Multiscale Approach of Investigating the Density of Simulated Fuel for a Zero Power Reactor.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 420, doi. 10.3390/jne5030026
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- Publication type:
- Article
Works matching IS 26734362 AND DT 2024 AND VI 5 AND IP 3
Results: 13
1
2
Siting Analysis of a Solar-Nuclear-Desalination Integrated Energy System †.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 402, doi. 10.3390/jne5030025
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- Publication type:
- Article
3
The Evaluation of Machine Learning Techniques for Isotope Identification Contextualized by Training and Testing Spectral Similarity.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 373, doi. 10.3390/jne5030024
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- Article
4
First-Order Comprehensive Adjoint Sensitivity Analysis Methodology for Neural Ordinary Differential Equations: Mathematical Framework and Illustrative Application to the Nordheim–Fuchs Reactor Safety Model.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 347, doi. 10.3390/jne5030023
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- Article
5
Evaluation of δ-Phase ZrH 1.4 to ZrH 1.7 Thermal Neutron Scattering Laws Using Ab Initio Molecular Dynamics Simulations.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 330, doi. 10.3390/jne5030022
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- Publication type:
- Article
6
Mini-Reactor Proliferation-Resistant Fuel with Burnable Gadolinia in Once-Through Operation Cycle Performance Verification.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 318, doi. 10.3390/jne5030021
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- Article
7
Trends and Perspectives on Nuclear Waste Management: Recovering, Recycling, and Reusing.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 299, doi. 10.3390/jne5030020
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- Publication type:
- Article
8
Open-Source Optimization of Hybrid Monte Carlo Methods for Fast Response Modeling of NaI (Tl) and HPGe Gamma Detectors.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 274, doi. 10.3390/jne5030019
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- Publication type:
- Article
9
Validation of the SCALE/Polaris–PARCS Code Procedure With the ENDF/B-VII.1 AMPX 56-Group Library: Boiling Water Reactor †.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 260, doi. 10.3390/jne5030018
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- Article
10
Validation of the SCALE/Polaris−PARCS Code Procedure with the ENDF/B-VII.1 AMPX 56-Group Library: Pressurized Water Reactor †.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 246, doi. 10.3390/jne5030017
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- Publication type:
- Article
11
Phenomenological Nondimensional Parameter Decomposition to Enhance the Use of Simulation Modeling in Fire Probabilistic Risk Assessment of Nuclear Power Plants.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 226, doi. 10.3390/jne5030016
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- Article
12
Reinforcement Learning-Based Control Sequence Optimization for Advanced Reactors.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 209, doi. 10.3390/jne5030015
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- Publication type:
- Article
13
New Mini Neutron Tubes with Multiple Applications.
- Published in:
- Journal of Nuclear Engineering (JNE), 2024, v. 5, n. 3, p. 197, doi. 10.3390/jne5030014
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- Publication type:
- Article