptance, construction, testing and inspection of nuclear installations, ASME expanded its multidisciplinary codes, standards and compliance programmes to cover areas such as:
- — Rules for Construction of Nuclear Facility Components
- — Rules for In-Service Inspection of Nuclear Power Plant Components
- — Operations and Maintenance
- — Qualification of Mechanical Equipment
- — Nuclear Air and Gas Treatment
- — Nuclear Quality Assurance
- — Nuclear Risk Management
- — Cranes for Nuclear Facilities
ASME’s nuclear codes and standards exist to ensure public safety, support global trade, advance technology and facilitate the transfer of knowledge, whilst easing the regulatory burden on governments. By combining technical and quality requirements (underpinned by a time-tested, consensus-based approach to decision-making) ASME develops standards that are universally adoptable, applicable and accepted. With offices in India, China and North America, ASME is ideally placed to continue its long-standing support for the nuclear industry.
Eight codes: the regulatory framework we follow every day.
From the manufacture of nuclear components to welding, from hydrogen pipework to conformity assessment, each code listed below is linked to the section of the website where it is directly applicable.
ASME Boiler and Pressure Vessel Code Sections.
The thirteen sections of the BPVC (plus the Code Cases) cover the entire life cycle of boilers, pressure vessels and nuclear components, from design to decommissioning. The terminology is retained in English, the international reference standard.
Section I, Rules for Construction of Power Boilers+
Requirements for the construction of power boilers, electric and miniaturised boilers, high-temperature water boilers, heat-recovery steam generators and certain directly heated pressure vessels in stationary service, as well as locomotive, portable and traction boilers operating at pressures exceeding 15 psig.
Section II, Materials+
- Part A, Ferrous Material Specifications
- Part B, Nonferrous Material Specifications
- Part C: Specifications for Welding Rods, Electrodes, and Filler Metals
- Part D, Properties (Customary)
- Part D, Properties (Metric)
Section III, Rules for Construction of Nuclear Facility Components+
It sets out the general requirements relating to materials, design, manufacture, examination, testing and protection against overpressure for the components specified in each subsection, thereby ensuring their structural integrity.
Division 1, Subsection NCA, It covers the general requirements for constructors, manufacturers, installers, designers, producers and suppliers of materials, and owners of nuclear installations. Referenced in Subsection NB-NG (Division 1) and Division 2, it covers quality assurance requirements, ASME certification marks and authorised inspection for Class 1, 2, 3, MC, CS and CC structures. It makes selective reference to the ASME NQA-1 standard (not included in the BPVC subscription; must be purchased separately).
Division 1, Subsection NB, NF, APP, NB covers materials, design, manufacture, examination, testing and overpressure protection for Class 1 components. NF covers materials, design, manufacture and examination of supports for Class 1, 2, 3 and MC structures. The Appendices (APP) contain mandatory and non-mandatory appendices for reference in relation to NCA-NG and Division 2, including Data Report Forms.
Division 1, Subsection NCD, requirements relating to materials, design, manufacture, examination, testing and protection against overpressure for Class 2 and 3 components.
Other Sub-sections and Divisions, NE covers Class MC structures. NG covers additional Class MC requirements. NH covers the manufacture and installation of core support structures, the structures that directly support the fuel assemblies inside the reactor vessel.
- Division 1: Subsection NCA (General Requirements Division 1 & 2), NB (Class 1 Components), NCD (Class 2 and Class 3 Components), NE (Class MC Components), NF (Supports), NG (Core Support Structures), NH (Class 1 Components in Elevated Temperature Service), Appendices
- Division 2, Code for Concrete Containments
- Division 3, Containment Systems and Transport Packaging for Spent Nuclear Fuel and High-Level Radioactive Waste
- Division 4, Fusion Energy Devices
- Division 5, High Temperature Reactors
Section IV, Heating Boilers+
Requirements for the construction of heating boilers, low-pressure heating boilers made of steel and cast iron.
Section V, Nondestructive Examination+
Non-destructive testing methods for detecting surface and internal defects in materials, welds and fabricated components, and requirements for the qualification of personnel carrying out such tests.
Section VI, Recommended Rules for the Care and Operation of Heating Boilers+
Guidelines on general descriptions, terminology and operational procedures for steel and cast-iron heating boilers.
Section VII, Recommended Guidelines for the Care of Power Boilers+
Guidelines for those directly responsible for the operation, maintenance and inspection of power boilers, including the auxiliary equipment that ensures their safe operation.
Section VIII, Pressure Vessels+
- Division 1, Basic Coverage
- Division 2, Alternative Rules
- Division 3, Alternative Rules for Construction of High-Pressure Vessels
Section IX: Welding, Brazing, and Fusing Qualifications+
Welding, Brazing, and Fusing Qualifications.
Section X, Fiber-Reinforced Plastic Pressure Vessels+
Design, manufacture and testing requirements for fibre-reinforced plastic pressure vessels.
Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components+
- Division 1, Rules for Inspection and Testing of Components of Light-Water Cooled Plants
- Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor Facilities
Section XII, Rules for the Construction and Continued Service of Transport Tanks+
Requirements for the construction and maintenance of tanks for the transport of goods under pressure by road, rail and sea.
Section XIII, Rules for Overpressure Protection+
Requirements for the design, materials, inspection, assembly, testing, marking and installation of overpressure protection devices (safety valves, burst discs, non-resetting plug and spring-loaded devices) applicable to boilers, pressure vessels and pipework systems.
Code Cases, Nuclear Components+
Code Cases: Nuclear Components.
Code Cases, Boilers and Pressure Vessels+
Code Cases: Boilers and Pressure Vessels.
Companion Nuclear Codes and Standards.
In addition to the BPVC, a set of dedicated ASME standards covers quality assurance, maintenance, equipment qualification, risk assessment, air and gas treatment, and lifting, all of which are applicable to nuclear power stations, SMRs and advanced reactors.
NQA-1, Quality Assurance Requirements for Nuclear Facility Applications+
It sets out the quality assurance requirements for facilities, systems, components and activities relevant to nuclear safety, throughout the entire life cycle of the plant, from site selection to decommissioning. Full details (7 quality assurance areas, notes and official links) can be found on the page Certification & Accreditation ↗.
OM, Operation and Maintenance of Nuclear Power Plants+
It sets out the requirements for the testing and pre-commissioning and in-service inspection of certain components, in order to assess their operational readiness in light-water reactor plants. It identifies the components subject to testing or inspection, responsibilities, methods, intervals, parameters to be measured and assessed, criteria for evaluating results, corrective actions, staff qualifications and record-keeping.
QME-1, Qualification of Mechanical Equipment Used in Nuclear Facilities+
It sets out the requirements and guidelines for the qualification of mechanical equipment (pumps, valves, seismic protection devices) used in nuclear power stations, including SMRs and advanced reactors. It defines the principles, procedures and methods for qualification.
RA-S-1.1, Probabilistic Risk Assessment for Nuclear Power Plant Applications (PRA)+
Requirements for a Level 1 Probabilistic Risk Assessment of internal and external hazards to an operating plant, to assess the frequency of core damage, with a limited Level 2 analysis of the frequency of large-scale early release. It explicitly excludes only security threats of deliberate human origin (sabotage, terrorism). Applicable to light-water reactors in operation, under design or under construction, or to advanced reactors such as SMRs, with additional requirements as may be necessary.
RA-S-1.2, Probabilistic Risk Assessment for Nuclear Power Plant Applications (PRA)+
Requirements for probabilistic risk assessments (PRA) to support risk-informed decision-making for commercial light-water nuclear power stations, including SMRs. Specifies specific requirements where necessary for specific reactor designs.
AG-1, Code on Nuclear Air and Gas Treatment+
Performance, design, construction, acceptance testing and quality assurance requirements for equipment used as components in air and gas handling systems relevant to nuclear safety, including nuclear installations, SMRs and advanced reactors.
N511: In-Service Testing of Nuclear Air Treatment, Heating, Ventilating, and Air-Conditioning Systems+
Requirements for in-service testing of air-handling, heating, ventilation and air-conditioning systems relevant to nuclear safety in nuclear installations.
NUM-1: Rules for Construction of Cranes, Monorails, and Hoists (with Bridge or Trolley or Hoist of the Underhung Type)+
This covers overhead travelling cranes, travelling cranes and gantry cranes with suspended trolleys, wall-mounted cranes, jib cranes, monorail systems and hoists (including those with integrated trolleys) used in nuclear power stations, SMRs and advanced reactors, with the exception of double-girder cranes with suspended trolleys and bridges, which are covered by ASME NOG-1.
NOG-1, Rules for Construction of Overhead and Gantry Cranes (Top Running Bridge, Multiple Girder)+
It covers electric double-girder overhead travelling cranes and gantry cranes with suspended bridges and trolleys, used in nuclear power stations and other high-risk facilities, including SMRs and advanced reactors.
NORMADOC · access to standards.
For accessing and purchasing ASME codes and standards, 3HCSI relies on NORMADOC, an authorized reseller for corporate (retail and subscriptions) and corporate partner of 3HCSI.
NORMADOC, Your Expert Partner in Standards and Technical Documentation
A globally certified supplier of standards, regulatory documents and technical publications, serving industrial sectors worldwide for over 30 years. Access to more than 2 million standards — ASME, IEC, ASTM, AAMI, IEEE, DIN, BSI, SAE, ICAO, TEMA, NBIC, UL, CSA, IPC and more — with regulatory monitoring services and centralised subscription management.
Visit NORMADOC.com ↗What we cover
8 ASME codes directly linked to the website’s Focus Areas, from the construction of nuclear components (Section III) to welding (Section IX), from hydrogen piping (B31.12) to conformity assessment (CA-1). Further details on each code can be found in the Member Area, where you can request a pre-assessment from our qualified engineers.
Access to standards
- NORMADOC, certified supplier, over 30 years’ experience
- Over 2 million international standards (ASME, IEC, ASTM, etc.)
Frequently asked questions.
What is the Boiler & Pressure Vessel Code (BPVC)?+
The ASME code covering the entire life cycle of boilers, pressure vessels and nuclear components: design, materials, manufacture, inspection and testing. It is organised into thirteen Sections by area of application, ranging from power boilers to nuclear components, from non-destructive testing to overpressure protection, plus Code Cases for situations not yet covered by the current edition.
How do you purchase ASME codes?+
Through NORMADOC, a certified partner of 3HCSI and, from 2025, the official online distributor of ASME publications, with access to over 2 million international standards.
Which code applies to hydrogen pipework?+
ASME B31.12, the construction code for hydrogen pipes and pipelines, part of the ASME B31 series on pressure piping.
Can 3HCSI help me work out which code I need?+
Yes. Please email team@3hcsi.com so that we can assess together which ASME standard applies to your specific case.
Can't find the code you need?
Write to us: we’ll help you identify the ASME standard that applies to your situation.