• Nuclear Engineering and Technology
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• v.56 no.11
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• pp.4905-4913
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• 2024

This study focuses on the Structure, System, and Components (SSC) of G.A Siwabessy Multipurpose Reactor (RSG-GAS), emphasizing the integration of reliability improvement within asset management optimization. The research aims to derive Maintenance Priority Index (MPI) values, contributing to system reliability ratings, crucial for assessing component functionality and estimating Remaining Useful Life (RUL) The methodology involves measuring critical aspects of system quality, safety, and cost. The MPI value, representing 10 % of SSC critical components, guides subsequent reliability calculations. Utilizing failure data from RSG-GAS components (2010-2018) and reactor core configurations (70th-96th core), SSC reliability is simulated using Monte Carlo simulation, with RUL based on real data. High MPI values are identified for critical components such as KBE01/AP01-02_B in the primary purification system, JE-01/AP01-02_A in the primary cooling system, and PA01-02/CR001_A in the secondary cooling system. Maintenance intervals of 100 days are recommended for KBE01/AP 01-02_B and JE-01/AP01-02_A, exceeding 50 % reliability, while PA01-02/CR001_A maintenance can extend to 75 days. Monte Carlo simulation results, with 1000 samples, closely align with real reliability values. The RUL result projects operational lifetimes of 225.6, 221.4, and 171.5 days for KBE01/AP 01-02_B, JE-01/AP01-02_A, and PA01-02/CR001_A components. This study improves asset management, offering practical insights for critical safety system component maintenance planning.

• International conference on construction engineering and project management
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• 2020.12a
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• pp.353-358
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• 2020

Recent efforts to develop a common standard for nuclear power plants (NPPs) with the aim of creating (1) a digital environment for a better understanding of NPPs life-cycle management aspect and (2) engineering data interoperability by using existing standards among different unspecified project participants (e.g., owners/operators, engineers, contractors, equipment suppliers) during plants' life cycle process (EPC, O&M, and decommissioning). In order to meet this goal, there is a need for formulating a standardized high-level physical breakdown structure (PBS) for NPPs project management office (PMO). However, high-level PBS must be comprehensive enough and able to represent the different types of plants and the new trends of technologies in the industry. This has triggered the need for addressing the issues of the recent operational NPPs and future technologies' ramification for evaluating the changes in the NPPs physical components in terms of structure, system, and component (SSC) configuration. In this context, this ongoing study examines the recent conventional NPPs and technological trends in the development of future NPPs facilities. New reactor models regarding the overlap of variant issues of nuclear technology were explored. Finally, issues on PBS for project management are explored by the examination of the configuration of NPPs primary system. The primary systems' configuration of different reactor models is assessed in order to clarify the need for analyzing the new trends in nuclear technology and to formulate a common high-level PBS. Findings and implications are discussed for further studies.