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Safety and Sustainability of Nuclear Energy
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Safety and Sustainability of Nuclear Energy

A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".

Deadline for manuscript submissions: closed (30 March 2023) | Viewed by 4024

Special Issue Editor

Prof. Dr. Yu Yu

E-Mail Website
Guest Editor
School of Nuclear Science and Engineering, North China Electric Power University, Beijing, China
Interests: probability safety analysis; passive system reliability; accident simulation and uncertainty analysis; multi-unit nuclear power plant site risk; analysis; severe accident

Special Issue Information

Dear Colleagues,

Safety is a matter of great concern for nuclear power plants. Deterministic and probabilistic safety analysis are two major methods; they give the insight into safety/risk levels, verify the safety system design according to the requests of the law, recognize the vulnerable factors for safety and give advice for improvement. In recent years, many new theories and methods have been developed along with new types of reactor design. Their use has been increasing not only in nuclear power plants, but also in non-reactor nuclear installations.

This Special Issue aims to present and disseminate the most recent advances related to the theory, method, simulation and analysis of nuclear power plant safety and non-reactor nuclear installations.

Topics of interest for publication include, but are not limited to:

  • Advanced method in PSA for nuclear power plant;
  • Nuclear power plant accident simulation;
  • Experiments for phenomena research in accidents of nuclear power plants;
  • Passive safety system reliability analysis methods;
  • Risk-inform methods for nuclear power plants;
  • Uncertainty analysis in nuclear energy;
  • Safety evaluation methods for non-reactor nuclear installations.

Prof. Dr. Yu Yu
Guest Editor

Manuscript Submission Information

Manuscripts should be submitted online at www.mdpi.com by registering and logging in to this website. Once you are registered, click here to go to the submission form. Manuscripts can be submitted until the deadline. All submissions that pass pre-check are peer-reviewed. Accepted papers will be published continuously in the journal (as soon as accepted) and will be listed together on the special issue website. Research articles, review articles as well as short communications are invited. For planned papers, a title and short abstract (about 100 words) can be sent to the Editorial Office for announcement on this website.

Submitted manuscripts should not have been published previously, nor be under consideration for publication elsewhere (except conference proceedings papers). All manuscripts are thoroughly refereed through a single-blind peer-review process. A guide for authors and other relevant information for submission of manuscripts is available on the Instructions for Authors page. Energies is an international peer-reviewed open access semimonthly journal published by MDPI.

Please visit the Instructions for Authors page before submitting a manuscript. The Article Processing Charge (APC) for publication in this open access journal is 2600 CHF (Swiss Francs). Submitted papers should be well formatted and use good English. Authors may use MDPI's English editing service prior to publication or during author revisions.

Keywords

  • accident simulation
  • system reliability
  • hazard
  • risk-inform
  • uncertainty
  • multi-unit risk
  • fault diagnosis
  • human reliability
  • phenomena
  • modelling

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Further information on MDPI's Special Issue policies can be found here.

Published Papers (2 papers)

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Research

8 pages, 1568 KiB  
Article
The Method of Calculating the Frequency of the Initiating Event in a Dual-Unit Site with the Example of LOOP Events
by Wanxin Feng, Ming Wang, Zhixin Xu and Yu Yu
Energies 2023, 16(2), 903; https://doi.org/10.3390/en16020903 - 12 Jan 2023
Cited by 2 | Viewed by 1760
Abstract
In a nuclear power plant, the consequences of a multi-unit event occurring concurrently are more serious than those of a single-unit event. The first step in the probabilistic safety analysis of multi-units is to analyze the initiating events and calculate the frequency of [...] Read more.
In a nuclear power plant, the consequences of a multi-unit event occurring concurrently are more serious than those of a single-unit event. The first step in the probabilistic safety analysis of multi-units is to analyze the initiating events and calculate the frequency of initiating events for simultaneous events of multiple units. The difficulty in using the fault tree model is that the known data are all frequency data from a single unit and cannot be logically multiplied. In this paper, taking a dual unit as an example, we used the formula to convert the probability of failure of the second unit within 72 h and then build a fault tree model. After analyzing the results of the dual unit, the most frequent cut set was the common cause of failure of the main transformer and of the switching failure of the main and auxiliary external power. The final calculation of the frequency of simultaneous loss of off-site power events for the dual units within 72 h was 3.22 × 10−4/year. After comparing with the single-unit results, it was found that the common cause failure of each unit’s independent equipment was the main reason for the occurrence of a loss of off-site power. Shared equipment in a single unit was ranked low in all the cut sets (such as the stability of the external grid for the main and auxiliary power systems) but was ranked high in multiple units. The calculation results of the frequency of initiating events of double units were two orders of magnitude lower than those of a single unit. However, the consequences of simultaneous events of multiple units were higher than those of single reactors. Therefore, attention should be paid to the risk of a simultaneous loss of off-site power event of multiple units. Full article
(This article belongs to the Special Issue Safety and Sustainability of Nuclear Energy)
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12 pages, 4957 KiB  
Article
Application of Simulated Annealing Algorithm in Core Flow Distribution Optimization
by Zixuan Wang, Yan Wang, Haipeng Xu and Heng Xie
Energies 2022, 15(21), 8242; https://doi.org/10.3390/en15218242 - 4 Nov 2022
Cited by 4 | Viewed by 1655
Abstract
Core flow distribution is closely related to the thermal–hydraulic performance and safety of reactors. For natural circulation reactors with a limited driving force, flow distribution optimization is of particular significance, which can be contrived by suitably assigning the inlet resistance of a core [...] Read more.
Core flow distribution is closely related to the thermal–hydraulic performance and safety of reactors. For natural circulation reactors with a limited driving force, flow distribution optimization is of particular significance, which can be contrived by suitably assigning the inlet resistance of a core assembly channel in reactor design. In the present work, core flow distribution optimization during the fuel life cycle is regarded as a global optimization problem. The optimization objective is to minimize the maximal outlet temperature difference of assembly channels during the fuel life cycle, while the input variable is the inlet resistance coefficient of each assembly channel. The simulated annealing algorithm is applied to the optimization code. The results show that the maximal outlet temperature difference is significantly reduced after optimization, and the resultant core outlet temperature distribution becomes more uniformed. Further evaluation indicates that the optimal solution has good applicability and stability under different reactor conditions. A comparison of the optimization objective function using different temperature difference definitions is also studied in the current study. Full article
(This article belongs to the Special Issue Safety and Sustainability of Nuclear Energy)
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