Xing L. Yan

ORCID: 0009-0005-4193-9748
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About
Contact & Profiles
Research Areas
  • Nuclear reactor physics and engineering
  • Nuclear Materials and Properties
  • Graphite, nuclear technology, radiation studies
  • Advanced Power Generation Technologies
  • Nuclear Engineering Thermal-Hydraulics
  • Chemical Looping and Thermochemical Processes
  • Nuclear and radioactivity studies
  • Spacecraft and Cryogenic Technologies
  • Refrigeration and Air Conditioning Technologies
  • Heat transfer and supercritical fluids
  • Integrated Energy Systems Optimization
  • Risk and Safety Analysis
  • Nuclear Physics and Applications
  • Heat Transfer and Numerical Methods
  • Industrial Gas Emission Control
  • Combustion and Detonation Processes
  • Advanced Combustion Engine Technologies
  • Thermodynamic and Exergetic Analyses of Power and Cooling Systems
  • Combustion and flame dynamics
  • Iron and Steelmaking Processes
  • Aerodynamics and Fluid Dynamics Research
  • Radiative Heat Transfer Studies
  • Hybrid Renewable Energy Systems
  • Tribology and Lubrication Engineering
  • Rocket and propulsion systems research

Japan Atomic Energy Agency
2016-2025

Southwest Petroleum University
2023-2024

Tsinghua Sichuan Energy Internet Research Institute
2018

Tongji University
2010

Jiangsu University
2006

Fraunhofer Institute for Microengineering and Microsystems
2000

Carl Zeiss (Germany)
2000

Massachusetts Institute of Technology
1991-1994

10.1016/j.nucengdes.2004.08.026 article EN Nuclear Engineering and Design 2004-10-01

10.15669/pnst.7.293 article EN Progress in Nuclear Science and Technology 2025-03-31

10.1016/j.nucengdes.2019.01.010 article EN Nuclear Engineering and Design 2019-01-11

Existing practice of nuclear desalination cogeneration incurs loss plant power generation because it competes for live steam with turbine. Such is completely avoided the design proposed in present study. The called GTHTR300 based on a high-temperature gas reactor rated at 600 MWt. Gas turbine used to replace as generator. converts about half reactor's thermal electricity while rejecting balance sensible waste heat be utilized multistage flash (MSF) seawater desalination. A new MSF process...

10.1002/er.2995 article EN International Journal of Energy Research 2012-12-07

Japan Atomic Energy Agency has conducted a conceptual design of 50 MWt small-sized high temperature gas cooled reactor (HTGR) for multiple heat applications, named HTR50S, with the outlet coolant 750°C and 900°C. It is first-of-a-kind commercial plant or demonstration HTGR system to be deployed in developing countries 2020s. The concept HTR50S satisfy user requirements multipurpose applications such as district heating process supply based on steam turbine power generation by helium hydrogen...

10.1155/2013/918567 article EN cc-by International Journal of Nuclear Energy 2013-12-26

In a safety demonstration test involving the loss of both reactor reactivity control and core cooling, high-temperature engineering (HTTR) demonstrates spontaneous stabilization power. The analytical results tripping one or two out three gas circulators without scram have already been reported. Moreover, pre-analytical result all has presented. On other hand, are shown in this paper. About experiments, at an initial power 30% (9 MW), when were tripped to reduce coolant flow rate zero, fuel...

10.1080/00223131.2014.967324 article EN Journal of Nuclear Science and Technology 2014-11-11

GTHTR300A is a power plant design based on high-temperature gas-cooled reactor. It relies exclusive dry cooling for production and in emergency, practice not found existing other proposed plants. Besides well-known environmental benefits, successful use of may provide the new safety advantage because it avoids water-related event such as tsunami or generation explosive hydrogen. In GTHTR300A, reactor coolant used to drive direct-cycle gas turbine, further systems are provided meet three...

10.1002/er.3172 article EN International Journal of Energy Research 2014-01-22
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