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Welding is the process of joining materials in the manufacturing industry. To maintain the quality of welding results in accordance with established standards, it is necessary to inspect or inspect the product. To find out whether or not there are defects in the product before the next process is carried out, or before the product is marketed, an inspection is usually carried out using a nondestructive testing (NDT) method, namely testing materials without damaging the material being tested. Several types of non-destructive testing, namely, visual checking, penetrant test, radiographic test and magnetic particle test. This article discusses about the welding analysis of stringer tertiary screen at PT PAL Indonesia. To check whether there are defects in the welded joints in the stringer tertiary screen, a visual check and magnetic particle test have been carried out. Based on interpretation using ASME section IX, the test results show that there are several defects such as spatter on the base metal and wormholes which are unacceptable. The finding of this defect has been followed up with re-welding repairs as recommended. For spatter defects, repairs are carried out with the help of an air chipping hammer which functions to clean the spatter from the base metal, then for wormhole defects repairs are carried out by dismantling the weld and re-welding. The results of repeated visual checks and magnetic particle tests after repair showed that the defects had been successfully eliminated. Thus, the welding results on the stringer tertiary screen are acceptable. [ABSTRACT FROM AUTHOR]

Liquefied petroleum gas (propane or butane) is a colorless liquid which readily evaporates into a gas. It has no smell, although it will normally have an odor added to help detect leaks. Liquefied petroleum gas is stored and handled as a liquid when under pressure inside an LPG cylinder. Liquefied petroleum gas cylinders are subjected to various tests to ensure their compliance requirements as per standard. This research studies the durability of welding and performance of base metal of L. P. G. home cylindrical in Kurdistan region. The experiments were carried out on three types of LPG cylinder using in Kurdistan regions A, B, and C and an unformed plate. To carried out the samples and tests during the research we depending on the standard tests for LPG cylinders. Three samples are extracted from each of LPG cylinders and unformed plate for each of tensile test, Bending test and Hardness test according to ISO 6892-2016 and ASME standards from each type of LPG cylinders and from unformed plate to examine the mechanical properties. In addition, chemical compositions also were carried out. These values are compared with standard.

In this article, a structural integrity assessment of ITER Torus Cryo-Pump Housing (TCPH) is presented. TCPH is a penetration structure located on the cryostat cylinder whose main function is to accommodate and support the Torus Cryo-Pump (TCP), connect it to the vacuum vessel (VV), and provide tritium confinement and primary vacuum boundary. The design of the TCPH structure was finalized during the final design review (FDR). After the FDR, based on the manufacturing feasibility study, changes in the design were proposed to facilitate the nondestructive examination of weld joints. To qualify the proposed changes, structural integrity assessment was performed as per Section VIII Div. 2 Part 5 of ASME code by finite-element analysis using ANSYS software. The structural and thermal assessment was done as per TCPH load specification for protection against plastic collapse, local failure, ratcheting, buckling, and fatigue to perform the structural integrity of the TCPH. The results obtained from the integrity assessment qualified the design criteria. Margins available over allowable stress values for plastic collapse, local failure, and ratcheting are 20%, 19%, and 30%, respectively. A buckling factor of 79 was achieved with a minimum allowable value of 13.42. For fatigue, a usage fraction of 0.516 was obtained against allowable maximum value of 1. Thus, the design with proposed changes was qualified and incorporated. [ABSTRACT FROM AUTHOR]

• The design of the EC window unit, already optimized by FEM analysis, was advanced by ASME III-NC and the manufacturing aspects. • The design of the EC window unit was adapted to the ITER project decision to reduce the inner diameter of the waveguides from 63.5 to 50 mm. • The design of the EC window unit is sufficiently mature to start the prototyping and testing activity in view of the ITER final design review. The torus window unit is a very particular component of the ITER EC H&CD upper launcher aiming to provide the primary vacuum and confinement boundary between the vacuum vessel and the transmission lines (TLs). The high power 170 GHz millimeter-wave beams generated by the gyrotrons travel along the TLs and pass through the window units, before being quasi-optically guided into the plasma via the upper launchers. The design of the window unit shall thus meet stringent requirements to guarantee the safety function, the millimeter-wave beam transmission and the structural integrity during normal operation and off-normal events. The unit consists of an ultra-low loss CVD diamond disk brazed to two copper cuffs; this structure is then integrated into a metallic housing by welding. The compliance with the requirements shall be assured by applying the ASME Section III – Subsection NC code and a dedicated experimental qualification program. This paper reports the way in which the design of the unit, already optimized by FEM analyses against the ITER loading conditions, was further improved by the application of the ASME III-NC code, leading to a more feasible and simpler manufacturing and assembling sequence. In addition, the impact of the ITER project decision to change the inner diameter of the waveguide from 63.5 to 50 mm, to improve the beams' mode purity, was assessed and it is also discussed. Different materials for the metallic housing and in particular for the millimeter-wave inserts of the unit were compared using appropriate engineering criteria to mitigate the significant increase of the millimeter-wave thermal loads on the waveguides when the diameter is decreased. [ABSTRACT FROM AUTHOR]

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Conventional analysis methods for piping systems have incorporated many conservative assumptions. Some of these assumptions can be abandoned by employing advanced analyses, thus allowing for higher loads, which can lead to further uprating of the system without physically intervening with it. This paper shows the procedure of uprating the design seismic load of an existing pipeline through advanced analyses. First, it was discovered that the seal between the pipe and the wall in fact represents a support which is even stiffer than an engineered, purposely built support. Secondly, analyses demonstrate that a pipeline built of thin wall pipes can sustain significant lateral deformation (ovalization and indentation), imposed by seismically induced relative displacements between the buried pipe and building wall penetration, without breaching the pipe wall. This finding is supported by the fact that the pipe passed the flattening test. In the pipeline qualification procedure, the stress state in the dented pipe wall is compared with the stress state during the flattening test. All relevant stress indicators (stress intensities) at the uprated loading state were smaller than allowed by the applicable code or obtained from the flattening test; thus, the pipeline qualified for uprated seismic conditions. [ABSTRACT FROM AUTHOR]

Highlights • An experimental set up is being developed for studying thermo-fluid MHD phenomenon. • The maximum magnetic field achievable is 1.4 T in the polar area of 400 × 1000 mm2 and a pole gap of 370 mm. • Detailed engineering analysis has been performed for the design optimisation of components & loop. • Pipe flexibility analysis has been performed to accommodate the thermal stresses in the loop piping. • Selection of MHD test mock ups has been done for first phase of MHD experiments. Abstract In the frame of the design and development of Liquid breeder blankets, a number of R & D activities are in progress in the area of liquid metal technology development. In presence of strong plasma confining toroidal magnetic field, motion of electrically conducting liquid metal leads to Magneto Hydro Dynamic (MHD) phenomena, as a consequence of which liquid metal flow profile changes inside the flow channels of liquid breeder blankets and additional pressure drop occurs due to the flow opposing Lorentz force (J × B). For the design and development of liquid breeder blankets, 3D MHD flow needs to be studied for various flow configurations as present in the liquid breeder blankets. A lead lithium (Pb-Li) MHD loop is being developed at IPR to perform MHD experiments for Pb-Li flow in various flow geometry such as U-bend, transition zones, circular pipes, sudden expansion and contraction, etc. The test mock ups will be placed in a uniform magnetic field up to 1.4 T, produced by a C-shaped Iron core electromagnet with a pole gap of 370 mm. Both Isothermal and thermo-fluid MHD experiments are being planned for MHD database generation and code validation. [ABSTRACT FROM AUTHOR]

This study evaluates the structural feasibility of a prismatic pressure vessel using strength assessments. A prismatic pressure vessel, which differs from a cylindrical or spherical pressure vessel, is proposed. A prismatic pressure vessel can be used to ship liquefied gas. A prototype of the prismatic pressure vessel was designed, manufactured and tested in accordance with the ASME Boiler and Pressure Vessel Code. Its design uses the “design-by-analysis” method, including protection against plastic collapse. The prototype of the prismatic pressure vessel uses typical construction materials considering their linear elastic and nonlinear plastic behaviors. The vulnerable components of the structure were obtained through numerical analysis using the finite element method. A pressure test with strain gauges was conducted, and the results demonstrate the feasibility of the prismatic pressure vessel as a suitable vessel for high-pressure fluids with high volume efficiencies. The prismatic pressure vessel has potential for general applicability in the shipping of liquefied gas. [ABSTRACT FROM AUTHOR]

Indian negative-ion source development program has gained momentum with planned integration of Indian Test Facility (INTF) for International Thermonuclear Experimental Reactor (ITER)—Diagnostic Neutral Beam (DNB) characterization at the Institute for Plasma Research (IPR). Eight RF driver-based negative-ion source, being developed for DNB will be tested and operated in INTF. The Two driver-based Indigenously built Negative ion source (TWIN) source provides a bridge between the operational single driver-based negative-ion source test facility, ROBIN in IPR, and an ITER-type multidriver-based ion source. The source is designed to be operated in continuous mode with 180 kW, 1 MHz, 5-s on/600-s off duty cycle and also in 5-Hz modulation mode with 3-s on/20-s off duty cycle for three such cycles. The complete design of TWIN source and its test facility, from conceptual to detailed engineering, has been carried out in IPR. The manufacturing design has been optimized to match the capability of Indian manufacturers, without compromising on the specifications. Some examples of optimization are: 1) an improvised design of the Faraday shields where electrodeposition has been replaced by vacuum brazing; 2) a simplified design of the side walls of the plasma source, where jointing process is simplified, without the application of Electron Beam Welding; and 3) introduction of a fiber reinforced polymer-based integrated electrical and vacuum isolation scheme that replaces the application of a large ceramic. Finite-element analysis (FEA) based on heat load and structural load calculation ensure the functionality and structural integrity of each component of the source. Due to nonnuclear environment in TWIN source experimental area, vacuum brazing is an acceptable manufacturing process. The contract for manufacturing of the ion source has been awarded to an Indian manufacturing company for the first indigenous production of a large-size fusion grade ion source. TWIN source is designed in such a way that it can be operated both in air mode (RF driver coil antennas are exposed to air) as well as vacuum mode. (Whole source is immersed inside vacuum.) The TWIN source shall be manufactured as per ASME guidelines for pressure vessel. Experiments on the TWIN source are foreseen in the last quarter of 2015, as all the auxiliary systems such as 180-kW, RF generator system, vacuum vessel with pumping station, cooling water system, data acquisition and control system, and other power supply systems are already installed in the lab premises. This paper discusses the FEA-based engineering design, simplified manufacturing design, manufacturing experience with highlighting quality control, and the system integration activities undertaken for the TWIN source test facility. [ABSTRACT FROM PUBLISHER]

This research proposed a prismatic pressure vessel for gas-fuel storage on a gas-fuelled ship. The prismatic pressure vessel consisted of flat-plated shells, stiffeners, and beam structures. According to the design principle of pressure vessels, the beam structures were designed to receive tensile stresses generated from the internal pressure. International regulations and a finite element analysis were considered for the design, strength calculations, fatigue assessments, plastic collapse, and thermal effects. A case study in which the prismatic pressure vessel was applied as a gas-fuel tank to provide ship propulsion on a crude-oil tanker was performed. Nine per cent nickel steel was used to be applicable for cryogenic service. Several design loadings were considered to evaluate the design feasibility of the pressure vessel. The computational analysis results indicated that the prismatic pressure vessel satisfied the design regulations and should be applicable for use as a gas-fuel storage tank for ships. [ABSTRACT FROM AUTHOR]

Gasketed bolted flange joints are used in process industry for connecting pressure vessels and pipes. Design procedures available in the literature mostly discuss structural strength, while sealing failure is still a big concern in industries. Similarly, limited work is found in the literature regarding performance of gasketed bolted joints under combined loading. A detailed 3D nonlinear finite element analysis is performed to study the strength and sealing of a gasketed bolted flanged pipe joint under different bolt-up strategy (Industrial and ASME) and under combined internal pressure and axial loading. [ABSTRACT FROM AUTHOR]

Recent advances in the digitization of manufacturing have prompted ASME and International Organization for Standardization (ISO) standards committees to reexamine the definition of datums. Any new definition of datums considered by the standards committees should cover all datum feature types used in design and support both traditional metrological methods and new digital measurement techniques. This is a challenging task that requires some careful compromise. This paper describes and analyzes various alternatives considered by the standards committees. Among them is a new mathematical definition of datums based on constrained least-squares fitting. It seems to provide the best compromise and has the potential to support advanced manufacturing that is increasingly dependent on digital technologies., Competing Interests: Conflict of Interest There are no conflicts of interest.

The ITER blanket Shield Block is a bulk structure to absorb radiation and to provide thermal shielding to vacuum vessel and external vessel components, therefore the most significant load for Shield Block is the thermal load. In the previous study, the thermo-mechanical analysis has been performed under the inductive operation as representative loading condition. And the fatigue evaluations were conducted to assure structural integrity for Shield Block according to Structural Design Criteria for In-vessel Components (SDC-IC) which provided by ITER Organization (IO) based on the code of RCC-MR. Generally, ASME code (especially, B&PV Sec. III) is widely applied for design of nuclear components, and is usually well known as more conservative than other specific codes. For the view point of the fatigue assessment, ASME code is very conservative compared with SDC-IC in terms of the reflected K e factor, design fatigue curve and other factors. Therefore, an accurate fatigue assessment comparison is needed to measure of conservatism. The purpose of this study is to provide the fatigue usage comparison resulting from the specified operating conditions shall be evaluated for Shield Block based on both SDC-IC and ASME code, and to discuss the conservatism of the results. [ABSTRACT FROM AUTHOR]

In a national project, with the aim to develop a robust method for structural verification of pressure equipment subjected to ratcheting, a two-rod test approach is developed. Two testing machines, with one specimen in each, are controlled in such way that a constant primary load and a cyclic secondary load are applied on the specimens. The ferritic steel P265 and the austenitic steel 316L are tested for a number of load combinations. Test results show that ratcheting is produced in all tests. As expected, the amount of ratcheting increases with the load level. At the start of a two-rod test, structural ratcheting dominates over material ratcheting. Depending on the load level and combination of primary load and cyclic secondary load, material ratcheting might eventually become more important. Based on results from tensile testing and fully-reversed strain controlled cycling, five different constitutive models are calibrated. The possibility to simulate the response of the conducted experiments with the different models is investigated. The most advanced model investigated, i.e. the nonlinear kinematic Chaboche model, does not necessarily give the best predictions. Up to a strain level of 5%, i.e. the criterion in ASME NB-3228.4, the bi-linear model best predicts the experiments. Recommendations for how ratcheting in structures subjected to cyclic plastic deformation can be predicted by numerical simulation are given. [ABSTRACT FROM AUTHOR]