Description
This course introduces the B31.1 Power Piping Code. It discusses its relationship with ASME BPV Code, Section I – Rules for Construction on Power Boilers, and the requirements for design, fabrication, and testing. It covers the jurisdictional limits of the B31.1 Code and the ASME Boiler and Pressure Vessel Code, Section I and design issues specific to Power Piping systems. This course also reviews the qualification requirements for operators and operating procedures for welders and brazers and nondestructive examination requirements.
Quick Comparison
| Settings | B31.1 Power Piping remove | B31.3 Process Piping remove | Nuclear Piping Systems ASME BPV Code, Section III and B31.1: Design, Integrity Operability Assessment, and Repairs remove | Bolted Joints and Gasket Behavior remove | Design of Bolted Flange Joints remove | ASME NQA 1 Quality Assurance Requirements for Nuclear Facility Applications remove | ||
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| Name | B31.1 Power Piping remove | B31.3 Process Piping remove | Nuclear Piping Systems ASME BPV Code, Section III and B31.1: Design, Integrity Operability Assessment, and Repairs remove | Bolted Joints and Gasket Behavior remove | Design of Bolted Flange Joints remove | ASME NQA 1 Quality Assurance Requirements for Nuclear Facility Applications remove | ||
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| Price | 4,800.00 EGP | 4,800.00 EGP | 6,000.00 EGP | 4,000.00 EGP | 4,000.00 EGP | 550.00 EGP | ||
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| Content | This course introduces the B31.1 Power Piping Code. It discusses its relationship with ASME BPV Code, Section I - Rules for Construction on Power Boilers, and the requirements for design, fabrication, and testing. It covers the jurisdictional limits of the B31.1 Code and the ASME Boiler and Pressure Vessel Code, Section I and design issues specific to Power Piping systems. This course also reviews the qualification requirements for operators and operating procedures for welders and brazers and nondestructive examination requirements. | This course provides an introduction to the ASME B31.3 Process Piping Code. It covers the requirements of B31.3 for design, analysis, materials, fabrication, testing and inspection of process piping systems. It explores the rules for various components including fittings, connections, bends, valves and specialty components. | This course provides information and instruction on the design, analysis, and qualification of nuclear power plant piping systems that are consistent with the ASME BPV Code, Section III, Division 1, Subsections NB/NC/ND, as well as the parallel requirements of ASME B31.1 for nuclear power plants. The methods and criteria described throughout the course, apply to new systems, as well as modifications or repairs to existing systems.The course also addresses the integrity assessment of degraded nuclear piping systems (wall thinning and crack damage) using the methods and criteria of ASME BPV Code, XI, operability assessment per NRC Inspection Manual, and piping repairs per ASME BPV Code, XI and ASME PCC-2.The course covers (a) the code and regulatory requirements, (b) the technical and historical basis of the requirements, and (c) best industry practices for the correct and cost-effective design, analysis, and integrity assessment of nuclear piping systems. | This course examines how to assess a successful value of bolt load, as well as explains the importance of specifying a tightening procedure. It introduces the subject of PVRC (Pressure Vessel Research Council) leak tightness calculations and presents an overview of current trends and practices to achieve reliable leak-tight bolted joint solutions. | Bolted flange joints are essential components for the design and operation of pressure vessels and piping. | In addition to covering the NQA-1 Standard, it also provides a brief overview of Section III Rules for Construction of Nuclear Facility Components of the B&PV Code as they apply ASME NQA-1 for their quality assurance standard for new construction of nuclear facilities and plant modifications. This is an intermediate level course for engineers, managers and quality personnel who are, or will be, directly or indirectly involved in manufacturing, fabrication and examination of components or structures for nuclear power facilities. Participants should have at least one year of experience in the design, construction, and operation of, or have a supporting-supplier role for, nuclear power facilities and their components. | ||
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