C. Zou

发表

Influences of reprocessing separation efficiency on the fuel cycle performances for a Heavy Water moderated Molten Salt Reactor

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2021 .

Analysis of minor actinides transmutation for a Molten Salt Fast Reactor

Yuwen Ma, Chunyan Zou, Jingen Chen, 2015 .

Analyses of production capacity of 89Sr and 90Sr in the 2 MW molten salt reactor.

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2021, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Ameliorating the positive temperature feedback coefficient for an MSR fueled with transuranic elements

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2021 .

Influence of 7Li enrichment on Th-U fuel breeding performance for molten salt reactors under different neutron spectra

Jianhui Wu, Shaopeng Xia, Jingen Chen, 2020 .

Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2020 .

Supply of I-131 in a 2 MW molten salt reactor with different production methods.

Xiangzhou Cai, Jianhui Wu, Xiaohe Wang, 2020, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Sustainable supply of 99Mo source in a 2 MW molten salt reactor using low-enriched uranium.

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2020, Applied radiation and isotopes : including data, instrumentation and methods for use in agriculture, industry and medicine.

Thorium utilization in a small modular molten salt reactor with progressive fuel cycle modes

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2019, International Journal of Energy Research.

Transition to thorium fuel cycle for TMSR

Jianhui Wu, Jingen Chen, Cheng-Gang Yu, 2018 .

Preliminary study on TRUs utilization in a small modular Th-based molten salt reactor (smTMSR)

Guifeng Zhu, Y. Zou, Jingen Chen, 2018, Nuclear Engineering and Design.

Th-U breeding performance in a Channel-type molten salt Fast reactor with different starting fuels

Xiangzhou Cai, Longting He, Jianhui Wu, 2018, Annals of Nuclear Energy.

Minor actinide incineration and Th-U breeding in a small FLiNaK Molten Salt Fast Reactor

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2017 .

Flow effect on 135I and 135Xe evolution behavior in a molten salt reactor

Chen Guo, Xiangzhou Cai, Jianhui Wu, 2017 .

Minor Actinides Incineration in a Small Molten Salt Fast Reactor

Jingen Chen, Cheng-Gang Yu, C. Zou, 2016 .

Startup and burnup strategy for Th-U/U-Pu fuel cycles in an EM2 reactor

Jianlong Han, Cheng-Gang Yu, C. Zou, 2015 .

Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2021, International Journal of Energy Research.

Nuclear non‐proliferation review and improving proliferation resistance assessment in the future

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2020, International Journal of Energy Research.

Breed-and-burn strategy in a fast reactor with optimized starter fuel

Xiangzhou Cai, Jingen Chen, Jianlong Han, 2015 .

Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor

Xiangzhou Cai, Jingen Chen, Jianlong Han, 2015 .

Radiotoxicity of minor actinides in thermal, epithermal and fast TMSRs with very high burnup

Jianhui Wu, Shaopeng Xia, Jingen Chen, 2020 .

Synthesis and evaluation of tacrine-E2020 hybrids as acetylcholinesterase inhibitors for the treatment of Alzheimer's disease.

C. Luo, Yuanchao Li, C. Zou, 2004, Bioorganic & medicinal chemistry letters.

A Review of Molten Salt Reactor Multi-Physics Coupling Models and Development Prospects

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2022, Energies.

Development and verification of a three-dimensional spatial dynamics code for molten salt reactors

C. Zou, Y. Cui, J.G. Chen, 2022, Annals of Nuclear Energy.

Transition to thorium fuel cycle on a heavy water moderated molten salt reactor by using low enrichment uranium

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2022 .

Neutronic effect of graphite dimensional change in a small modular molten salt reactor

W. Guo, Guifeng Zhu, Y. Zou, 2020, International Journal of Energy Research.

A novel concept for a molten salt reactor moderated by heavy water

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2019, Annals of Nuclear Energy.

149Sm evolution behavior in a small modular molten salt reactor

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2018, Annals of Nuclear Energy.

Optimization of temperature coefficient and breeding ratio for a graphite-moderated molten salt reactor

Chenggang Yu, Jie Chen, Yuwen Ma, 2015 .

Impacts of power density on the breeding performance of molten salt reactors

Jingen Chen, C. Zou, A. Zhang, 2022, International Journal of Energy Research.

Study of natural uranium utilization in a heavy water moderated molten salt reactor

Xiangzhou Cai, Jianhui Wu, Jingen Chen, 2022, Progress in Nuclear Energy.

Low enriched uranium and thorium fuel utilization under once‐through and offline reprocessing scenarios in small modular molten salt reactor

Guifeng Zhu, Y. Zou, W. Guo, 2019, International Journal of Energy Research.

High-fidelity neutronics simulation of channel-type molten salt reactors

C. Zou, M. Dai, A. Zhang, 2023, Nuclear Engineering and Design.

The homocysteine associated variant rs548987 of SLC17A3 confers susceptibility to ischemic stroke in Chinese population

Lidian Chen, C. Zou, Lianhua Yin, 2016, Journal of the Neurological Sciences.

Modelling the influence of incident radiation on the SIF-based GPP estimation for maize

Liangyun Liu, Zhunqiao Liu, Xinjie Liu, 2021 .

Optimizing the Empirical Parameters of the Data-Driven Algorithm for SIF Retrieval for SIFIS Onboard TECIS-1 Satellite

Liangyun Liu, Xinjie Liu, Shanshan Du, 2021, Sensors.

Development and application of optimal burnup estimation methodology for pebble bed reactor

Xiangzhou Cai, Jingen Chen, C. Zou, 2018, Annals of Nuclear Energy.

Effects of fuel salt composition on fuel salt temperature coefficient (FSTC) for an under-moderated molten salt reactor (MSR)

C. Zou, Xiaoxiao Li, Yuwen Ma, 2018, Nuclear Science and Techniques.

Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium

Jianhui Wu, D. Cui, C. Zou, 2023, Nuclear Science and Techniques.

Machine Learning Approaches to Equilibrium Burnup Analysis for Molten Salt Reactor

Jingen Chen, C. Zou, Jun Zhou, 2023, SSRN Electronic Journal.