Becht Engineering Blog

Download/View as PDF Summary - This article assists engineers in selecting ASME XI options for the repair of ASME III nuclear components. In summary, the repair options in ASME XI are dispersed throughout Section XI and Code Cases, while, in contrast, the ASME PCC-2 repair standard (for non-safety related components) lists repair options in a well-structured manner. So, we are going to use the structure of ASME PCC-2 as a road map to cross-correlate the equivalent ASME XI repair, where it exists. Therefore, the Table can be used as a checklist to remind engineers of the many repair options. On one hand …. ASME XI : The repair of safety-related Class 1, 2, and 3 nuclear components is addressed in ASME Boiler & Pressure Vessel Code Section XI and in a series of ASME XI Code Cases. The use of ASME XI and its Code Cases to select a repair technique...

Compliance with the Process Safety Management rule, OSHA 1910.119, is a requirement for plants processing certain highly hazardous materials exceeding threshold quantities. The rule requires the owner to demonstrate all equipment has been purchased and installed in accordance with recognized industry standards. Maintenance practices must also be according to Recognized and Generally Accepted Good Engineering Practice (RAGAGEP) . The owner must document this information as part of the Process Safety Information and Mechanical Integrity program for the plant. Use of Codes The use of codes and standards can help assure compliance with the rule. For example ASME Section VIII is the recognized code for construction of pressure vessels operating in the United States at pressures over 15 psi. It would be difficult to debate vessels could be designed and built to other requirements and still be acceptable under the PSM rule. Codes such as the ASME code have been developed and...

Before we tackle environmentally-assisted fatigue (EAF), what is fatigue? In ASME Boiler & Pressure Vessel Section III Division 1, Subsection NB (in short, ASME III NB) fatigue refers to the damage caused by systems and components as a result of cyclic loads. The qualification of the primary coolant system of light water reactors (ASME III Class 1 components) must address the fatigue damage caused by pressure and thermal cycling of the equipment and piping during their design life. How is fatigue life analysed and qualified for 40 years, 60 years, or more of service? The fatigue analysis and qualification is achieved by following a procedure outlined in ASME III Div.1 Subsection NB for Class 1 piping and components. This procedure can be outlined in five key steps: STEP-1 TRANSIENTS : Developing the thermal and pressure transients, in the form of time-dependent functions P i (t) and T i (t). For each...

Overview Fluid Catalytic Cracking (FCC) units were first developed in the 1930s. Over the years this technology has evolved and it is one of the most important processes used in refineries. The FCC units are used to convert high boiling point, high molecular weight hydrocarbon fractions of crude oils to gasoline, olefinic gases, and other products. There are a number of process technology providers who license proprietary FCC technology; however, the equipment is basically the same ─ a reactor vessel where the hydrocarbon feed and hot catalyst contact and react (~950F) producing hydrocarbon vapors for further processing, and a regenerator vessel where the carbon laid down on the surface of catalyst from the reaction is burned off (regenerated and heated) in a fluidized bed (~1350F). The regenerated catalyst is returned to the reactor. The catalyst circulation between the reactor and regenerator is continuous. Large diameter refractory lined piping (transfer lines) circulate the...