专题：Nuclear reactor physics and engineering

This cluster of papers covers advanced nuclear reactor technology, including topics such as molten salt reactors, neutron transport, Generation IV reactors, the thorium fuel cycle, and small modular reactors. It also discusses the development and application of Monte Carlo codes, lead-cooled fast reactors, transmutation processes, and nuclear data libraries.
最新文献
Molten Salt Reactors and Thorium Energy

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Parallel connected natural circulation loops using different working fluids: experimental results

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Overview of Small Modular and Advanced Nuclear Reactors and Their Role in the Energy Transition

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Validation of the dynamic simulation capabilities of Serpent2/Subchanflow using experimental data from the research reactor SPERT IV D-12/25

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Core design optimization of a 200 MWt pressurized water SMR using evolutionary simulated annealing

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Optimization of the Second Target Station cold source moderators using an automated workflow

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239Pu Be neutron reference field: Physical and dosimetric parameters

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Time-dependent leakage model for the identification of defective fuel assemblies of VVER-type nuclear reactors, part 1: Theory

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NuScale-like SMR Model Development and Applied Safety Analyses with the Code Chain Serpent-DYN3D-ATHLET

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Helium bubble evolution under cascade in bcc iron relevant to fusion conditions investigated by a novel coupling MD-OKMC method

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近5年高被引文献
When and why PINNs fail to train: A neural tangent kernel perspective

article Full Text OpenAlex 878 FWCI78.76187722

The NUBASE2020 evaluation of nuclear physics properties *

article Full Text OpenAlex 635 FWCI27.12009819

A comprehensive study of non-adaptive and residual-based adaptive sampling for physics-informed neural networks

article Full Text OpenAlex 443 FWCI227.17541433

The AME 2020 atomic mass evaluation (I). Evaluation of input data, and adjustment procedures*

article Full Text OpenAlex 380 FWCI15.20807212

Self-adaptive physics-informed neural networks

article Full Text OpenAlex 324 FWCI166.15086737

Environmental degradation of structural materials in liquid lead- and lead-bismuth eutectic-cooled reactors

article Full Text OpenAlex 315 FWCI106.18875899

Japanese evaluated nuclear data library version 5: JENDL-5

article Full Text OpenAlex 314 FWCI162.74443395

Nuclear energy: A pathway towards mitigation of global warming

article Full Text OpenAlex 273 FWCI13.82900028

Recent improvements of the particle and heavy ion transport code system – PHITS version 3.33

article Full Text OpenAlex 256 FWCI133.10726866

Review on chromium coated zirconium alloy accident tolerant fuel cladding

article Full Text OpenAlex 255 FWCI15.67286699