Performance Improvement of Weight Window Method by Incorporating DXTRAN.
- Published in:
- Nuclear Science & Engineering, 2025, v. 199, n. 9, p. 1391, doi. 10.1080/00295639.2024.2438570
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- Article
Works matching AU Cao, Liangzhi
Results: 17
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Development and Verification of Sampling Code NECP-SOUL for Evaluated Nuclear Data Files in ENDF-6 Format.
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- Nuclear Science & Engineering, 2025, v. 199, p. S765, doi. 10.1080/00295639.2024.2364471
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- Article
3
Resonance Calculation of FCM Fuel Based on the Global-Local Method.
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- Nuclear Science & Engineering, 2025, v. 199, p. S73, doi. 10.1080/00295639.2023.2296239
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- Publication type:
- Article
4
Study on Unstructured Mesh–Based Monte Carlo/Deterministic Coupled Particle Transport Calculation Method.
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- Nuclear Science & Engineering, 2024, v. 198, n. 11, p. 2209, doi. 10.1080/00295639.2023.2295065
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- Article
5
A Unified Framework of Stabilized Finite Element Methods for Solving the Boltzmann Transport Equation.
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- Nuclear Science & Engineering, 2023, v. 197, n. 3, p. 472, doi. 10.1080/00295639.2022.2106733
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- Article
6
A Residual-Based Subgrid-Scale Method Combined with Spherical Harmonics Angular Approximation for Solving the Boltzmann Transport Equation.
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- Nuclear Science & Engineering, 2022, v. 196, n. 5, p. 526, doi. 10.1080/00295639.2021.2011667
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- Publication type:
- Article
7
Moment Matching: A New Optimization-Based Sampling Scheme for Uncertainty Quantification of Reactor-Physics Analysis.
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- Nuclear Science & Engineering, 2021, v. 195, n. 12, p. 1247, doi. 10.1080/00295639.2021.1923338
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- Publication type:
- Article
8
A Comparison Between the Embedded Self-Shielding Method and the Enhanced Neutron Current Method Based on the Equivalent Pin Cell Model on the Irregular Fuel Lattice Problem.
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- Nuclear Science & Engineering, 2020, v. 194, n. 3, p. 232, doi. 10.1080/00295639.2019.1664146
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- Article
9
Subchannel Analysis, CFD Modeling and Verifications, CHF Experiments and Benchmarking.
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- Science & Technology of Nuclear Installations, 2014, p. 1, doi. 10.1155/2014/209747
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- Article
10
Economic Evaluation on the MOX Fuel in the Closed Fuel Cycle.
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- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/698019
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- Article
11
Overview of the new capabilities in the Monte-Carlo particle-transport code NECP-MCX V2.0.
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- EPJ Nuclear Sciences & Technologies, 2024, v. 10, p. 1, doi. 10.1051/epjn/2024014
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- Publication type:
- Article
12
SPARK-NC: A Lead-Bismuth-Cooled Small Modular Fast Reactor with Natural Circulation and Load Following Capabilities.
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- Energies (19961073), 2020, v. 13, n. 20, p. 5410, doi. 10.3390/en13205410
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- Article
13
A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR.
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- Energies (19961073), 2020, v. 13, n. 16, p. 4070, doi. 10.3390/en13164070
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- Article
14
Analysis of the thermal feedback effect and nuclides flow effect on the fuel‐cycle characteristics of Molten Salt Reactors.
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- International Journal of Energy Research, 2021, v. 45, n. 8, p. 11677, doi. 10.1002/er.5490
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- Article
15
Conceptual core design study of an innovative small transportable lead‐bismuth cooled fast reactor (SPARK) for remote power supply.
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- International Journal of Energy Research, 2018, v. 42, n. 11, p. 3672, doi. 10.1002/er.4119
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- Article
16
Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code.
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- International Journal of Energy Research, 2018, v. 42, n. 1, p. 261, doi. 10.1002/er.3828
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- Publication type:
- Article
17
Reactor core transient analysis of an innovative high-level nuclear waste transmuter with metal fuel.
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- International Journal of Energy Research, 2017, v. 41, n. 9, p. 1322, doi. 10.1002/er.3715
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- Publication type:
- Article