A5052241176- Graphite, nuclear technology, radiation studies
- Fusion materials and technologies
- Nuclear and radioactivity studies
- Radiation Shielding Materials Analysis
- Neutrino Physics Research
- Atomic and Subatomic Physics Research
- Metal and Thin Film Mechanics
- Catalysis and Hydrodesulfurization Studies
- Catalytic Processes in Materials Science
- Dark Matter and Cosmic Phenomena
- Advancements in Battery Materials
- Graphene research and applications
- Quantum, superfluid, helium dynamics
- Crystallization and Solubility Studies
- Nuclear reactor physics and engineering
- Electrocatalysts for Energy Conversion
- Nuclear Materials and Properties
- X-ray Diffraction in Crystallography
- Nuclear Physics and Applications
- Electron and X-Ray Spectroscopy Techniques
China National Nuclear Corporation
2025
Tsinghua University
2020-2023
Kunming University of Science and Technology
2017
Institute of High Energy Physics
2014-2015
Chinese Academy of Sciences
2015
This study investigates the enhancement of thermal conductivity in silicon carbide (SiC) matrix pellets for accident-tolerant fuels via atomic layer deposition (ALD) alumina (Al2O3) coatings. Pressure-holding ALD protocols ensured precursor saturation, enabling precise coating control (0.09 nm/cycle). The ALD-coated Al2O3 layers on SiC particles were found to be more uniform while minimizing surface oxidation compared traditional mechanical mixing. Combined with yttria (Y2O3) additives and...
Progress on a method of barium tagging for the nEXO double beta decay experiment is reported. Absorption and emission spectra deposits atoms ions in solid xenon matrices are presented. Excitation prominent lines, temperature dependence, bleaching fluorescence reveal existence different matrix sites. A regular series sharp lines observed ${\mathrm{Ba}}^{+}$ identified with some type hydride molecule. Lower limits quantum efficiency principal Ba transition Under current conditions, an image...
We describe a system to transport and identify barium ions produced in liquid xenon, as part of R&D towards the second phase double beta decay experiment, nEXO. The goal is Ba ion resulting from an extremely rare nuclear isotope 136Xe, hence providing confirmation occurrence decay. This achieved through Resonance Ionization Spectroscopy (RIS). In test setup described here, can be xenon or vacuum collected on clean substrate. substrate then removed analysis chamber under vacuum, where...
Nuclear graphite can be used in fission and fusion systems due to its excellent nuclear performance mechanical properties where the ability of oxidation resistance is usually concerned. Although new ET-10 was revealed by previous experiments regarding accident conditions a reactor, further studies are needed oxidize under recommended ASTM D7542 standard. A test facility designed developed cylindrical specimen with 10 L/min airflow. According rates microstructures specimens, chemical...
6Li and 10B contents in the nuclear graphite need to be calculated evaluated for 4He gaseous radioactive waste 3H, which should eliminated an acceptable low level. Furthermore, it will help analyze diffusion adsorption behavior as precursors of 3H 4He. Based on reactions 6Li(n,α)3H 10B(n,α)7Li, we employ Neutron Depth Profiling (NDP) a non-invasive versatile technique, providing content three different kinds graphite, including fuel element matrix reflector boron-containing carbon bricks...
The nickel-base alloy is one of the leading candidate materials for generation IV nuclear reactor pressure vessel. To evaluate its stability helium damage and retention, ions with different energy 80 keV 180 were introduced by ion implantation to a certain dose (peak displacement 1–10 dpa). Then thermal desorption spectroscopy (TDS) atoms was performed discuss characteristic trapping sites. peaks shift lower temperature increasing dpa both irradiation, reflecting reduced diffusion activation...
By combining X-ray micro-computed tomography with mercury porosimetry, the evolution of oxygen supply, porous structure, mass loss and oxidized compositions were investigated to characterize oxidation behavior fine-grained graphite ET-10, regarding geometry specimen its temperature. Here, structure gas flows out into comprehensively compared for two kinds specimens-large pure (D = H 25.4 mm), at a test facility based on ASTM D7542, small partially SiC-coated ≈ 1 mm 1.95 in bottom section...
The annealing process of nuclear graphite accompanying the release Wigner energy was studied in this research. IG-110U and ETP-10 were irradiated at 200 ℃ by neutrons with low-dose (1.38×10 23 n/m 2 ) high-dose (1.92×10 24 ), respectively. Their 100-550 measured based on a high-precision differential scanning calorimeter. Characteristics spectrum investigated. activation peak (170-230 ℃) for 1.48 eV, which related to decomposition interstitial clusters behaviour subsequent pairs....
The neutron irradiated microstructure and performance of nuclear graphite as a moderator structural materials are directly related to the safety longevity reactors. Nuclear-grade isotropic IG-110U ETP-10 were at 200°C with low-dose (1.38×1023n/m2, 0.02dpa) high-dose (1.92×1024n/m2, 0.25dpa) high-temperature annealed high temperatures up 1400°C, whole process analyzed using X-ray diffractometer CARBONX program. After irradiation both doses, c-axis lattice constant <c> became significantly...