State of the Art Mapping of the Initiating Event Identification Methods by Bibliometric Analysis

DOI: https://doi.org/10.22146/ajche.19479
Keywords: Nuclear Reactor, Process Safety, Reference Analysis

Abstract

Probabilistic Safety Assessment (PSA) can be used to evaluate the safety of Nuclear Power Plants (NPPs). To improve NPPs’ safety, reactor safety technology is always developing. Each technology will have a different hazard that can cause an Initiating Event (IE). Of course, this development will affect IE. IE is the event that can affect normal operation and have the potential to cause worst-case conditions when the mitigation system does not work properly. A comprehensive, detailed bibliometric analysis of NPP PSA and IE remains absent from the literature. The objective of this paper is to discuss existing research and identify future trends through bibliometric analysis and a literature review in the PSA and IE domains. The search criteria include the keywords, publication period, publication type, and language. Ninety-five scientific papers were identified during the first screening and were included in the bibliometric analysis. The Bibliometric analysis will represent the keyword network using VOSviewer 1.6.20. The second screening stage is used to strengthen the analysis and generate 43 articles as objects for the literature review. The results showed that the topic of identifying and developing identification methods has not been widely discussed and has become an important research topic. The results of this analysis strengthen the research hypothesis that developing IE methods for new technology NPPs, including High Temperature Gas Cooled Reactors (HTGRs), is feasible.

References

Afshar, N., Pirouzmand, A., Faghihi, F., 2021. “VVER-1000/V446 spent fuel pool risk assessment and support through portable mitigating equipment.” Ann. Nucl. Energy 156. 108204. https://doi.org/10.1016/j.anucene.2021.108204

Ameyaw, F., Abrefah, R., Yamoah, S., Birikorang, S., 2021. “Analysis and estimation of core damage frequency of flow blockage and loss of Coolant Accident: A case study of a 10 MW water-water research reactor-PSA Level 1.” Scie. Technol. Nucl. Install. 1, 9423176. https://doi.org/10.1155/2021/9423176

Ameyaw, F., Abrefah, R.G., Yamoah, S., Fletcher, J.J., Birikorang, S.A., 2018. “A review for identification and selection of initiating events important for Level 1 probabilistic safety assessment study for a 10 MW water water research reactor (VVR).” Ann. Nucl. Energy 115, 303–314. https://doi.org/10.1016/j.anucene.2018.01.039

Arigi, A.M., Park, G., Kim, J., 2020. “Dependency analysis method for human failure events in multi-unit probabilistic safety assessments.” Reliab. Eng. Syst. Saf. 203. 107112. https://doi.org/10.1016/j.ress.2020.107112

Arigi, A.M., Park, J., Lim, H.K., Kim, J., 2020. “Analysis of human-induced initiating events in a multi-unit loss of offsite power scenario.” J. Nucl. Sci. Technol. 57, 121–132. https://doi.org/10.1080/00223131.2019.1661305

Baas, J., Schotten, M., Plume, A., Côté, G., Karimi, R., 2020. “Scopus as a curated, high-quality bibliometric data source for academic research in quantitative science studies.” Quant. Sci. Stud. 1, 377–386. https://doi.org/10.1162/qss_a_00019

BinKhadim, S. A., Zubair, M. A., 2024. “Preliminary safety inspection methodology in the UAE using AIMS-PSA for risk assessment of APR1400 LOCA transients.” Prog. Nucl. Energ. 169. https://doi.org/10.1016/j.pnucene.2024.105069

Bogalecka, M., Dąbrowska, E., 2023. “Monte Carlo simulation approach to shipping accidents consequences assessment.” Water 15 (10). 1824. https://doi.org/10.3390/w15101824

Budi, R.F.S., Ariyanto, S., Salimy, D.H., Nurmayady, D., Amitayani, E.S., Nuryanti., Anzhar, K., Nurulhuda, E., Nurlaila., 2024. “Scaling law method for cost estimation of Indonesia’s first HTGR (PeLUIt-40) and its implementation strategy.” Nucl. Eng. Des. 423. 113195. https://doi.org/10.1016/j.nucengdes.2024.113195

Čepin, M., 2018. “Application of shutdown probabilistic safety assessment.” Reliab. Eng. Syst. Saf. 178, 147–155. https://doi.org/10.1016/j.ress.2018.05.012

Chisholm, B.M., Krahn, S.L., Fleming, K.N., 2020. “A systematic approach to identify initiating events and its relationship to probabilistic risk assessment: Demonstrated on the molten salt reactor experiment.” Prog. Nucl. Energ. 129. 103507. https://doi.org/10.1016/j.pnucene.2020.103507

Choi, J., Seok, H., 2021. “Development of risk assessment framework and the case study for a spent fuel pool of a nuclear power plant.” Nucl. Eng. Techol. 53, 1127–1133. https://doi.org/10.1016/j.net.2020.09.011

Coleman, J. F., Boafo, E. K., Yamoah, S., Ameyaw, F., 2023. “Assessing the impact of common cause failures on site risk within level 1 multi-unit PSA.” Sci. Tech. Nucl. Install. 2023, 5889803. https://doi.org/10.1155/2023/5889803

Deng, J., Xu, Y., Qiu, Z., Zhang, H., Wu, L., Wang, X., Peng, H., Du, Z., 2020. “Research on level 1 PSA and risk-informed design for ACP100.” Ann. Nucl. Energy 144. 107542. https://doi.org/10.1016/j.anucene.2020.107542

Deswandri, D., Sudarno, S., Tyas, R. L., Kumaraningrum, A. R., Maerani, R., Hidayatullah, I. M., Sahlan, M., Shariff, A. M., Hermansyah, H., 2024. “Risk identification of integral pressurized water reactor (IPWR) cooling system using a combination HAZOP, FMEA, and FTA methods.” Process Saf. Prog. 43. 12570. https://doi.org/10.1002/prs.12570

Foerster, E., Girault, N., Helminen, A., 2022. “Probabilistic safety assessment for internal and external events on nuclear power plants and on mitigation strategies/H2020 European projects NARSIS, R2CA and BESEP.” EPJ Nucl. Sci. Technol. 8, 23. https://doi.org/10.1051/epjn/2022014

Hamza, M., Joslin, N., Lawson, G., McSweeney, L., Liao, H., Vivanco, A., Diaconeasa, M. A., 2024. “Identifying and quantifying a complete set of full-power initiating events during early design stages of high-temperature gas-cooled reactors.” Reliab. Eng. Syst. Saf. 242. 109688. https://doi.org/10.1016/j.ress.2023.109688

Hashem, E. A. R., Md. Salleh, N. Z., Abdullah, M., Ali, A., Faisal, F., Nor, R. M., 2023. “Research trends, developments, and future perspectives in brand attitude: A bibliometric analysis utilizing the Scopus database (1944–2021).” Heliyon 9. e12765. https://doi.org/10.1016/j.heliyon.2022.e12765

IAEA. 2019. Deterministic safety analysis for nuclear power plants (SSG-2). IAEA International Atomic Energy Agency.

Jeong, J., Cho, D. K., 2020. “A method for operational safety assessment of a deep geological repository for spent fuels.” J. Nucl. Fuel Cycle Waste Technol. 18, 63–74. https://doi.org/10.7733/jnfcwt.2020.18.S.63

Jung, Y. H., Kang, D. I., 2020. “Construction and quantification of a fire probabilistic safety assessment model using support system initiating event fault trees.” Ann. Nucl. Energ. 138. 107180. https://doi.org/10.1016/j.anucene.2019.107180

Kamyab, S., Nematollahi, M. R., Hadad, K., 2018. “Using MCNP for success criteria evaluation of reactor trip function in probabilistic modeling of ATWS upon LOOP.” Prog. Nucl. Energ. 106, 270–277. https://doi.org/10.1016/j.pnucene.2018.02.011

Kang, D. I., Jung, Y. H., 2018. “Comparative study on the construction of support system initiating event fault trees for a fire probabilistic safety assessment.” Nucl. Eng. Des. 332, 345–356. https://doi.org/10.1016/j.nucengdes.2018.03.038

Kang, D. I., 2020. “Study on construction of loss of component cooling water system initiating event fault tree for fire event PSA.” J. Nuc.l Sci. Technol. 57, 79–89. https://doi.org/10.1080/00223131.2019.1659871

Kiflee, A. K. R., Hasbullah, N. N., Madli, F., 2024. “Corporate social responsibility-sustainability nexus: A systematic literature review and bibliometric analysis.” Int. J. Ind. Eng. Prod. Res. 35 (2). 1968. https://doi.org/10.22068/ijiepr.35.2.1968

Kim, B., No. H. C., 2019. “Application of Wilks’ formula and concept of state change time to integrated deterministic and probabilistic safety assessment for evaluation of the safety margin of DEC accidents.” Nucl. Eng. Des. 352. 110195. https://doi.org/10.1016/j.nucengdes.2019.110195

Kim, D. S., Park, J. H., Lim, H. G., 2020. “Technical note: Estimation of Korean industry-average initiating event frequencies for use in probabilistic safety assessment.” Nucl. Eng. Technol. 52, 211–221. https://doi.org/10.1016/j.net.2019.06.028

Kim, H., Kim, J. T, Heo, G., 2018. “Failure rate updates using condition-based prognostics in probabilistic safety assessments.” Reliab. Eng. Syst. Saf. 175, 225–233. https://doi.org/10.1016/j.ress.2018.03.022

Kim, M. C., 2023. “Rigorous derivation of interfacing system LOCA frequency formulas for probabilistic safety assessment of nuclear power plants.” Reliab. Eng. Syst. Saf. 238. 109470. https://doi.org/10.1016/j.ress.2023.109470

Kim, T., 2018. “Frontier between medium and large break loss-of-coolant accidents of pressurized water reactor.” Desal. Water Treat. 110, 355–361. https://doi.org/10.5004/dwt.2018.22347

Lee, Y. H., Jang, S. C., 2021. “Effects of a change in the design of cooling water injection on risk reduction in a beam tube rupture.” Ann. Nucl. Energ. 161. 108455. https://doi.org/10.1016/j.anucene.2021.108455

Lee, Y. H., 2019. “A design-phase probabilistic safety assessment of a research reactor to enhance its safety.” Ann. Nucl. Energ. 131, 367–377. https://doi.org/10.1016/j.anucene.2019.04.007

Lee, Y. H., 2021. “Risk-informed approach for safety improvement of domestic research reactor.” Ann. Nucl. Energ. 156. 108173. https://doi.org/10.1016/j.anucene.2021.108173

Lim, H. K., Park, J. H., 2020. “Effects of house load operation on PSA based on operational experiences in Korea.” Nucl. Eng. Technol. 52, 2812–2820. https://doi.org/10.1016/j.net.2020.05.018

Maskin, M., Hassan, A., Brayon, F. C., Phongsakorn, P. T., Zakaria, M. F., Ramli, Z., Mohamed, F., 2018. “Quantification of initiating event frequencies and component reliability data in level 1 probabilistic safety assessment at Puspati TRIGA research reactor.” Ann. Nucl. Energ. 121, 22–28. https://doi.org/10.1016/j.anucene.2018.07.013

Mendizábal, R., Sánchez, M., Queral, C., Hortal, J., Martorell, S., Pelayo, F., Freixa, J., 2024. “Activities in Spain on the integration of probabilistic and deterministic safety analysis methods. Discussion on their applicability to DEC-A scenarios.” Nucl. Eng. Des. 419. 112944. https://doi.org/10.1016/j.nucengdes.2024.112944

Mikhalycheva, E. A, Trifonov, A. G., 2024. “Application of Probabilistic Safety Analysis to the Emergency Scenarios Assessment of a Loss of Coolant Accidents in the VVER-Reactor Plant.” Nonlin. Phenom. Comp. Syst. 27, 69–77.

https://doi.org/10.5281/zenodo.10889768

Mohsendokht, M., Hadad, K., Jabbari, M., 2018. “Reducing the loss of offsite power contribution in the core damage frequency of a VVER-1000 reactor by extending the house load operation period.” Ann. Nucl. Energ. 116, 303–313. https://doi.org/10.1016/j.anucene.2018.01.030

Picoco, C., Rychkov, V., 2023. “A pragmatic approach to update support studies and human reliability analyses for a PSA model.” Nucl. Sci. Eng. 197, 2778-2786. https://doi.org/10.1080/00295639.2023.2196227

Piwowar-Sulej, K., Sołtysik, M., Jarosz, S., Pukała, R., 2023. “The linkage between renewable energy and project management: what do we already know, and what are the future directions of research?” Energies 16 (12). 4609. https://doi.org/10.3390/en16124609

Purba, J. H., 2018. “Master logic diagram: An approach to identify initiating events of HTGRs.” In: Journal of Physics: Conference Series, Institute of Physics Publishing. https://doi.org/ 10.1088/1742-6596/962/1/012036

Riyandwita, B. W, Subhan, M., Setiadipura, T., Amelia, A. C., Hastuty, S., Kadarno, P., Sulistyo, F. Y., 2023. “Design scenario and analysis for preliminary specification of steam generator in The Peluit-40.” Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega. 25, 15. https://doi.org/10.55981/tdm.2023.6778

So, E., Kim, M. C., 2021. “Level 1 probabilistic safety assessment of supercritical–CO2–cooled micro modular reactor in conceptual design phase.” Nucl. Eng. Technol. 53, 498–508. https://doi.org/10.1016/j.net.2020.07.029

Tabadar, Z., Ansarifar, G. R., Pirouzmand, A., 2019. “Probabilistic safety assessment of portable equipment applied in VVER-1000/V446 nuclear reactor during loss of ultimate heat sink accident for stress test program development.” Prog. Nucl. Energ. 117. 103101. https://doi.org/10.1016/j.pnucene.2019.103101

Trianti, N., Widiawati, N., Wulandari, C., Miftasani, F., Rohanda, A., Khakim, A., Setiadipura, T., 2023. “Optimum power determination and comparison of multi-pass and OTTO fuel management schemes of HTGR-based PeLUIt reactor.” Nucl. Eng. Des. 415. 112696. https://doi.org/10.1016/j.nucengdes.2023.112696

Tyas, R. L., Purba, J. H., Sukmana, J., 2024. “The Evaluation of Postulated Initiating Events of RSG-GAS using HAZOP Method.” AIP Conf. Proc. 2967, 010001. https://doi.org/10.1063/12.0024027

Tyas, R. L., Purba, J. H., Sukmana, J., 2023. “The evaluation of postulated initiating events of RSG-GAS using HAZOP method.” AIP Conf. Proc. 2967, 130021. https://doi.org/10.1063/5.0192827

Vechgama, W., Silva, K., Pechrak, A., Wetchagarun, S., 2021. “Application of hazard and operability technique to level 1 probabilistic safety assessment of Thai Research Reactor-1/Modification 1: Internal events and human errors.” Prog. Nucl. Energ. 138. 103838. https://doi.org/10.1016/j.pnucene.2021.103838

Yoon, J. Y., Kim, D. S., 2022. “Estimating the adverse effects of inter-unit radioactive release on operator actions at a multi-unit site.” Reliab. Eng. Syst. Saf. 228. 108764. https://doi.org/10.1016/j.ress.2022.108764

Yu, S., Zhang, J., Labeau, P. E., 2024. “Safety margin quantification by integrating probabilistic and deterministic safety assessments — Application to design extension conditions.” Nucl. Eng. Des. 421, 113121. https://doi.org/10.1016/j.nucengdes.2024.113121

Zhou, J., Wu, J., Cui, Y., Zhao, H., Zou, C., Chen, J., 2023. “Research on initiating events analysis of small helium-xenon gas cooled nuclear reactor.” Energies 16 (19). 6769. https://doi.org/10.3390/en16196769

Zubair, M, Ishag, A., 2018. “Sensitivity analysis of APR-1400’s reactor protection system by using RiskSpectrum PSA.” Nucl. Eng. Des. 339, 225–234. https://doi.org/10.1016/j.nucengdes.2018.09.019

Published
2025-12-31
How to Cite
Tyas, R. L., Hermansyah, H., Purba, J. H., & Widuri, N. R. (2025). State of the Art Mapping of the Initiating Event Identification Methods by Bibliometric Analysis. ASEAN Journal of Chemical Engineering, 25(3), 518-535. https://doi.org/10.22146/ajche.19479
Issue
Vol 25 No 3 (2025)
Section
Articles

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