: This chapter addresses ASME Code Section XI, Subsections IWE and IWL, for nuclear power plant containments. Subsection IWE provides requirements for preservice and inservice examination/inspection, repair/replacement (R/R) activities, and testing of Class MC (metal containment) pressure-retaining components and their integral attachments and R/R activities. It also provides requirements for testing of Class CC (concrete containment) pressure-retaining components and their integral attachments for boiling water reactors (BWRs) and pressurized water reactors (PWRs). Similarly, Subsection IWL provides requirements for preservice and inservice examination/inspection, R/R activities, and testing of the reinforced concrete and post-tensioning systems of Class CC components for BWRs and PWRs. Together with Subsection IWA, a comprehensive basis is provided for ensuring the continued structural and leak-tight integrity of containments in nuclear power plants. The chapter includes a brief history of the development of ASME Code requirements, the latest information on the U.S. Nuclear Regulatory Commission regulatory review and incorporation of recent ASME Code Editions and Addenda, and current listings of U.S. ‘construction-complete’ commercial nuclear power plants and their containment types and operating status. A summary of recent nuclear industry developments in advanced plant designs and a discussion of the as-yet-unrealized ‘U.S. nuclear renaissance’ are also presented, along with information on the global demand for energy and the current status of commercial nuclear power around the world. Lastly, the current Subsection IWE and IWL Commentaries, as approved and maintained by the ASME Working Group on Containment, are included.

This chapter describes the bases and provisions of the ASME Boiler and Pressure Vessel Code for Concrete Containments. It describes the concrete containment general environment, types of existing containments, future containment configurations, and background development including the regulatory bases of concrete containment construction code requirements. The chapter addresses reinforced-concrete containment behavior under internal pressure and temperatures of up to about 100°C. The discussion presented includes a comparison between prestressed and deformed-bar concrete reinforcements, the effects of elevated temperature on concrete, and the effect of radial and tangential shear in containment shells. It explains the analysis, design, and testing of concrete containment structures and provides information on the organization of the Concrete Containment Design Code contained in the Code Section III, Division 2, Subsection CC. The chapter summarizes the following requirements for concrete containments: general and specific construction or placement requirements for concrete, including the fabrication and placing requirements for steel reinforcement systems and the fabrication and welding requirements for liners; requirements for nondestructive examinations, procedure qualifications and evaluations; requirements for qualification and certification of nondestructive personnel; and general requirements for containment structural integrity test. The major areas to be considered in the future revisions of the Code are also highlighted in this chapter.on and certification of nondestructive personnel; and general requirements for containment structural integrity test. The major areas to be considered in the future revisions of the Code are also highlighted in this chapter. History John D. Stevenson was the original author of this chapter and updated it for the second edition. The third edition was updated by Joseph F. Artuso, Hansraj Ashar and Barry Scott. The fourth edition was updated by Arthur Eberhardt, Michael Hessheimer, Ola Jovall and Clayton Smith. The fifth edition was updated by Arthur C. Eberhardt, Clayton T. Smith, Ola Jovall and Christopher A. Jones. The current online edition was updated by Arthur C. Eberhardt and Christopher A. Jones.

ASME Section XI, Subsection IWE, Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water-Cooled Plants , provides requirements for preservice and inservice examination/inspection, repair/replacement activities, and testing of Class MC (metal containment) pressure-retaining components and their integral attachments and repair/replacement activities and testing of Class CC (concrete containment) pressure-retaining components and their integral attachments for Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs). Similarly, Subsection IWL, Requirements for Class CC Concrete Components of Light-Water-Cooled Plants , provides requirements for preservice and inservice examination/inspection, repair/replacement activities, and testing of the reinforced concrete and post-tensioning systems of Class CC (concrete containment) components for BWRs and PWRs. Together with Subsection IWA, General Requirements , a comprehensive basis is provided for ensuring the continued structural and leak-tight integrity of containments in nuclear power plants.

A novel steel concrete composite vessel (SCCV) technology has been developed as a cost-effective solution for stationary high-pressure gaseous hydrogen storage applications. SCCV technology is flexible to meet different pressure levels and storage capacities. SCCV has layered steel vessel wall and strategically placed vent holes to solve the safety concerns of hydrogen embrittlement (HE) problem for high-strength steel by design. A demonstration vessel capable of storing approximately 90 kg gaseous hydrogen at 6250 psi (43 MPa) has been designed and fabricated to demonstrate the SCCV technical feasibility. Hydrotest and cyclic hydrogen pressure test are used to validate both constructability and performance of the SCCV. Critical design parameters and the test data are reviewed.

Design analysis is performed for a novel, low-cost, high-pressure, steel/concrete composite vessel (SCCV) for stationary storage of gaseous hydrogen. The SCCV comprises an inner, layered steel vessel encased by an outer pre-stressed concrete sleeve. The vessel design calculations are established based on engineering formulae from ASME Boiler and Pressure Vessel Code. A SCCV cost modeling tool is developed by considering the detailed bill of materials and labor costs for each of the vessel manufacturing steps. Using the vessel design calculations and cost modeling tool, the SCCV designs are studied for three pressure levels (i.e., 16, 43 and 86 MPa) relevant to the hydrogen production and delivery infrastructure. The effect of vessel dimensions on SCCV cost is discussed.

Initial requirement defect identification and their mitigation is the key aspect in planning the development of the system. In this paper we are trying to identify potential requirement defect through Inspection Technique and setting defect severity as well their priority to mitigate. Here, we propose a Framework for Reliable Requirement Specification (RRS) consisting three major component 1) Input component in the form of Initial Requirement 2) Free Wheel Processing Assembly as the combination of Defect Identification Technique, Requirement Defect, Severity & priority and Defect Mitigation 3) Output component in the form of Reliable Requirement Specification. The importance of this research is to construct initial requirement defect free and also make it capable to deliver the concrete, high quality and reliable requirement for the further phases of the Software Development.

This chapter describes the general requirements of Section III applicable to all Classes of construction, including steel vessels, piping, pumps, and valves, as well as concrete structures. It identifies how to classify components and describes how the jurisdictional boundaries of Section III define what is within and outside the scope of the Code. Use of Code Editions and Addenda and Code Cases is explained. The requirements for Design Basis, Design and Construction Specifications, and Design Reports are described. Furthermore, the chapter addresses the responsibilities and Quality Assurance Program requirements of the different entities involved in constructing a nuclear power plant, from the manufacturer of materials to the Owner. Requirements for ASME accreditation, application of the ASME Code Symbol Stamp, and use of Code Data Reports are also described.

This Chapter describes the bases and provisions of the Code for Concrete Containments. It describes the concrete containment general environment, types of existing containments, future containment configurations, and background development including the regulatory bases of concrete containment construction code requirements. The description covers sequentially the following topics: Introduction, Concrete Reactor Containments, Types of Containments, Future Containments, Regulatory Bases for the Code Development, Background Development of the Code, Reinforced Concrete Containment Behavior, Containment Design Analysis and Related Testing, Code Design Requirements, Fabrication and Construction, Construction Testing and Examination, Containment Structural Integrity Testing, Containment Overpressure Protection, Stamping and Reports, Containment Structure and Aircraft Impact, Containment and Severe Accident Considerations, Other Relevant Information, Summary and Conclusion. The original editions of this chapter were developed by John D. Stevenson. Additional information relating to the regulatory basis for the code requirements, future containments and considerations for future revisions to the code was provide by Hansraj Asher, Barry Scott and Joseph Artuso. The basic format of this chapter is kept the same as in the previous editions. The current edition of this chapter brings the material up to date with the 2010 version of the Code and was prepared by Joseph Artuso, Arthur Eberhardt, Michael Hessheimer, Ola Jovall and Clayton Smith.

ASME Section XI, Subsection IWE, Requirements for Class MC and Metallic Liners of Class CC Components of Light-Water Cooled Plants , specifies requirements for preservice and inservice examination/inspection, repair/replacement activities, and testing of Class MC (metal containment) pressure-retaining components and their integral attachments and repair/replacement activities and testing of Class CC (concrete containment) pressure-retaining components and their integral attachments for Boiling Water Reactors (BWRs) and Pressurized Water Reactors (PWRs). Similarly, Subsection IWL, Requirements for Class CC Concrete Components of Light-Water Cooled Plants , specifies requirements for preservice and inservice examination/inspection, repair/replacement activities, and testing of the reinforced concrete and the post-tensioning systems of Class CC (concrete containment) components for BWRs and PWRs. Together with Subsection IWA, General Requirements , a comprehensive basis is provided for ensuring the continued structural and leak-tight integrity of containments in nuclear power facilities. The U.S. Nuclear Regulatory Commission (USNRC or NRC) incorporated the requirements of the 1992 Edition with the 1992 Addenda of Subsections IWA, IWE, and IWL into the Code of Federal Regulations (CFR) in an amendment of Title 10, Part 50.55a (10 CFR 50.55a) [4] that was published in the Federal Register (FR) on August 8, 1996. This amendment, 61 FR 41303 [5], contained rules that provided requirements in addition to those in Subsections IWE and IWL, and also specified that certain provisions in these Subsections were optional and not required for regulatory compliance. The rulemaking also required that all nuclear power plants in the United States develop and implement a containment inspection program in accordance with Section XI, Subsections IWA, IWE, and IWL (as applicable for the type of containment) by September 9, 2001. On September 12, 1999, the USNRC amended this rulemaking in a subsequent rulemaking, 64 FR 51370 [6], to incorporate by reference the 1995 Edition with the 1996 Addenda of Subsections IWA, IWE, and IWL into 10 CFR 50.55a. The rule also allowed Owners to continue to use the 1992 Edition with the 1992 Addenda of these Subsections for the containment inspection program, if so desired. The effective date for this amendment was November 22, 1999. Again, this rulemaking included several requirements in addition to those of ASME Section XI, and is also required that the Owners of all nuclear power plants in the United States develop and implement a containment inspection program by September 9, 2001.

Cement is the substance which holds concrete together, i.e. it is extremely widely used in civil projects. Consequently, application of nano-materials into the production of cement and concrete can lead to improvements in sustainable engineering because the mechanical strength and life of concrete structures are determined by the micro-structure and by the mass transfer in nano-scale. Nano-SiO2 in many countries is produce in industrial scale these days. So, this paper is going to evaluate the compressive strength and the permeability of nano-SiO2 stabilized concrete samples. The Critical Voltage Method (CVM) was used to investigate the later property; So 6 mix designs with different nano-SiO2 percents were tested. The results showed that by increasing the nano-SiO2 content, the electrical resistance of concrete is increased. So, nano-SiO2 can improve the water permeability resistance of concrete. The same concept was occurred for the compressive strength.

The paper presented the evaluation of properties waste paper sludge aggregate (WPSAA) as replacement of normal coarse aggregate in concrete. The mining activity of normal coarse aggregate was produced a lot of problem such as noise pollution, air pollution and landslide. In addition, the high human population were created a lot of waste material such as fly ash, waste paper sludge ash and bottom ash. Other issues, the area of waste material for landfill was limited. With a lot of problem existed, Waste Paper Sludge Ash (WPSA) from newspaper industry was designed to replace the normal coarse aggregate. First part, the WPSA was measured for the chemical properties and physical properties. Then, The WPSA was manufactured by using ratio WPSA to water (2:1), mixed, pelletized, dried and lastly sintered in the oven for 1 day with 200°C. The physical and mechanical of the WPSA was determined. From the physical result, the WPSAA was categorised as high water absorption aggregate and showed WPSAA as lightweight aggregate. For further experiment, the compressive strength of concrete with the proportion from 0.5 % until 4.0 % was determined. The result shown the mix with 2.0 % WPSAA was classified as appropriate percentage to generate better compressive strength with low cost production.

Effect of cementing material type on foam concrete under different water ratio, fly ash content and foam content was studied by the method of orthogonal experimental design, in which compressive strength, apparent density and thermal conductivity was considered as the evaluation index. It was found that, on the condition of same quantity of cementing materials, the order of influencing significance on compressive strength of different cementing material was: rapid-hardening sulphate aluminium cement (RSC) > ordinary Portland cement (PO) > Portland slag cement (PS), the order of influencing significance on apparent density was: PS > RSC > PO, and that of thermal conductivity was RSC > PO > PS. The optimum test data of compressive strength, apparent density and thermal conductivity was 5.74MPa, 203kg/m 3 and 0.041W/m.k −1 respectively.

Root file system is an important component of Linux embedded system. It is the beginning point of all files and device modules, and the key whether the system can have a normal start. Combined with the characteristics of the embedded system, this paper introduces how to use Busybox tool to construct embedded root file system whose name is Cramfs and how to transplant Cramfs to a concrete ARM development platform. Simultaneously, we proposed a new approach to configure the root file system. And this approach can support requirements of reading and writing based on applications, it doesn't need to add extra file system, but only use own characteristics of root file system to construct a partial writable root file system. Finally, it is tested in the actual development board that verified the new root file system generated validity and reliability.

Determination of the effect of the physical and mechanic properties that the aggregates have on concrete strength is only possible with the tests conducted. These studies take a long time and mostly are not economic. Therefore, different methods formed by utilizing the experimental studies done before are used to determine the strength characteristics. Results obtained from the model formed with the strength properties of concrete made by setting off from the physical characteristics that the largest component aggregate forming the concrete have and the results obtained with Linear Regression are compared in this study. Concretes complying with TS 706 standards have been prepared by keeping all components other than the aggregate forming the concrete constant and the 7 and 28 days compressive strengths of these concretes have been measured. The values determined experimentally have been estimated by developing models in Artificial Neural Networks and Linear Regression methods. 20 variables including crushed sand, Specific Weight of fine aggregate and coarse aggregate, Water Absorption, Dry Unit Weight, Bulk Density, Tight Unit Weight, Los Angeles Abrasion Strength, Fineness Modulus, and Flatness Modules have been used at the input stratum and 7 and 28 days compressive strengths have been used at the output stratum. It has been observed at the comparisons that the training and test results in the models can be estimated very close to test results.

Because of the quo that IPv4 and IPv6 will coexist for a long time in the internet, it is inevitable to share resources between the IPv4 and IPv6 network. The article puts forward a method based on the reverse proxy to share resources of two networks. It is more convenient and more effective. There is an concrete example to demonstrate how to realize the case in the article.

The pre-stressed concrete composite slab is a kind of new-type structure form in floor construction of industry and civil building structure. In the present paper, the inverted T composite slab is produced, which has great advantages over traditional slab. To study the characteristic of the inverse T composite, the numerical simulation is done to analyze the stress and deformation distribution in the T composite slab of precast fabricated construction as well as the stress distribution of the steel bar, whose result will give some guidance for the real practice.

Firstly, this paper analyzes requirement of QualiPSo Factory, and illustrates the basic functions which Factory should have. Secondly, this paper puts forward the overall service architecture of Factory. This paper also illustrates Factory from the perspectives of service release, resources management and search, security access control, logging and so on, and proposes concrete implements and test methods.

This study dealt with risk-based analysis for design of concrete channel and grass-swale at Lima Kedai, Skudai, Johor. Recent trends in the design of channel and other structures are towards the use of risk analysis. The risk value for both concrete channel and grass-swale was evaluated using mathematical models in this study. The peak flow obtained using Rational Method for grassed swale and concrete with trapezoidal channel were 7.584 m3/s and 10.4 m3/s respectively. The drainage sizes (trapezoidal) for grassed swale was larger compared to concrete channel. The dimension for grassed swale was 1.6 meter (base width), 0.6 meter (depth) and 6.4 meter (surface width). Concrete channel size was 1.25 meter (base width), 0.5 meter (depth) and 5.25 meter (surface width). Overflow risk varies with elapse time (time to peak), whereby grassed swale has lower risk at lower drain time (recession time) and increased with increasing the drain time. The lowest overflow risk obtained were 0.207 (MASMA) and 0.250 (Rapid disposal). The overflow risk for highest elapse and drain time was 0.456 for grassed swale and 0.453 for rapid disposal (concrete). It is suggested to design at lower elapse and drain time to minimize the overflow risk.

Iron ore tailing (IOT) is a waste material from the iron ore mining processes and constitutes a nuisance both to human health and the environment. A study on its use as a cement replacement material was initiated in Civil Engineering Programmed, Abubakar Tafawa Balewa University, Bauchi, Nigeria. The preliminary tests carried out on the material showed that it has potentials for improving cement mortar and concrete properties. Setting times of cement is delayed and heat of hydration reduced by about 29 percent when cement was replaced with 40 percent IOT by mass. The workability of the concrete was also improved and compressive strength at 10 percent and beyond 28 days of curing compared favourably with the reference mix. The ratio of the flexural strength to splitting tensile strength was about 1.7.