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Weng-Sheng Kuo

Observed name: Kuo, Weng-Sheng
ORCID: 0000-0002-2656-7430
Observed ORCID: 0000-0002-2656-7430
OpenAlex ID: A5027710222
Using particle swarm optimization algorithm to search for a power ascension path of boiling water reactors
2016 · Tzung-Yi Lin, Jau-Tyne Yeh, et al. · Annals of Nuclear Energy · 12
A 30 MeV-cyclotron-based quasi-monoenergetic neutron source
2023 · Kuo-Yuan Chu, Weng-Sheng Kuo, et al. · Nuclear Engineering and Technology · 9
Qualification of the Taiwan Power Company's pressurized water reactor physics methods using CASMO-4/SIMULATE-3
2012 · Hsien-Chuan Lin, Shung-Jung Yaur, et al. · Nuclear Engineering and Design · 7
Optimization of axial enrichment distribution for BWR fuels using scoping libraries and block coordinate descent method
2016 · Wu-Hsiung Tung, Tien-Tso Lee, et al. · Nuclear Engineering and Design · 6
MCNP simulation of TRR-II cold neutron source design
2002 · Tai-Cheng Guung, Wen-Fa Tsai, et al. · Physica B Condensed Matter · 6
Evaluation of cadmium ratio for conceptual design of a cyclotron-based thermal neutron radiography system
2022 · Weng-Sheng Kuo · Nuclear Engineering and Technology · 5
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In-core power sharing and fuel requirement study for a decommissioning Boiling Water Reactor using the linear reactivity model
2014 · Chung-Yuan Chen, Wu-Hsiung Tung, et al. · Nuclear Engineering and Design · 4
The cyclotron-based neutron sources and projects at NARI
2024 · Sheng-Long Jeng, How-Ming Lee, et al. · EPJ Web of Conferences · 3
Fuel lattice design in a boiling water reactor using a knowledge-based automation system
2015 · Wu-Hsiung Tung, Tien-Tso Lee, et al. · Nuclear Engineering and Design · 3
The general evaluation of the nodal synthesis method in nuclear reactor transient analysis
1993 · Kuo, Weng-Sheng · DSpace@MIT (Massachusetts Institute of Technology) · 2
Evaluation of deep drillholes for high level nuclear waste disposal
1991 · Weng-Sheng Kuo · DSpace@MIT (Massachusetts Institute of Technology) · 2
Nuclear Criticality Analyses of the Spent Fuel Pool Under Loss of Spent Fuel Pool Water and Neutron Absorbers in the Racks for Taipower’s Chinshan Nuclear Power Plant
2013 · Weng-Sheng Kuo · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
KS-FSOPS: A computer-aided simulation system for the in-core fuel shuffling operation for Taipower`s Kuosheng nuclear power plant
1996 · Weng-Sheng Kuo, Tianshu Song · OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information)
Works count: 13
Citation count: 60
H-index: 5
I10-index: 1
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