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OpenAlex Citation Counts

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OpenAlex is a bibliographic catalogue of scientific papers, authors and institutions accessible in open access mode, named after the Library of Alexandria. It's citation coverage is excellent and I hope you will find utility in this listing of citing articles!

If you click the article title, you'll navigate to the article, as listed in CrossRef. If you click the Open Access links, you'll navigate to the "best Open Access location". Clicking the citation count will open this listing for that article. Lastly at the bottom of the page, you'll find basic pagination options.

Requested Article:

The technology of shielding design for nuclear reactor: A review
YangQuan Chen, Bing Yan
Progress in Nuclear Energy (2023) Vol. 161, pp. 104741-104741
Closed Access | Times Cited: 16

Showing 16 citing articles:

Synthesis of Bi2O3 doping powder from CRT-screen waste glass: Physical, structural, and radiation attenuation properties
Beriham Basha, Mine Kirkbinar, Khadijah Mohammedsaleh Katubi, et al.
Radiation Physics and Chemistry (2023) Vol. 214, pp. 111279-111279
Closed Access | Times Cited: 43
A binary composite material of nano polyaniline intercalated with Nano-Fe2O3 for enhancing gamma-radiation-shielding properties: Experimental and simulation study
Ahmed S. G. Khalil, I.I. Bondouk, Elhassan A. Allam, et al.
Progress in Nuclear Energy (2024) Vol. 169, pp. 105067-105067
Closed Access | Times Cited: 26
Monte Carlo N-Particle (MCNP) simulation of neutron flux at a vertical port in the Suranaree University of Technology Research Reactor (SUT-RR) building
Atirat Pitaktrakul, Jittinun Saenpoowa, Natthawut Laojamnongwong, et al.
Journal of Physics Conference Series (2025) Vol. 2934, Iss. 1, pp. 012036-012036
Open Access
Research on fission and fusion neutron shielding performance of various materials
Sabahattin Akbaş
Radiation Physics and Chemistry (2024) Vol. 218, pp. 111601-111601
Closed Access | Times Cited: 4
Optimization of passive modular molten salt microreactor geometric perturbations using machine learning
Andrew Larsen, Ross Lee, Braden Clayton, et al.
Nuclear Engineering and Design (2024) Vol. 424, pp. 113307-113307
Closed Access | Times Cited: 2
Coupled neutronic-thermal–mechanical analysis of a medium temperature heat pipe cooled reactor
Sina Li, Junji Huang, Bing Yan, et al.
Nuclear Engineering and Design (2024) Vol. 421, pp. 113064-113064
Closed Access | Times Cited: 1
Multi-objective optimization of molten salt microreactor shielding perturbations employing machine learning
Andrew Larsen, Ross Lee, Caden Wilson, et al.
Nuclear Engineering and Design (2024) Vol. 426, pp. 113372-113372
Closed Access | Times Cited: 1
Synthesis and radiation damage tolerance of Mo0.75W0.25AlB solid solution for nuclear fusion reactor applications
Meng Wang, Dongya Zhang, Peter Richardson, et al.
Radiation Physics and Chemistry (2024) Vol. 223, pp. 112025-112025
Closed Access | Times Cited: 1
Corrosion-resistant Gd particles-doped Fe-based amorphous coatings with excellent neutron absorption properties
B.M. Ji, Debin Wang, Tianrun Li, et al.
Corrosion Science (2024) Vol. 238, pp. 112376-112376
Closed Access | Times Cited: 1
Genetic algorithm for multilayer shield optimization with a custom parallel computing architecture
F. Cordella, Mauro Cappelli, Marco Ciotti, et al.
The European Physical Journal Plus (2024) Vol. 139, Iss. 2
Open Access
Enhancing Gamma Ray Shielding Properties of Oxyanion Complexes: A Comparative Study of CaMoO4, PbCrO4, PbMoO4, and CaWO4
Nadher Ali Salman, Kafa Khalaf Hammud
Iraqi Journal of Industrial Research (2024) Vol. 11, Iss. 1, pp. 48-66
Open Access
Microstructure and properties controlling of Al-xGd alloys for thermal neutron absorbing
Zixie Wang, Jie Pan, Ao Liu, et al.
Journal of Nuclear Materials (2024) Vol. 603, pp. 155447-155447
Closed Access
A Method for Optimizing Different Geometric Shields of D-T Neutron Generators by Combining BP Neural Network and Analytic Hierarchy Process
Jiayu Li, Shiwei Jing, Jingfei Cai, et al.
Computer Physics Communications (2024) Vol. 307, pp. 109397-109397
Closed Access
Characteristics of Nuclear Radiation Shielding using Natural Bentonitic Shale
Samah Abdullah Abd El-Azeem, Nareman M. Harpy, Howaida Mansour
Engineering Technology & Applied Science Research (2024) Vol. 14, Iss. 5, pp. 16881-16889
Open Access
A Fast Variance Reduction Technique for Efficient Radiation Shielding Calculations in Nuclear Reactors
Sung‐Hyun Jo, Sang‐Hwan Kim, Jaehyun Cho
Energies (2024) Vol. 17, Iss. 22, pp. 5695-5695
Open Access
Design and fabrication of thermal neutron shielding materials based on natural rubber and boron carbide
Jittinun Saenpoowa, Atirat Pitaktrakul, Supharat Inphonlek, et al.
MRS Communications (2023) Vol. 13, Iss. 6, pp. 1449-1454
Open Access | Times Cited: 1
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