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Advances in the Thermal Hydraulics of Reactor Engineering and Reactor Safety Analyses

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

Deadline for manuscript submissions: 18 July 2024 | Viewed by 2188

Special Issue Editors

Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Tsinghua University, Beijing 100084, China
Interests: thermal hydraulics of reactor engineering; theoretical modeling and simulation; high-temperature two-phase flow and heat transfer; pebble flow gas-cooled reactor core; reactor safety analysis; particle flow

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Guest Editor
Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Tsinghua University, Beijing 100084, China
Interests: two-phase flow; loss of coolant accident; density instability in ocean condition; thermal hydraulics of reactor engineering; tokamak plasma

Special Issue Information

Dear Colleagues,

The Guest Editor is inviting submissions to a Special Issue of Energies on the subject area of “Advance in Thermal Hydraulics of Reactor Engineering and Reactor Safety Analysis”. The most crucial factor for fission nuclear energy is reactor safety. Thermal hydraulics continues to be an important area of exploration when it comes to comprehending the safety operation and design of nuclear systems. Specifically,the thermal-hydraulic analysis of thermodynamics, fluid mechanics, and heat transfer can be used to determine critical reactor design parameters. In addition, the technology for reactor accident (flow boiling crisis, flow instability, and loss of coolant accidents) mitigation and prevention is necessary for the system’s optimization and safety assessments of nuclear power plants. The reliability of thermal-hydraulic computer codes in predicting consequences of severe accidents and the specification of appropriate accident management strategies are main challenges in mitigating potential severe accidents in nuclear safety analyses.

This Special Issue invites all researchers from nuclear reactor academia and industry to share their latest important results to advance the fields of thermal hydraulics and reactor safety. Submissions of high-quality research papers on the above topics are welcome, particularly those demonstrating a high level of academic discussion and communication. Topics of interest for publication include but are not limited to the following:

  • Nuclear thermal hydraulics;
  • Nuclear safety analysis;
  • Thermodynamics;
  • Fluid mechanics;
  • Heat transfer;
  • Flow boiling crisis;
  • Flow instability;
  • Loss of coolant accident;
  • Computational fluid dynamics;
  • Severe accident analysis.

Dr. Nan Gui
Dr. Xiaoxi Zhang
Guest Editors

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.

Published Papers (1 paper)

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Research

13 pages, 3670 KiB  
Article
Uncertainty and Sensitivity Analysis of Hydrogen Source Term under Severe Accident of Marine Reactor
by Yuqing Chen and Haifeng Wang
Energies 2023, 16(1), 130; https://doi.org/10.3390/en16010130 - 23 Dec 2022
Cited by 1 | Viewed by 1428
Abstract
In order to explore the hydrogen source term characteristics under severe accidents of marine pressurized water reactors (PWR) and effectively assess the hydrogen risk, the best estimation program SCDAP/RELAP5/MOD3.2 is used to establish the marine reactor severe accident analysis model. Based on the [...] Read more.
In order to explore the hydrogen source term characteristics under severe accidents of marine pressurized water reactors (PWR) and effectively assess the hydrogen risk, the best estimation program SCDAP/RELAP5/MOD3.2 is used to establish the marine reactor severe accident analysis model. Based on the Latin Hypercube sampling (LHS) method and the Wilks sampling theory, a set of methods for the uncertainty analysis of severe accidents is developed. This method can be applied to the uncertainty and sensitivity analysis of different target parameters. The phenomenon identification and ranking table (PIRT) under the severe accident induced by the break are established, and 14 uncertain parameters are selected as input variables. The established PIRT fills the gap in the uncertainty and sensitivity analysis of severe accidents of marine reactors and provides a reference for subsequent research. The quantitative uncertainty analysis of the calculation results is carried out, and the uncertainty range of hydrogen production is defined. The Spearman correlation coefficient is used to evaluate the sensitivity of input parameters, and the sensitivity of each parameter to hydrogen production is obtained. The results show that under the severe accident caused by the medium equivalent diameter break, the uncertainty range of hydrogen production in the zirconium–water reaction in the pressure vessel is 20.14 kg~22.19 kg with 95% confidence, and the fuel cladding thickness has a significant positive correlation on the hydrogen production. Full article
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