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1、chapter one Overview of pressure vessels Contents 1.1Introduction. 1.2Development of pressure vessel construction codes. References . 1.1Introduction Vessels, tanks, and pipelines that carry, store, or receive fl uids are called pressure vessels. A pressure vessel is defi ned as a container with a p
2、ressure differential between inside and outside. The inside pressure is usually higher than the outside, except for some isolated situations. The fl uid inside the vessel may undergo a change in state as in the case of steam boilers, or may combine with other reagents as in the case of a chemical re
3、actor. Pressure vessels often have a combination of high pressures together with high temperatures, and in some cases fl ammable fl uids or highly radio- active materials. Because of such hazards it is imperative that the design be such that no leakage can occur. In addition these vessels have to be
4、 designed carefully to cope with the operating temperature and pressure. It should be borne in mind that the rupture of a pressure vessel has a potential to cause extensive physical injury and property damage. Plant safety and integrity are of fundamental concern in pressure vessel design and these
5、of course depend on the adequacy of design codes. When discussing pressure vessels we must also consider tanks. Pressure vessels and tanks are signifi cantly different in both design and construction: tanks, unlike pressure vessels, are limited to atmospheric pressure; and pressure vessels often hav
6、e internals while most tanks do not (and those that do are limited to heating coils or mixers). Copyright 2005 by CRC Press, Inc. All Rights Reserved. Pressure vessels are used in a number of industries; for example, the power generation industry for fossil and nuclear power, the petrochemical indus
7、try for storing and processing crude petroleum oil in tank farms as well as storing gasoline in service stations, and the chemical industry (in chemical reactors) to name but a few. Their use has expanded throughout the world. Pressure vessels and tanks are, in fact, essential to the chemical, petro
8、leum, petrochemical and nuclear industries. It is in this class of equipment that the reactions, separations, and storage of raw materials occur. Generally speaking, pressurized equipment is required for a wide range of industrial plant for storage and manufacturing purposes. The size and geometric
9、form of pressure vessels vary greatly from the large cylindrical vessels used for high-pressure gas storage to the small size used as hydraulic units for aircraft. Some are buried in the ground or deep in the ocean, but most are positioned on ground or supported in platforms. Pressure vessels are us
10、ually spherical or cylindrical, with domed ends. The cylindrical vessels are generally preferred, since they present simpler manufacturing problems and make better use of the available space. Boiler drums, heat exchangers, chemical reactors, and so on, are generally cylindrical. Spherical vessels ha
11、ve the advantage of requiring thinner walls for a given pressure and diameter than the equivalent cylinder. Therefore they are used for large gas or liquid containers, gas-cooled nuclear reactors, containment buildings for nuclear plant, and so on. Containment vessels for liquids at very low pressur
12、es are sometimes in the form of lobed spheroids or in the shape of a drop. This has the advantage of providing the best possible stress distribution when the tank is full. The construction of a typical pressure vessel is shown in Figure 1.1. A spherical pressure vessel is shown in Figure 1.2. This i
13、s a special pressure Figure 1.1 Typical pressure vessel. Copyright 2005 by CRC Press, Inc. All Rights Reserved. ? vessel and is really a storage sphere. Functionally it acts as a tank because its purpose is to store a fl uid. However since it does so at pressures above atmospheric, it can be classif
14、i ed as a pressure vessel. This however does not have internals and operates at atmospheric temperatures. A horizontally supported cylindrical pressure vessel with a hemispherical head and conical transition is shown in Figure 1.3. This consists of a cylindrical main shell, with hemispherical header
15、s and several nozzle connections. The vessel geometries can be broadly divided into plate- and shell-type confi gurations. The plate-type construction used in fl at covers (closures for pressure vessels and heat exchangers) resists pressure in bending, while the shell-types membrane action operates
16、in a fashion analogous to what happens in balloons under pressure. Generally speaking the shell-type construction is the preferred form because it requires less thickness (as can be demonstrated analytically) and therefore less material is required for its manufacture. Shell-type pressure components
17、 such as pressure vessel and Figure 1.2 Spherical pressure vessel. Figure 1.3 Horizontally supported pressure vessel. Copyright 2005 by CRC Press, Inc. All Rights Reserved. ? heat exchanger shells, heads of different geometric confi gurations, and nozzles resist pressure primarily by membrane action
18、. Pressure vessels are made in all shapes and sizes, from a few centimeters (cm) in diameter to 50 meters (m) or more in diameter. The pressure may be as low as 0.25 kilopascals (kPa) to as high as 2000 megapascals (MPa). The American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel
19、 Code, Section VIII, Division 1,1 specifi es a range of internal pressures from 0.1 MPa to 30 MPa. Pressure equipment, such as the American Petroleum Institute (API) storage tanks are designed to restrict internal pressure to no more than that generated by the static head of the fl uid contained in
20、the tank. A few more examples are provided in this chapter. In the area of nuclear power generation a number of coolant systems are used. The two plant cycles most often found in nuclear power plants are the pressurized water reactor and the boiling water reactor. The pressurized water reactor insid
21、e the reactor pressure vessel is subjected to a high coolant water pressure. The pressurized water is heated and the pump circulates the water through a heat exchanger (steam generator) where the steam for the turbine is generated. The part of the nuclear power plant containing the reactor coolant i
22、s called the primary circuit. Included in the primary circuit is an important vessel called the pressurizer. The coolant volume varies when the load changes require reactor coolant temperature changes, and when this occurs, the pressurizer serves as the expansion tank in the primary system, which al
23、lows the water to undergo thermal expansion and contraction keeping the primary circuit pressure nearly constant. If the pressures are allowed to fl uctuate too far, steam bubbles might form at the reactor heating surfaces; these bubbles or voids if formed inside the reactor core greatly alter react
24、or power output. The pressurizer has electric heating elements located low inside to provide the vapor needed to cushion the fl owing liquid coolant. All of these items are included in the primary circuit. Figure 1.4 shows a pressurized water reactor (PWR) vessel. A PWR steam generator and a PWR pre
25、ssurizer are indicated in Figures 1.5 and 1.6, respectively. The rest of the plant is called the secondary circuit. The steam generator produces the steam that passes through the turbine, condenser, condensate pumps, feed pump, feed water heaters and back to the steam generator. Pressure vessels as
26、components of a complete plant are designed to meet various requirements as determined by the designers and analysts responsible for the overall design. The fi rst step in the design procedure is to select the necessary relevant information, establishing in this way a body of design requirements, as
27、 shown in Figure 1.7. Once the design requirements have been established, suitable materials are selected and the specifi ed design code will give an allowable design or nominal stress that is used to dimension the main pressure vessel thickness. Additional code rules cover the design of various ves
28、sel components such as nozzles, fl anges, and so on. Following these rules an arrangement of the various components are fi nalized and analyzed for failure. Most of the types of Copyright 2005 by CRC Press, Inc. All Rights Reserved. ? failure relevant to pressure vessel design are stress dependent a
29、nd therefore it is necessary to ensure the adequacy of the stress distribution and check against different types of postulated failure modes. The proposed design is fi nally iterated until the most economical and reliable product is obtained. The functional requirements cover the geometrical design
30、parameters such as size and shape, location of the penetrations, and so on. Some of these parameters may have to be fi xed in collaboration with the overall design team, but in a majority of situations the pressure vessel designer acts freely on the basis of his or her experience. Figure 1.4 Pressur
31、ized water reactor (PWR) pressure vessel. (Courtesy of Westinghouse Electric Company, Pittsburgh, PA.) Copyright 2005 by CRC Press, Inc. All Rights Reserved. In the design of pressure vessels safety is the primary consideration, especially for nuclear reactor pressure vessels, due the potential impa
32、ct of a possible severe accident. In general however, the design is a compromise between consideration of economics and safety. The possible risks of a given mode of failure and its consequences are balanced against the effort required for its prevention; the resulting design should achieve an adequ
33、ate standard of safety at minimum cost. Safety cannot be absolutely assured for two reasons. First, the actual form of loading during service may be more severe than was anticipated at Figure 1.5 Pressurized water reactor (PWR) steam generator. (Courtesy of Westinghouse Electric Company, Pittsburgh,
34、 PA.) Copyright 2005 by CRC Press, Inc. All Rights Reserved. the design stage: abnormal, unpredictable loads inevitably occur during the pressure vessels lifetime. Second, our knowledge is seldom adequate to provide a qualifi ed answer to the fracture of materials, state of stress under certain cond
35、itions, and so on. It is true that although the fundamental mechanism of failure is not suffi ciently understood, it is possible to establish preventive measures based on semiempirical methods. Following this line of thinking, the pressure vessels could be classifi ed according to the severity of th
36、eir operations since this will affect both the possibility of failure and its Figure 1.6 Pressurized water reactor (PWR) pressurizer. (Courtesy of Westinghouse Electric Company, Pittsburgh, PA.) Copyright 2005 by CRC Press, Inc. All Rights Reserved. consequences. These considerations lead to the cla
37、ssifi cation of vessels ranging from nuclear reactor pressure vessels at one end to underground water tanks at the other. The design factor used in the ASME Boiler and Pressure Vessel Code1is intended to account for unknown factors associated with the design and construction of the equipment. The de
38、sign formulas and the stress analysis methods are generally approximate and have built-in assumptions. Typically it is assumed that the material is homogeneous and isotropic. In the real world the material has fl aws and discontinuities, which tend to deviate from this assumption. In 1925, the rules
39、 for construction of power boilers was written using a design factor of 5 which was subsequently reduced to 4 in 1942, presumably to help conserve steel. In 1955, new processes in the petrochemical industry were requiring signifi cant design pressures requiring wall thickness in vessels to be betwee
40、n 150 and 200 millimeters (mm). The ASME Pressure Vessel and Code Committee decided to form a task group with the allowable stresses based on a design factor of 3. The purpose was to reduce fabrication costs, with the implied assumptions that this could be applied to limited materials, with the addi
41、tion of fracture toughness rules along with design rules for cyclic operation (fatigue) and that detailed stress analysis was used for most loading conditions. The committee felt that the nuclear code for pressure vessels would be easier to write than the code for pressure vessels used in petrochemi
42、cal processes. This is because the nuclear pressure vessels only contained steam and water, and the maximum temperature was 800?F (427? C). Many nuclear plant design specifi cations identifi ed that the design cycles for fatigue evaluation should be based on a 40-year life expectancy of the plant. T
43、he 40 years was based on nuclear plants being able to last twice as long as fossil plants (which usually lasted Figure 1.7 Design procedure. Copyright 2005 by CRC Press, Inc. All Rights Reserved. 20 years). The design for cyclic operation was based on the estimated cycles for 40 years, with the seve
44、rity of the cycles based on estimated worst conditions. This method of design was a rough attempt to ensure freedom from fatigue cracking during the 40-year period. Using the code fatigue curves, a cumulative usage factor was calculated that was arbitrarily required to be equal to less than unity, w
45、hich is based on the estimated number of cycles for the postulated 40-year period. The methodology has many conservative design factors in it, namely a factor of 2 for stress and a 20 for cycles. 1.2Development of pressure vessel construction codes Numerous boiler explosions took place through the l
46、ate 1800s and early 1900s. This led to the enactment of the fi rst code for construction of steam boilers by the Commonwealth of Massachusetts in 1907. This subsequently resulted in the development and publication of the ASME Boiler and Pressure Vessel Code in 1914, which sought to standardize the d
47、esign, manufacturing, and inspection of boilers and pressure vessels. In 1921 the National Board of Boiler and Pressure Vessel Inspectors was organized to promote consistent inspection and testing. The publication of the section on locomotive boilers also appeared in 1921. The ASME and the ASTM (Ame
48、rican Society for Testing and Materials) material specifi cation merged in 1924. The fi rst publication of Section VIII Unfi red Pressure Vessels, appeared in 1925. This document was referred to as one of a theoretical factor of safety of 5. The petroleum industry did not consider it to be adequate
49、for their purposes and also desired better utilization of available materials. The year 1928 saw the advent of welded pressure vessels. For higher pressures the welded shells were made thicker than 70 mm. These required nondestructive examination (NDE) before service. In 1934, a joint APIASME Committee published the fi rst edition of an unfi red pressure vessel code specifi cally for the petroleum industry. In 1952 these two separate codes merged into a single code the ASME Unfi red Pressure Vessel Code, Section VIII. The ASME Pressure Vessel Code,