Computational Techniques of Nuclear Reactor Physics
Deadline for manuscript submissions: closed (31 August 2021) | Viewed by 15560
The peaceful use of nuclear energy technologies contributes to the production of electricity in many countries for energy independence. Major shifts and trends towards electrification and hydrogen fuel cells in the transportation energy sector present opportunities for future nuclear power increase in market share in the world energy economy. As part of these nuclear energy technologies, the reactor physics field interprets neutron behavior and fission reaction distributions inside reactors using computational tools, contributing to the analysis of heat pathways and the diagnosis of the fuel condition over time.
This Special Issue seeks any scientific discoveries and qualitative research outputs about improved accuracy of reactor core analysis methods/codes/tools, sensitivity analysis and uncertainty quantification, artificial intelligence technique applications, and multiphysics analysis through linkage with other research areas. Furthermore, discussions about countermeasures against the problem of spent nuclear fuel saturation based on calculation results, future technologies for securing economic nuclear fuel resources, the fourth-generation nuclear power reactor design techniques, nuclear non-proliferation technologies, and validation studies against experimental data are always welcome.
We therefore invite papers on innovative technical developments, reviews, case studies, analytical, as well as assessment, papers from different disciplines, which are relevant to computational code system for nuclear reactor core analysis.
Prof. Dr. Deokjung Lee
Manuscript Submission Information
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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.
- Neutron transport method
- Neutron diffusion method
- Monte Carlo method
- Sensitivity analysis and uncertainty quantification
- Best estimates plus uncertainty
- Artificial intelligence techniques
- Machine learning
- Multiphysics analysis
- Analyses of the fourth generation reactors
- Verification and validation