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17 Result(s)

within **ang-Zhou Cai Remove this filter Particle and Nuclear Physics Remove this filter

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  1. No Access

    Article

    Preliminary safety analysis for a heavy water-moderated molten salt reactor

    The heavy water-moderated molten salt reactor (HWMSR) is a newly proposed reactor concept, in which heavy water is adopted as the moderator and molten salt dissolved with fissile and fertile elements is used a...

    Gao-Ang Wen, Jian-Hui Wu, Chun-Yan Zou, **ang-Zhou Cai… in Nuclear Science and Techniques (2024)

  2. No Access

    Article

    Design and prototy** of the readout electronics for the transition radiation detector in the high energy cosmic radiation detection facility

    The high energy cosmic-radiation detection (HERD) facility is planned to launch in 2027 and scheduled to be installed on the China Space Station. It serves as a dark matter particle detector, a cosmic ray inst...

    Jie-Yu Zhu, Yang-Zhou Su, Hai-Bo Yang, Fen-Hua Lu… in Nuclear Science and Techniques (2024)

  3. No Access

    Article

    Plutonium utilization in a small modular molten-salt reactor based on a batch fuel reprocessing scheme

    A molten salt reactor (MSR) has outstanding features considering the application of thorium fuel, inherent safety, sustainability, and resistance to proliferation. However, fissile material

    Xue-Chao Zhao, Rui Yan, Gui-Feng Zhu, Ya-Fen Liu… in Nuclear Science and Techniques (2024)

  4. No Access

    Article

    Isovector giant dipole resonance mode with an improved propagation approach in the framework of EQMD model

    The Extended Quantum Molecular Dynamics (EQMD) model is one of the few QMD-like transport approaches that can describe the \(\alpha \) ...

    Chen-Zhong Shi, **ang-Zhou Cai, De-Qing Fang, Yu-Gang Ma in The European Physical Journal A (2024)

  5. Article

    Open Access

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

    **ao-**ao Li, De-Yang Cui, Chun-Yan Zou, Jian-Hui Wu… in Nuclear Science and Techniques (2024)

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  6. No Access

    Article

    Nondestructive technique for identifying nuclides using neutron resonance transmission analysis at CSNS Back-n

    Nondestructive and noninvasive neutron assays are essential applications of neutron techniques. Neutron resonance transmission analysis (NRTA) is a powerful nondestructive method for investigating the elementa...

    Sheng-Da Tang, Yong-Hao Chen, **g-Yu Tang, Rui-Rui Fan… in Nuclear Science and Techniques (2024)

  7. Article

    Open Access

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

    To provide a reliable and comprehensive data reference for core geometry design of graphite-moderated and low-enriched uranium fueled molten salt reactors, the influences of geometric parameters on the tempera...

    **ao-**ao Li, De-Yang Cui, Chun-Yan Zou, Jian-Hui Wu… in Nuclear Science and Techniques (2023)

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  8. No Access

    Article

    Analysis of burnup performance and temperature coefficient for a small modular molten-salt reactor started with plutonium

    In a thorium-based molten salt reactor (TMSR), it is difficult to achieve the pure \({}^{232}\hbox {Th}\) ...

    Xue-Chao Zhao, Yang Zou, Rui Yan, **ang-Zhou Cai in Nuclear Science and Techniques (2023)

  9. No Access

    Article

    Preliminary analysis of fuel cycle performance for a small modular heavy water-moderated thorium molten salt reactor

    Heavy water-moderated molten salt reactors (HWMSRs) are novel molten salt reactors that adopt heavy water rather than graphite as the moderator while employing liquid fuel. Owing to the high moderating ratio o...

    Ya-Peng Zhang, Yu-Wen Ma, Jian-Hui Wu, **-Gen Chen… in Nuclear Science and Techniques (2020)

  10. No Access

    Article

    Core and blanket thermal–hydraulic analysis of a molten salt fast reactor based on coupling of OpenMC and OpenFOAM

    In the core of a molten salt fast reactor (MSFR), heavy metal fuel and fission products can be dissolved in a molten fluoride salt to form a eutectic mixture that acts as both fuel and coolant. Fission energy ...

    Bin Deng, Yong Cui, **-Gen Chen, Long He, Shao-Peng **a… in Nuclear Science and Techniques (2020)

  11. No Access

    Article

    Transmutation of 129I in a single-fluid double-zone thorium molten salt reactor

    Herein, we assess the 129I transmutation capability of a 2250-MWt single-fluid double-zone thorium molten salt reactor (SD-TMSR) by considering two methods. One is realized by loading an appropriate amount of 129

    Kun-Feng Ma, Cheng-Gang Yu, **ang-Zhou Cai, Chun-Yan Zou… in Nuclear Science and Techniques (2020)

  12. No Access

    Article

    Influence of 235U enrichment on the moderator temperature coefficient of reactivity in a graphite-moderated molten salt reactor

    To optimize the temperature coefficient of reactivity (TCR) for a graphite-moderated and liquid-fueled molten salt reactor, the effects of fuel salt composition on the fuel salt temperature coefficient of reac...

    **ao-**ao Li, De-Yang Cui, Yu-Wen Ma, **ang-Zhou Cai… in Nuclear Science and Techniques (2019)

  13. No Access

    Article

    Development of a dynamics model for graphite-moderated channel-type molten salt reactor

    A molten salt reactor (MSR) is one of the six advanced reactor concepts selected by the generation IV international forum because of its advantages of inherent safety, and the promising capabilities of Th-U br...

    Long He, Cheng-Gang Yu, Rui-Min Ji, Wei Guo, Ye Dai… in Nuclear Science and Techniques (2019)

  14. No Access

    Article

    Analysis of Th-U breeding capability for an accelerator-driven subcritical molten salt reactor

    Accelerator-driven systems based on molten salt fuel have several unique advantages and features for advanced nuclear fuel utilization. The aim of this work was to study the Th-U breeding capability in such s...

    Xue-Chao Zhao, De-Yang Cui, **ang-Zhou Cai, **-Gen Chen in Nuclear Science and Techniques (2018)

  15. No Access

    Article

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

    With respect to a liquid-fueled molten salt reactor (MSR), the temperature coefficient of reactivity mainly includes the moderator temperature coefficient (MTC) and the fuel salt temperature coefficient (FSTC...

    **ao-**ao Li, Yu-Wen Ma, Cheng-Gang Yu, Chun-Yan Zou… in Nuclear Science and Techniques (2018)

  16. No Access

    Article

    Transition toward thorium fuel cycle in a molten salt reactor by using plutonium

    The molten salt reactor (MSR), as one of the Generation IV advanced nuclear systems, has attracted a worldwide interest due to its excellent performances in safety, economics, sustainability, and proliferation...

    De-Yang Cui, Shao-Peng **a, **ao-**ao Li, **ang-Zhou Cai… in Nuclear Science and Techniques (2017)

  17. No Access

    Article

    Neutron excess method for performance assessment of thorium-based fuel in a breed-and-burn reactor with various coolants

    Fertile fuel, such as thorium or depleted uranium, can be bred into fissile fuel and burnt in a breed-and-burn (B&B) reactor. Modeling a full core with fertile fuel can assess the performance of a B&B reactor...

    Kun Yang, Wei Qin, **-Gen Chen, **ang-Zhou Cai in Nuclear Science and Techniques (2016)