Search Results - "Chen, Jingen"
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Accident Modeling and Analysis of Nuclear Reactors
Published in Energies (Basel) (01-08-2022)“…Nuclear energy has played and will continue playing a key role in the fight against climate change due to its extremely low green-house gas emissions, and high…”
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Research on Initiating Events Analysis of Small Helium-Xenon Gas Cooled Nuclear Reactor
Published in Energies (Basel) (01-10-2023)“…Initiating event analysis is an essential prerequisite of conducting probabilistic safety assessment for nuclear reactors, which plays an important role in…”
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3
Nuclear non‐proliferation review and improving proliferation resistance assessment in the future
Published in International journal of energy research (25-06-2021)“…Summary An increasing number of countries have taken nuclear energy as a preferred approach in response to the environment deterioration and energy supply…”
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A Review of Molten Salt Reactor Multi-Physics Coupling Models and Development Prospects
Published in Energies (Basel) (01-11-2022)“…Molten salt reactors (MSRs) are one type of GEN-IV advanced reactors that adopt melt mixtures of heavy metal elements and molten salt as both fuel and coolant…”
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Numerical study on heat transfer characteristics of molten salt in annular channel with wire coil
Published in Applied thermal engineering (25-11-2021)“…•Annular channel with wire coil is firstly proposed to heat molten salt.•Wire coil inserts are used to enhance the heat transfer in annular channel.•Overall…”
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Impacts of power density on the breeding performance of molten salt reactors
Published in International journal of energy research (25-10-2022)“…Summary A liquid‐fueled molten salt reactor (MSR) can be flexibly designed with a broad range of power density (PD) and neutron spectrum, both of which have a…”
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Development of fuel depletion code for molten salt reactor with very deep burnup
Published in Progress in nuclear energy (New series) (01-01-2025)“…A liquid-fueled molten salt reactor (MSR) can reach a deep burnup based on online reprocessing and continuously refueling, which requires significantly…”
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High-fidelity neutronics simulation of channel-type molten salt reactors
Published in Nuclear engineering and design (01-01-2023)“…As one of the generation IV reactors, molten salt reactors (MSRs) have attracted much attention in recent years. Generally, molten salt acting as both fuel and…”
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Experimental investigation of the thermal-hydraulic characteristics of a printed circuit heat exchanger in the helium-xenon Brayton cycle
Published in International journal of heat and mass transfer (01-09-2024)“…•Experimental tests investigate the impacts of process parameters on he-xe PCHE performance.•The effects of Tin, p and m (400–600 K, 1–2 MPa, 5–45 kg/h) on…”
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10
Machine learning approaches to equilibrium burnup analysis for Molten Salt Reactor
Published in Annals of nuclear energy (01-11-2023)“…•A filtering model and a prediction model for equilibrium state of Molten Salt Reactors are developed.•The LightGBM model is the most favorable for filtering…”
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Design Analysis of a Helium Xenon-Printed Circuit Heat Exchanger for a Closed Brayton Cycle Microtransport Reactor
Published in International journal of energy research (03-07-2023)“…Microtransport with small size and a wide range of applications is very attractive for the utilization of future reactor modularization. A microreactor uses a…”
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Potential of transuranics transmutation in a thorium‐based chloride salt fast reactor
Published in International journal of energy research (10-10-2022)“…Summary A thorium‐based chloride salt fast reactor (TCLFR) for transuranics (TRUs) transmutation is proposed to decrease radioactive nuclear waste. The TCLFR…”
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Parametric study on minor actinides transmutation in a graphite‐moderated thorium‐based molten salt reactors
Published in International journal of energy research (01-04-2021)“…Summary Transmutation of minor actinides (MAs) is an effective solution to reduce the long‐term radiotoxicity of nuclear waste. Online refueling and no fuel…”
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Preliminary study on TRUs utilization in a small modular Th-based molten salt reactor (smTMSR)
Published in Nuclear engineering and design (01-12-2018)“…•The characteristics of the thorium fuel cycle transition with TRUs as starting fuel for a smTMSR are analyzed.•Five different fuel fractions in the core are…”
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Development of a GPU-based three-dimensional neutron transport code
Published in Annals of nuclear energy (01-09-2022)“…•A GPU-based 3D neutron transport code is newly developed.•Calculating the modified total source on-the-fly to significantly reduce the GPU memory…”
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Ex‐core transition to thorium cycle in a small modular heavy‐water moderated molten salt reactor with unchanged concentration of heavy metal nuclides in the fuel salt
Published in International journal of energy research (25-06-2021)“…Summary Ex‐core transition to thorium fuel cycle is an effective way to address the issue of the lacking of the 233U in nature. It consists to extract online…”
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Study of natural uranium utilization in a heavy water moderated molten salt reactor
Published in Progress in nuclear energy (New series) (01-04-2022)“…Heavy water moderated molten salt reactor (HWMSR) is a newly proposed molten salt reactor. It adopts heavy water as the moderator and molten salt dissolved…”
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Transition to thorium fuel cycle in a small modular molten salt reactor based on a batch reprocessing mode
Published in Annals of nuclear energy (01-04-2020)“…•The properties of a sm-TMSR using TRUs and Th as fuels are analyzed.•The U233 demands with thorium fuel cycle in various thermal sm-TMSRs are evaluated.•These…”
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Ameliorating the positive temperature feedback coefficient for an MSR fueled with transuranic elements
Published in Annals of nuclear energy (15-09-2021)“…•Analysis of ameliorating the positive TFC for a TRU-fueled MSR is analyzed.•Two effective solutions are proposed to ameliorate the positive TFC.•With a…”
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Transmutation of 135 Cs in a single‐fluid double‐zone thorium molten salt reactor
Published in International journal of energy research (25-06-2021)Get full text
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