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Studies on Nuclear Reactors

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

Deadline for manuscript submissions: 10 September 2024 | Viewed by 1764

Special Issue Editor


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Guest Editor
Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai 201800, China
Interests: reactor design and analysis; reactor physics and neutronics; nuclear fuel cycles; innovative reactors and new applications

Special Issue Information

Dear Colleagues,

In the pursuit of the goals of achieving peak carbon emissions and carbon neutrality, nuclear energy, as a clean energy source, is an effective way of meeting global energy demands. The application of nuclear reactors has been increasing, not only in electricity supply, but also in heat supply, seawater desalination, high temperature hydrogen production, etc. In recent years, many innovative nuclear reactor concepts, including molten salt reactors, very high temperature reactors, gas-cooled fast reactors, lead-cooled fast reactors, sodium-cooled fast reactors, and supercritical water reactors, have been proposed. Furthermore, nuclear reactors are designed at different scales (small modular reactors, microreactors, etc.) for specific application scenarios, such as mobile power supply, deep-sea operation, and space operation.

This Special Issue aims to present and disseminate the most recent advances related to the theory, experiment, design, and application of all types of nuclear reactors.

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

  • Reactor design and analysis;
  • Reactor thermal hydraulics and safety;
  • Reactor physics and neutronics;
  • Nuclear fuel cycles;
  • Innovative reactors and new applications;
  • digital reactor and new technology;
  • Waste management, spent fuel, decommissioning.

Dr. Chunyan Zou
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

  • nuclear reactor
  • nuclear fuel cycle
  • nuclear waste transmutation

Published Papers (2 papers)

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Research

19 pages, 21319 KiB  
Article
Research on Neutronics Safety Parameters of the AP1000 Nuclear Reactor under Different Conditions
by Xinyi Niu, Jianquan Liu, Zenghao Dong, Jie Wei and Wenlong Zhou
Energies 2023, 16(22), 7549; https://doi.org/10.3390/en16227549 - 13 Nov 2023
Viewed by 819
Abstract
Changes in temperature during reactor operation may cause changes in physical parameters, leading to core overheating and accidents. It is essential to analyze and assess the safety parameters of the core under different operating conditions. This paper investigates the effects of fuel temperature, [...] Read more.
Changes in temperature during reactor operation may cause changes in physical parameters, leading to core overheating and accidents. It is essential to analyze and assess the safety parameters of the core under different operating conditions. This paper investigates the effects of fuel temperature, moderator density, boron concentration, and control rod state on AP1000 safety parameters. The study uses RMC and NJOY to calculate the changes in reactivity factor, effective delayed neutron fraction, and neutron generation time of the AP1000 reactor under different operating conditions. The changes in reactivity coefficients, neutron fluxes, and relative power densities of AP1000 reactors are analyzed for normal and accidental operating conditions. The results indicated that the reactivity coefficient remained negative under accident conditions, which ensured the safe operation of the reactor. The delayed neutron fraction, neutron flux, and power density distributions are affected by fuel temperature, moderator density, and control rod position. The control rod worth was sufficient for the emergency shutdown of the reactor under accidental conditions. It is demonstrated that the operation of the AP1000 reactor under study conditions is safe and controllable. Full article
(This article belongs to the Special Issue Studies on Nuclear Reactors)
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20 pages, 4645 KiB  
Article
Quantitative Analysis Study of Effects of Nuclide Concentration Uncertainties on Biases and Bias Uncertainties in Criticality Calculation Method
by Zining Ni, Xirong Chen, Jinsen Xie, Muhammad Abdul Wasaye and Tao Yu
Energies 2023, 16(21), 7378; https://doi.org/10.3390/en16217378 - 31 Oct 2023
Viewed by 583
Abstract
To quantify the uncertainties propagating from the fuel depletion calculation to the criticality calculation in the burnup credit system, this paper evaluates the effects of the nuclide concentration uncertainty on the criticality calculation based on Monte Carlo uncertainty sampling methods, and analyzes the [...] Read more.
To quantify the uncertainties propagating from the fuel depletion calculation to the criticality calculation in the burnup credit system, this paper evaluates the effects of the nuclide concentration uncertainty on the criticality calculation based on Monte Carlo uncertainty sampling methods, and analyzes the assumption that the measured-to-calculated nuclide concentration ratio obeys a normal distribution with uncorrelation among isotopes in the Monte Carlo uncertainty sampling method by using the sensitivity and uncertainty analysis method and the Latin hypercube sampling method. The results indicated that the Monte Carlo uncertainty sampling method could effectively quantify the uncertainties with a calculation accuracy within 3%, and the criticality uncertainty calculation for the assumption that the measured-to-calculated concentration ratios obey normal distributions was more conservative than that of the samples according to their actual distributions. Thus, the assumption of a normal distribution is reasonable in the sampling process. Moreover, the uncertainty results of the criticality calculation considering the correlations among important isotopes presented a decrease of approximately 5% over those without the isotopic correlations. Therefore, introducing the correlations of significant isotopes could reduce the uncertainty of the criticality calculation for spent-nuclear-fuel storage systems. Full article
(This article belongs to the Special Issue Studies on Nuclear Reactors)
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