Advances in Simulation and Numerical Model of Nuclear Fuel Safety
A special issue of Energies (ISSN 1996-1073). This special issue belongs to the section "B4: Nuclear Energy".
Deadline for manuscript submissions: 8 January 2025 | Viewed by 468
Special Issue Editor
Interests: nuclear reactor physics; core design of advanced nuclear reactor; nuclear fuel cycle
Special Issues, Collections and Topics in MDPI journals
Special Issue Information
Dear Colleagues,
This Special Issue, entitled “Advances in Simulation and Numerical Model of Nuclear Fuel Safety”, aims to present and disseminate the latest advances in the simulation and experiment of nuclear fuel cycle safety.
The nuclear industry has experienced Gen-I, Gen-II, and Gen-III nuclear reactor systems since the 1950s, with the economy and safety being greatly enhanced as a result. To further improve the performance of reactor systems, Gen-IV advanced reactors, which encompass the gas-cooled fast reactor (GFR), lead-cooled fast reactor (LFR), molten salt reactor (MSR), sodium-cooled fast reactor (SFR), very-high-temperature reactor (VHTR), and super-critical water-cooled reactor (SCWR), were proposed in 2002 by the GIF (Generation IV International Forum) with the aim of achieving commercialization after 2030. Up until now, experimental reactors or demonstration reactors have been successfully built for the LFR, MSR, SFR, and VHTR. Meanwhile, with a growing demand on the exploration of ocean/space and off-grid electricity supply for remote areas, micro-nuclear reactors (power capacity up to 20 MWe) and small modular nuclear reactors (power capacity of up to 300 MWe) have attracted growing attention worldwide.
The nuclear fuel cycle is a complex process, covering the steps of fuel life from uranium/thorium mining, uranium enrichment, fuel element manufacture, fuel burning in the core, and spent fuel processing to the final disposal of spent fuel. Potential safety risks exist in each step of the nuclear fuel cycle, and related issues are a great challenge even for advanced reactor systems due to the introduction of unique technical features. Accident analysis and experiments of nuclear fuel cycle reactors have become paramount for reactor systems’ design and license application. As computing technologies constantly improve, reactor safety analysis approaches real accident conditions with little approximation and can provide more reliable accident assessments. Presenting these latest advances in the nuclear industry would provide a valuable reference for scholars involved in research in the nuclear industry.
In this Special Issue, potential topics of interest include, but are not limited to, the following:
- Accident modeling and analysis of the nuclear fuel cycle;
- Nuclear safety computing codes development, validation, and application;
- Accident probability analysis for micro-nuclear reactors and small modular nuclear reactors;
- Safety analysis in advanced U-Pu and Th-U nuclear fuel cycle;
- Application of machine learning methods in safety analysis of the nuclear fuel cycle.
Dr. Jianhui Wu
Guest Editor
Manuscript Submission Information
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Keywords
- nuclear energy
- nuclear fuel cycle
- nuclear physics
- thermal hydraulics
- nuclear waste management
- nuclear safety calculation code
- micro-nuclear reactor
- modular nuclear reactor
- GEN-IV reactor
- machine learning
- nuclear safety
- radiation shielding
- nuclear control
- nuclear materials
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