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CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS

SECTION III RULES FOR CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS

Provides general requirements which address the material, design, fabrication, examination, testing, and overpressure protection of the items specified within each respective Subsection, assuring their structural integrity.


SUBSECTION NCA (DIVISIONS 1 & 2)

Subsection NCA, which is referenced by and is an integral part of Division 1 and Division 2 of Section III, covers requirements for quality assurance, certification, and authorized inspection for Class 1, 2, 3, MC, CS, and CC construction.


DIVISION 1, SUBSECTIONS NB, NC AND ND

Subsection NB addresses items that are intended to conform to the requirements for Class 1 construction.


Subsection NC addresses items that are intended to conform to the requirements for Class 2 construction.


Subsection ND addresses items that are intended to conform to the requirements for Class 3 construction.


DIVISION 1, SUBSECTION NE

Subsection NE addresses items, which are intended to conform to the requirements for Class MC construction.


DIVISION 1, SUBSECTION NF

Subsection NF addresses the supports, which are intended to conform to the requirements for Classes 1, 2, 3, and MC construction.


DIVISION 1, SUBSECTION NG

Subsection NG addresses structures, which are designed to provide direct support or restraint of the core (fuel and blanket assemblies) within the reactor pressure vessel.


DIVISION 2

Division 2 addresses concrete containment structures, pre-stressed or reinforced. These requirements are applicable only to those components that are designed to provide a pressure retaining or containing barrier.


DIVISION 3

Division 3 addresses the design and construction of the containment systems, including internal support structures, used for the transportation and/or storage of spent nuclear fuel and high-level radioactive material.


DIVISION 5

Division 5 provides construction rules for high-temperature reactors, including both high-temperature, gas-cooled reactors (HTGRs) and liquid-metal reactors (LMRs).


APPENDICES

Section III Appendices contain both mandatory and non-mandatory appendices referenced by all Divisions of Section III. The mandatory appendices contain requirements for construction (e.g., design and design analysis methods, Data Report Forms), while the non-mandatory appendices provide additional information or guidance for the use of Section III (e.g., guidance on preparing a Design Report.


REFERENCED BPVC SECTIONS


BPVC-II, A, B, C, D

Section II, Materials, Parts A through D.


BPVC-V

Section V, Nondestructive Examination.


BPVC-IX

Section IX, Welding, Brazing, and Fusing Qualifications.


BPVC-XI

Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components.


REFERENCED ASME STANDARDS


Three Standards from the B1 Series on screw threads.

Eight Standards from the B16 Series on pipe flanges and fittings.

Three Standards from the B18 Series on hex bolts.

B36.10M – Welded and Seamless Wrought Steel Pipe.

B36.19M – Stainless Steel Pipe.

NQA-1 – Quality Assurance Program Requirements for Nuclear Facilities.

QAI-1 – Qualifications for Authorized Inspection.



Universal Engineering Services has more than a decades experience in the pressure vessel design for clients in UAE, Oman, Qatar, Kuwait, Bahrain, Saudi Arabia, and many more countries all over the world. UES work to many ASME standards to design and validate pressure vessels, boiler, fittings and piping systems. We are also experts in Stress analysis of piping, structural design, ASME Joint review, Design of Storage tanks, code calculations, FEA/FEM, and spotless service on design management.


**The content of this article is taken from web open source. The blogs are intended only to give technical knowledge to young engineers. Any engineering calculators, technical equations, and write-ups are only for reference and educational purposes.


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