The Becht Team
Code Committee Expertise
Presentations and Publications
Becht Nuclear Services
Fossil and Alt Power
Fitness for Service
Corrosion and Metallurgical
Software and Solutions
Becht Training Signup
Owner's Project Support
Becht Training Courses
Becht Info Request
Login to your account
Forgot your password?
Forgot your username?
Becht Engineering Blog
In this section of the site contributing authors submit interesting articles relating to the various services, industries and research & development efforts of Becht Engineering.
Subscribe to this list via RSS
ASME Section VIII, Division 1 - 2019 Edition - Changes to U-2(g)
Thursday, 27 June 2019
What Do You Do When There Are No Rules? On July 1, 2019, the 2019 Edition of ASME Section VIII, Division 1 will be published. Among the 117 changes to this Edition will be a revised paragraph U-2(g), and a new Mandatory Appendix 46. The new U-2(g) will read: (g) This Division of Section VIII does not contain rules to cover all details of construction. Where complete details of construction are not given, the Manufacturer, subject to the acceptance of the Authorized Inspector, shall provide the appropriate details to be used. (1) Where design rules do not exist in this Division, one of the following three methods shall be used: (-a) Mandatory Appendix 46; (-b) Proof test in accordance with UG-101; (-c) Other recognized and generally accepted methods, such as those found in other ASME/EN/ISO/National/Industry Standards or Codes. This option shall provide details of design consistent with...
Allowable Design Stress
ASME Section VIII Division 1 U-2(g)
Repair of Pressure Equipment and Piping in Nuclear Power Plants- Navigating ASME XI Repairs with PCC-2 as a Roadmap
Wednesday, 15 February 2017
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...
Recent comment in this post
Guest — Andy Hall
A Comprehensive Read.
Thank you George for the wonderful post on ASME XI Repairs. I deal with Pressure Vessel Equipment repair. Recently, I have been do...
Sunday, 22 October 2017 08:07
Importance of Codes and Standards for Process Safety
Monday, 14 November 2016
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...
Environmentally-Assisted Fatigue (EAF) in Nuclear Power Plants
Wednesday, 14 September 2016
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...
Subscribe To Becht Blogs
I agree to allow the site to collect my data solely for the use of subscriptions
Subscribe to our blog
Becht Blog Categories
Materials Degradation and Corrosion
Fitness for Service
Turnaround Services/Inspection Planning
Becht Laser Scanning/Dimensional Control
Training & Mentoring
Click to View Becht’s Current Technical Training Public Course Calendar