A5068293067- Nuclear reactor physics and engineering
- Nuclear Materials and Properties
- Nuclear Physics and Applications
- Fusion materials and technologies
- Nuclear and radioactivity studies
- Nuclear physics research studies
- Ion-surface interactions and analysis
- Nuclear materials and radiation effects
- Graphite, nuclear technology, radiation studies
- Radiation Detection and Scintillator Technologies
- Supercapacitor Materials and Fabrication
- High-Velocity Impact and Material Behavior
- Advancements in Battery Materials
- Military Technology and Strategies
- Radiation Shielding Materials Analysis
- Wind and Air Flow Studies
- Cavitation Phenomena in Pumps
- Advanced Photocatalysis Techniques
- Welding Techniques and Residual Stresses
- Luminescence Properties of Advanced Materials
- Fault Detection and Control Systems
- Advanced Technologies in Various Fields
- Crystallization and Solubility Studies
- Nuclear Engineering Thermal-Hydraulics
- X-ray Diffraction in Crystallography
Sun Yat-sen University
2016-2024
CEA Cadarache
2018-2022
Commissariat à l'Énergie Atomique et aux Énergies Alternatives
2018-2022
Université Grenoble Alpes
2018-2021
CEA Grenoble
2021
Direction des énergies
2020
National Taiwan University
1987
The illicit trafficking of radioactive materials, especially weapon-grade uranium or plutonium, is a significant security threat. Nuclear forensics helps trace the materials. present study develops methods for possible origins fuels irradiated in nuclear reactors, which are most powerful sources producing including plutonium. Three key factors fuel forensics, namely, initial 235U enrichment, burnup, and type irradiation reactors. first two determined based on experimental data six...
Neutronic performance is investigated for a potential accident tolerant fuel (ATF),which consists of U$_3$Si$_2$ and FeCrAl cladding. In comparison with current UO$_2$-Zr system, has better oxidation resistance but larger thermal neutron absorption cross section. higher conductivity uranium density, which can compensate the reactivity suppressed by FeCrAl. Based on neutronic investigations, possible U$_3$Si$_2$-FeCrAl fuel-cladding systemis taken into consideration. Fundamental properties...
Beryllium metal and beryllium oxide are critical nuclear materials, with neutron-induced reaction data on playing a crucial role in energy research development. Macroscopic validation is an essential step the evaluation process, providing means to assess reliability accuracy of such data. Critical benchmark experiments serve as most important references for this validation. However, discrepancies have been observed two closely related series beryllium-reflector fast-spectrum experiments,...
The present work investigates the discrepancy between numbers of atomic displacements from direct computation and damage energy-based calculation in Full Cascade (FC) simulation SRIM-like codes. A new formula is proposed to correlate energy. efficiency displacement increases with ion energy below keV owing increase residual transfer efficiency. In general, number proportional for incident above about 2 times value deduced modified Kinchin-Pease formula. linear relationship should also be...
• Neutronic properties of potential accident tolerant fuel UO 2 -BeO are investigated with claddings, SiC and FeCrAl. A critical condition to keep cycle length is obtained validated as a second order polynomial function uranium enrichment content fraction BeO. cladded zircaloy fuels similar in almost all neutronic performances, while FeCrAl one little different. Flatter radial power distribution found higher BeO fuel. Total gas release not much different, although 4 He production shown The...
Nuclear level density is important for evaluating nuclear reaction processes, but its microscopic investigation not frequently performed. The present work applies a recently developed shell-model-based method to estimate the of fission products $^{133--137}\mathrm{Xe}$ and $^{135--138}\mathrm{Ba}$. monopole-based universal interaction, ${V}_{\text{MU}}$, M3Y type spin-orbit interaction are combined construct shell-model Hamiltonian. model space truncated based on binding energy each...
The neutron irradiation-induced mechanical property change is a major challenge for nuclear materials. For Pressurized Water Reactor (PWR), irradiation embrittlement of the reactor pressure vessel one most important issues that determine whole power plant lifetime. present work focuses thus on uncertainty assessment displacement damage PWR vessel. uncertainties flux, data, and atomic models are propagated to Displacement per Atom (DPA) rates with special emphasis importance correlation...
Radiation damage is a common challenge for materials employed in radiation environment. The present work performs experimental validation of current primary models recoil energy near the displacement threshold using electron irradiation measures. verified rescaling resistivity change per Frenkel pair results reasonable agreements between theories and experiments. recent molecular dynamics-based model demonstrated as consistent with data Fe, Ni, Cu, whereas classical step function...
Due to the importance of radiation damage materials in nuclear facilities, it is interest accurately calculate and corresponding uncertainty. The CONRAD code developed at CEA Cadarache for evaluating data uncertainties using various methods. Different Displacement per Atom (DPA) models have been recently implemented perform calculation, sensitivity analysis, uncertainty propagation cross sections. current version able compute section associated covariance matrix from model parameters DPA...
A simple and analytical formula is suggested to solve the problems of local burnup isotope distributions. The present method considers two extreme conditions neutrons penetrating fuel rod. Based on these considerations, obtained calculate reaction rates $^{235}$U, $^{238}$U, $^{239}$Pu straightforward Starting from an initial level, parameters are fitted given by a Monte Carlo (MC) calculation. Then independently gives very similar results as MC calculation starting high but takes just few...