Pressure vessels, nuclear power

Direct fired pressure vessels Nuclear power plants Heating boilers Unfired pressure vessels... 

Rules for Nuclear Power piping are in Section 3 of the ASME Boiler Pressure Vessel Code. 

Zirconium is used as a containment material for the uranium oxide fuel pellets in nuclear power reactors (see Nuclearreactors). Zirconium is particularly usehil for this appHcation because of its ready availabiUty, good ductiUty, resistance to radiation damage, low thermal-neutron absorption cross section 18 x 10 ° ra (0.18 bams), and excellent corrosion resistance in pressurized hot water up to 350°C. Zirconium is used as an alloy strengthening agent in aluminum and magnesium, and as the burning component in flash bulbs. It is employed as a corrosion-resistant metal in the chemical process industry, and as pressure-vessel material of constmction in the ASME Boiler and Pressure Vessel Codes. 

B31.7 Nuclear Power Piping For fluids whose loss from the system could cause radiation hazard to plant personnel or the general pubhc Withdrawn see ASME Boiler and Pressure Vessel Code, Sec. 3... 

This report summarizes data on non-nuclear pressure vessel failures in order to develop data which could be applied to the nuclear power industry. Tables 3 through 6 present summaries of vessel failures and failure rates. 

Boiler and Pressure Vessel Code, Section II, Materials (Part A, Ferrous Material Specifications, and Part D, Properties ), Section ID, Rules for Construction of Nuclear Power Plant Components, and Section VIII, Pressure Vessels, Divisions 1 and 2. Code for Pressure Piping, ASME/ANSI B31.3, Chemical Plant and Petroleum Refinery Piping ... 

In the ASME Code Sections I and VIII, Division 1 (Power Boilers and Pressure Vessels) the design stresses below 650° F are 1/4 of the ultimate strength or 5/8 yield stren h. In Section III (Nuclear Vessels) and Section VIII, Division 2, they are 1/3 the ultimate strength or 2/3 the yield stress, whichever is least in each case. In France, the only official requirement is that the design stress for pressure vessels shall not exceed 1/3 the ultimate strength. 

Rules for Construction of Nuclear Power Plant Components Heating Boilers Nondestructive Examination Rules for Care and Operation of Heating Boilers Guidelines for the Care of Power Boilers Pressure Vessels... 

Welding and Brazing Qualifications Fiber-Reinforced Plastic Pressure Vessels Rules for Inservice Inspection of Nuclear Power Plant Components... 

The Nil-Ductility Transition (NDT) temperature, which is the temperature at which a given metal changes from ductile to brittle fracture, is often markedly increased by neutron irradiation. The increase in the NDT temperature is one of the most important effects of irradiation from the standpoint of nuclear power system design. For economic reasons, the large core pressure vessels of large power reactors have been constructed of low carbon steels. 

American Society of Mechanical Engineers (ASME). Nuclear Power Plant Components. ASHE Boiler and Pressure Vessel Code, Section III. ASME, New York, NY, 1985. 

In-service inspection (ISI) and surveillance will be carried out for structures, systems, and components (SSCs) of the Standard MHTGR to meet the applicable provisions of the ASME Boiler and Pressure Vessel Code, Section. XI, Rules for In-Service Inspection of Nuclear Power Plant Components, Divisions 1 and 2. The determination of the applicable portions of Section XI is based on the following criteria the SSC is required to achieve... 

Since 1972 the Reactor Plant Inspection Service (RPIS) of the Risley Nuclear Power Development Laboratories has undertaken contractual inspection of Pressurised Water Reactor Pressure Vessels (RPV s) in Europe. At this time 11 major pre-service and in-service Inspections of RPV s have been made and two more are planned for 1985. In addition numerous other inspections, both conventional and specialist, of nuclear plant have been made in Europe and the United Kingdom. 

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