China
Africa
Explore chapters and articles related to this topic
Engineering
Published in H. Selcuk Agca, Giancarlo Cotone, Introduction to Process Plant Projects, 2018
H. Selcuk Agca, Giancarlo Cotone
Flow sheets prepared by process engineering are the following: Process Block Diagrams (Block Flow Diagrams: BFD)PFDsP&IDs Process P&IDsUtility piping and instrumentation diagrams (UIDs, sometimes called utility P&IDs to supplement the ones prepared by utility vendors)Distribution P&IDs (distribution of the process and utility fluids and interconnecting)Symbols P&ID (or P&ID Legend)
Design Safe Processes
Published in James A. Klein, Bruce K. Vaughen, Process Safety, 2017
James A. Klein, Bruce K. Vaughen
In addition, the design of the piping systems used to convey the materials to and from the processing equipment and other equipment or utilities must consider materials of construction, whether flanges can be used or not, the types of valves, and the associated piping support structures. The instrumentation equipment used to monitor, control, and respond to the processing conditions, such as flow rates, temperatures and pressures must be properly designed, as well. Note that a piping and instrumentation diagram (P&ID) is the foundational document used when performing hazards analyses, as it captures the processing equipment, utilities, and other process interconnectivities and the associated piping and instrumentation in one diagram.
Thermal-Hydraulic Characterization and Numerical Modeling with RELAP5 Code of ATHENA Secondary Loop
Published in Nuclear Technology, 2023
Tommaso Del Moro, Fabio Giannetti, Mariano Tarantino, Pierdomenico Lorusso, Marco Caramello, Damiano Vitale Di Maio, Marin Constantin
ATHENA is a large multipurpose pool-type facility, having a power installed of 2210 kW and using pure lead as the primary coolant and pressurized water as the secondary cooling fluid. The large scale of the main vessel (3.2-m diameter and 10-m height) allows one to test the LFR components in relevant scale as well as to reproduce in a reliable way the main phenomena occurring in a large lead-cooled pool-type reactor. The facility will be operated to reproduce the lead thermal cycle as intended in ALFRED, following the steps defined in the staged approach. The design of the facility benefits from the previous experience of ENEA, collected during design activities and experimental campaigns performed on the large pool-type facility CIRColazione Eutettico (Eutectic Circulation)18 (CIRCE) in its Heavy liquid mEtal pRessurized water cOoled tubes19–21 (HERO) and Thermal-hydraulic HElical Tubes Innovative System22,23 (THETIS) configurations, at ENEA Brasimone Research Center. The main vessel layout and the piping and instrumentation diagram of the secondary loop of the facility are shown in Figs. 1 and 2.
Development of Conceptual Lead Cartridge Design to Perform Irradiation Experiments in VTR
Published in Nuclear Science and Engineering, 2022
Seung Jun Kim, Keith Woloshun, Joshua Richard, Jack Galloway, Cetin Unal, Jeffrey Arndt, Michael Ickes, Paolo Ferroni, Richard Wright, Osman Anderoglu, Cemal Cakez, Khaled Talaat, Shuprio Ghosh, Brandon Bohannon
A pump test stand using water was fabricated and tested at LANL for pump performance evaluation. This is a closed loop that replicates the full scale of the cartridge riser and downcomer pipes so as to accommodate pumps scaled 1 to 1 with the actual cartridge dimensions. The downcomer is modified in its lower region to accommodate a valve to vary the pressure drop. This replicates the full range of hydraulic resistance of the fuel or structural material testing inserts and provides the means for generating complete pump curves. This modification also accommodates a conventional flowmeter. The pumps will be driven by a 0.75 horsepower (HP) motor with variable speed control up to 2500 revolutions per minute (rpm). This test stand generates pump curves for all viable mechanical pump designs. Figure 8 shows an isometric view of the test stand and the piping and instrumentation diagram (P&ID). Inert gas will provide an overpressure to determine the pump suction head requirement, as needed.
Experimental Results of PbLi-Water Reaction Performed in LIFUS5/Mod3 Separate Effect Test Facility
Published in Nuclear Technology, 2023
Nicolò Badodi, Antonio Cammi, Marica Eboli, Daniele Martelli, Alessandro Del Nevo
The LIFUS5/Mod3 facility is a separate effect facility derived from the previous configuration LIFUS5/Mod2 (Ref. 18). It was built to simulate the evolution of pressure and temperature transients inside WCLL BB components during in-box LOCA scenarios by injecting varying amounts of water into a PbLi-filled reaction vessel. All the relevant parameters for the experimentation, such as the initial temperature and pressure of the system, and the amount of injected water can be precisely controlled to simulate different system working conditions. A piping and instrumentation diagram (P&ID) of the plant is shown in Fig. 1, and its design features are listed in Table I.