The Study of Mechanical Failure in Helical Steam Generator of High Temperature Gas-Cooled Reactor (HTGR)

Authors

  • Muhammad Subhan Research Centre for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency, Building No. 80 BJ Habibie Science and Technology Area, South Tangerang 15314, Indonesia
  • Topan Setiadipura Research Centre for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency, Building No. 80 BJ Habibie Science and Technology Area, South Tangerang 15314, Indonesia
  • Mohammad Dhandhang Purwadi Research Centre for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency, Building No. 80 BJ Habibie Science and Technology Area, South Tangerang 15314, Indonesia
  • Muksin Aji Setiawan Research Centre for Nuclear Reactor Technology, Research Organization for Nuclear Energy, National Research and Innovation Agency, Building No. 80 BJ Habibie Science and Technology Area, South Tangerang 15314, Indonesia
  • Tresna Priyana Soemardi Department of Mechanical Engineering, Faculty of Engineering, Universitas Indonesia, Kampus UI Depok 16424, Indonesia
  • Aryo Sunar Baskoro Department of Mechanical Engineering, Faculty of Engineering, Universitas Indonesia, Kampus UI Depok 16424, Indonesia
  • Cecep Slamet Abadi Department of Mechanical Engineering, State Polytechnic of Jakarta, Kampus UI Depok 16425, Indonesia
  • Evi Latifah Department of Mechanical Engineering, State Polytechnic of Jakarta, Kampus UI Depok 16425, Indonesia
  • Nafisah Amalia Department of Mechanical Engineering, State Polytechnic of Jakarta, Kampus UI Depok 16425, Indonesia
  • Yusi Amalia Renaningtyas Department of Mechanical Engineering, State Polytechnic of Semarang, Tembalang Semarang 50275, Indonesia

Keywords:

Nuclear reactor, Mechanical Failure, Helical, Steam Generator

Abstract

This research examines mechanical damage in helical steam generators, focusing on the causes, contributing factors, and impact of damage on the performance of the steam generator (SG). The research methodology involves analyzing various data sources, including scientific literature and previous nuclear industry experiences. The analysis results indicate that thermal stress, pressure fluctuations, material wear, and design errors can cause mechanical damage in helical SGs. Volumetric defects and leaks at pipe joints or welds are also potential issues. This study provides insights into failure mechanisms and highlights the importance of routine maintenance and inspection to prevent more serious failures. By better understanding these issues, innovative solutions can be developed to improve the performance and safety of helical steam generators in nuclear reactors.

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Published

2026-03-05

How to Cite

Subhan, M., Setiadipura, T., Purwadi, M. D., Setiawan, M. A., Soemardi, T. P., Baskoro, A. S., … Renaningtyas, Y. A. (2026). The Study of Mechanical Failure in Helical Steam Generator of High Temperature Gas-Cooled Reactor (HTGR). Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega, 26(3), 101–106. Retrieved from https://ejournal.brin.go.id/tridam/article/view/15526

Issue

Vol. 26 No. 3 (2024): October 2024

Section

Articles