The main pipes of reactor coolant systems (RCS) are usually long flexible structures that are connected to multiple key equipment and components of the nuclear system (e.g., reactor pressure vessel, steam generator, main pump, etc.). Mechanical analysis of pipe responses at key elbows and weld seams under static and dynamical load conditions is an essential step to ensure safety and reliability of the whole RCS. Common practice to keep the structural integrity of RCS piping under dynamical load (seismic or shock load) is to impose supporting devices at various locations so that the stiffness at weak spots can be improved. Nevertheless, the introduction of supporting devices, especially the mechanical stops, may cause significant increase of thermal stress due to the block of thermal expansion path of the piping. Hence, cooperative design and optimization of RCS piping supports by jointly considering the piping responses under static and dynamical load cases becomes quite a necessity. In this paper, such an optimal design task is formulated as a multi-objective optimization problem (MOP) with the stress level at key elbows and weld seams of the main pipes as objectives; and various parameters of each supporting device as design variables. The key feature of such MOP is that the number of design variables is unknown in prior. A single support sampling strategy is first proposed to observe the influence of one supporting device. Clustering algorithms are then applied to discover patterns from the single support sampling pool. A 3-snubber-3-stop main pipe support layout is determined via unsupervised clustering algorithms. We perform the surrogatemodel based parameter optimization once the optimization framework is fixed. Simulation results of the optimal piping support design show good satisfactions of stress level according to ASME boiler and pressure vessel code (BPVC) under both static and dynamical load cases. The data-driven design and optimization procedures presented in this paper suit the optimal design with conflicting objectives and unclear number of design variables.
Skip Nav Destination
ASME 2018 Pressure Vessels and Piping Conference
July 15–20, 2018
Prague, Czech Republic
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5163-0
PROCEEDINGS PAPER
Cooperative Design and Optimization of Reactor Coolant System Piping Supports Under Static and Dynamical Load Conditions
Fu-Rui Xiong,
Fu-Rui Xiong
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Bin Lan
Bin Lan
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Fu-Rui Xiong
Nuclear Power Institute of China, Chengdu, China
Bin Lan
Nuclear Power Institute of China, Chengdu, China
Paper No:
PVP2018-84026, V03BT03A040; 12 pages
Published Online:
October 26, 2018
Citation
Xiong, F, & Lan, B. "Cooperative Design and Optimization of Reactor Coolant System Piping Supports Under Static and Dynamical Load Conditions." Proceedings of the ASME 2018 Pressure Vessels and Piping Conference. Volume 3B: Design and Analysis. Prague, Czech Republic. July 15–20, 2018. V03BT03A040. ASME. https://doi.org/10.1115/PVP2018-84026
Download citation file:
34
Views
Related Proceedings Papers
Related Articles
Recommended Revisions to Nuclear Piping Thermal Expansion Stress Limits
J. Pressure Vessel Technol (April,2011)
On Failure Mechanisms in Flip Chip Assembly—Part 1: Short-Time Scale Wave Motion
J. Electron. Packag (June,2008)
A Reliability-Based Approach for the Design of Nuclear Piping for Internal Pressure
J. Pressure Vessel Technol (August,2009)
Related Chapters
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Functionality and Operability Criteria
Companion Guide to the ASME Boiler and Pressure Vessel Code, Volume 2, Third Edition
Functionality and Operability Criteria
Companion Guide to the ASME Boiler & Pressure Vessel Code, Volume 2, Second Edition: Criteria and Commentary on Select Aspects of the Boiler & Pressure Vessel and Piping Codes