Advanced search
Publication Cover
Journal of Nuclear Science and Technology Volume 52, 2015 - Issue 2
Submit an article Journal homepage
1,970
Views
18
CrossRef citations to date
0
Altmetric
Original Articles

Studies on the molten salt reactor: code development and neutronics analysis of MSRE-type design

Kun ZhuangNuclear Engineering Computational Lab., School of Nuclear Science and Technology, Xi’an Jiaotong University, ShannXi710049, P.R. ChinaView further author information
,
Liangzhi CaoNuclear Engineering Computational Lab., School of Nuclear Science and Technology, Xi’an Jiaotong University, ShannXi710049, P.R. ChinaView further author information
,
Youqi ZhengNuclear Engineering Computational Lab., School of Nuclear Science and Technology, Xi’an Jiaotong University, ShannXi710049, P.R. ChinaCorrespondence[email protected]
View further author information
&
Hongchun WuNuclear Engineering Computational Lab., School of Nuclear Science and Technology, Xi’an Jiaotong University, ShannXi710049, P.R. ChinaView further author information
Pages 251-263 | Received 21 May 2014, Accepted 08 Jul 2014, Published online: 07 Aug 2014

Citations (18)

Keep up to date with the latest research on this topic with citation updates for this article.

Subscribe to citation updates

Read on this site (3)

Shuangjian Chen, Dongsheng, Run-Sheng Gao & Zhijun Li. (2021) Manufacturing of molten salt reactor heat exchangers using inner hole welding. Materials and Manufacturing Processes 36:10, pages 1189-1198.
Read now
Daniel Wooten & Jeffrey J. Powers. (2018) A Review of Molten Salt Reactor Kinetics Models. Nuclear Science and Engineering 191:3, pages 203-230.
Read now
Kun Zhuang, Youqi Zheng, Liangzhi Cao, Tianliang Hu & Hongchun Wu. (2017) Improvements and validation of the transient analysis code MOREL for molten salt reactors. Journal of Nuclear Science and Technology 54:8, pages 878-890.
Read now

Articles from other publishers (15)

Yulin Wang, Weiran Chen, Linxuan Zhang, Xinyu Zhao, Yiming Gao & Venkata Dinavahi. (2024) Small Modular Reactors: An Overview of Modeling, Control, Simulation, and Applications. IEEE Access 12, pages 39628-39650.
Crossref
Indrajeet Singh, Anurag Gupta & Umasankari Kannan. (2023) Analysis of dynamic responses of circulating fuel reactors using in-house 3D space-time kinetics code ARCH. Nuclear and Particle Physics Proceedings 339-340, pages 66-69.
Crossref
Ao Zhang, Ming Dai, Maosong Cheng, Chunyan Zou & Jingen Chen. (2023) High-fidelity neutronics simulation of channel-type molten salt reactors. Nuclear Engineering and Design 401, pages 112063.
Crossref
Dalin Zhang. 2023. Handbook of Generation IV Nuclear Reactors. Handbook of Generation IV Nuclear Reactors 449 484 .
Jianhui Wu, Jingen Chen, Xiangzhou Cai, Chunyan Zou, Chenggang Yu, Yong Cui, Ao Zhang & Hongkai Zhao. (2022) A Review of Molten Salt Reactor Multi-Physics Coupling Models and Development Prospects. Energies 15:21, pages 8296.
Crossref
Xian-Di Zuo, Mao-Song Cheng, Yu-Qing Dai, Kai-Cheng Yu & Zhi-Min Dai. (2022) Flow field effect of delayed neutron precursors in liquid-fueled molten salt reactors. Nuclear Science and Techniques 33:8.
Crossref
Mustafa K. Jaradat, Hansol Park, Won Sik Yang & Changho Lee. (2021) Development and validation of PROTEUS-NODAL transient analyses capabilities for molten salt reactors. Annals of Nuclear Energy 160, pages 108402.
Crossref
Shi-He Yu, Ya-Fen Liu, Pu Yang, Rui-Min Ji, Gui-Feng Zhu, Bo Zhou, Xu-Zhong Kang, Rui Yan, Yang Zou & Ye Dai. (2021) Neutronics analysis for MSR cell with different fuel salt channel geometries. Nuclear Science and Techniques 32:1.
Crossref
Kai Huang, Liangzhi Cao, Hongchun Wu, Xuedong Fu, Yangjun Ying & Shengdong Zhu. (2020) Variable coefficient depletion equations – Efficient calculation method. Annals of Nuclear Energy 140, pages 107100.
Crossref
Kun Zhuang, Xiaobin Tang & Liangzhi Cao. (2019) Development and verification of a model for generation of MSFR few-group homogenized cross-sections based on a Monte Carlo code OpenMC. Annals of Nuclear Energy 124, pages 187-197.
Crossref
Kun Zhuang & Liangzhi Cao. (2018) A study of the impact of mixed mode of fuel salt in plenum on steady-state performance of channel-type molten salt reactor. Annals of Nuclear Energy 122, pages 207-216.
Crossref
Zhifeng Li & Jiejin Cai. (2018) Dynamics analysis of the graphite-moderated channel-type molten salt reactors based on Serpent/NTH3D-MSR. Annals of Nuclear Energy 121, pages 128-134.
Crossref
Kun Zhuang & Liangzhi Cao. (2018) Numerical analysis on the dynamic behaviors of a graphite-moderated molten salt reactor based on MOREL2.0 code. Annals of Nuclear Energy 117, pages 3-11.
Crossref
Liangzhi Cao, Kun Zhuang, Youqi Zheng, Tianliang Hu & Hongchun Wu. (2018) Transient analysis for liquid-fuel molten salt reactor based on MOREL2.0 code. International Journal of Energy Research 42:1, pages 261-275.
Crossref
Tianliang Hu, Hongchun Wu, Liangzhi Cao & Zhifeng Li. (2017) Finite volume method based neutronics solvers for steady and transient-state analysis of nuclear reactors. Energy Procedia 127, pages 275-283.
Crossref

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Order Reprints Request Corporate Permissions

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

Request Academic Permissions

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.

Related research

People also read lists articles that other readers of this article have read.

Recommended articles lists articles that we recommend and is powered by our AI driven recommendation engine.

Cited by lists all citing articles based on Crossref citations.
Articles with the Crossref icon will open in a new tab.