Updating of local blockage frequency in the reactor core of SFR and PRA on consequent severe accident in Monju

Nishimura, Masahiro; Fukano, Yoshitaka; Kurisaka, Kenichi; Naruto, Kenichi

doi:10.1080/00223131.2017.1344576

Journal of Nuclear Science and Technology

2017

DOI: 10.1080/00223131.2017.1344576

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Updating of local blockage frequency in the reactor core of SFR and PRA on consequent severe accident in Monju

Masahiro Nishimura

Yoshitaka Fukano

Kenichi Kurisaka

et al.

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Cited by 3 publications

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“…In the European Union (EU), 34 initiating events in six categories were identified for the Advanced Lead-cooled Fast Reactor European Demonstrator (ALFRED) using the MLD method [16]. In Japan, 77 internal initiating events in 15 categories were identified for the prototype sodium-cooled fast reactor MONJU via a combination of MLD and Engineering Evaluation methods [17]. Shanghai Institute of Applied Physics (SINAP) of China screened 37 initiating events in six categories of Thorium-based Molten Salt Reactor with Solid Fuel (TMSR-SF1) by MLD and the Reference List method [9].…”

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confidence: 99%

Research on Initiating Events Analysis of Small Helium-Xenon Gas Cooled Nuclear Reactor

Zhou,

Wu,

Cui

et al. 2023

Energies

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Initiating event analysis is an essential prerequisite of conducting probabilistic safety assessment for nuclear reactors, which plays an important role in improving the core design, identifying fault, and guiding operation. In order to determine the initiating event list of SIMONS (Small Innovative helium-xenon cooled Mobile Nuclear power System), preliminary researches on the initial event of SIMONS were carried out using the MLD (Main Logic Diagram) analysis method and referring to the initial event list and initial event analysis theory of other nuclear reactors such as HTGR (High Temperature Gas-cooled Reactor), MSR (Molten Salt Reactor), and PWR (Pressurized water reactor). With employing these methods, a total of 31 initial events are identified for SIMONS based on its latest conceptual design. These initial events are then divided into six groups according to the accident types, which are core heat removal increase, core heat removal decrease, abnormal reactivity and power distribution, pipeline crevasse and equipment leakage, anticipated transients without scram, and disasters (internal and external). The obtained results can provide a theoretical basis for the further safety analysis of SIMONS.

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confidence: 99%

Research on Initiating Events Analysis of Small Helium-Xenon Gas Cooled Nuclear Reactor

Zhou,

Wu,

Cui

et al. 2023

Energies

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“…Probabilistic Risk Assessment (PRA) on local fault (LF) which was initiated from local flow blockage (LB) was performed reflecting the state-of -the-art knowledge in this study. As the result, damage propagation from LF caused by LB in Monju can be negligible compared with the core damage due to Anticipated Transient without Scram (ATWS) or Protected Loss of Heat Sink (PLOHS) in the viewpoint of both frequency and consequence [2]. From Fukushima accident lessons learned, the feasibility of shared use of the Alternate AC Diesel Generator (AAC DG) under a dual-unit Station Blackout (SBO) was investigated.…”

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confidence: 99%

Recent activities in the field of Nuclear Operational Management and Nuclear Safety Engineering

Muta

2019

Journal of Nuclear Science and Technology

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Recent activities in the field of Nuclear Operational Management and Nuclear Safety Engineering, the studies related to risk analysis methodology, design, and operational management, physical phenomena, and emergency preparedness and nuclear security, have been progressed. Especially, 'risk analysis methodology' and 'design and operational management' are the main categories of the field, in which more than half of published articles on Journal of Nuclear Science and Technology are related to these categories.

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Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor

Fukano

2019

Journal of Nuclear Engineering and Radiation Science

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Local subassembly faults (LFs) have been considered to be of greater importance in safety evaluation in sodium-cooled fast reactors (SFRs) because fuel elements were generally densely arranged in the subassemblies (SAs) in this type of reactors, and because power densities were higher compared with those in light water reactors. A hypothetical total instantaneous flow blockage (HTIB) at the coolant inlet of an SA gives most severe consequences among a variety of LFs. Although an evaluation on the consequences of HTIB using SAS4A code was performed in the past study, SAS4A code was further developed by implementing analytical model of power control system in this study. An evaluation on the consequences of HTIB in an SFR by this developed SAS4A code was also performed in this study. It was clarified by the analyses considering power control system that the reactor would be safely shut down by the reactor protection system triggered by either of 116% over power or delayed neutron detector (DND) trip signals. Therefore, the conclusion in the past study that the consequences of HTIB would be much less severe than that of unprotected-loss-of-flow (ULOF) was strongly supported by this study. Furthermore, SAS4A code was newly validated using four in-pile experiments which simulated HTIB events. The validity of SAS4A application to safety evaluation on the consequence of HTIB was further enhanced in this study. Thus, the methodology of HTIB evaluation was established in this study together with the past study and is applicable to HTIB evaluations in other SFRs.

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Updating of local blockage frequency in the reactor core of SFR and PRA on consequent severe accident in Monju

Cited by 3 publications

References 3 publications

Research on Initiating Events Analysis of Small Helium-Xenon Gas Cooled Nuclear Reactor

Research on Initiating Events Analysis of Small Helium-Xenon Gas Cooled Nuclear Reactor

Recent activities in the field of Nuclear Operational Management and Nuclear Safety Engineering

Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor

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