Mixed analytical model to estimate the anisotropic effective thermal conductivity and in-reactor performance of metallic microcell UO2
出版年份 2023 全文链接
标题
Mixed analytical model to estimate the anisotropic effective thermal conductivity and in-reactor performance of metallic microcell UO2
作者
关键词
-
出版物
Journal of Nuclear Materials
Volume 585, Issue -, Pages 154655
出版商
Elsevier BV
发表日期
2023-07-27
DOI
10.1016/j.jnucmat.2023.154655
参考文献
相关参考文献
注意：仅列出部分参考文献，下载原文获取全部文献信息。- Thermal conductivity prediction of UO2-BeO composite fuels and related decisive features discovery via convolutional neural network
- (2022) Zhanpeng Gong et al. ACTA MATERIALIA
- Performance analysis of nuclear reactor core loaded with Accident-Tolerant Fuel: Mo/Cr metallic microcell UO2 pellets and CrAl coating
- (2022) Eun Jeong et al. ANNALS OF NUCLEAR ENERGY
- Prospects for additive manufacturing of nuclear fuel forms
- (2022) Andrew T. Nelson PROGRESS IN NUCLEAR ENERGY
- Analysis of pellet-to-cladding gap closure for a metallic micro-cell pellet under normal operating conditions
- (2021) Yang-Hyun Koo et al. JOURNAL OF NUCLEAR MATERIALS
- Evaluation of thermophysical properties of UO2-10 Vol% Mo nuclear fuel pellets
- (2021) Murali Krishna Tummalapalli et al. JOURNAL OF NUCLEAR MATERIALS
- Enhancing thermal conductivity of UO2 with the addition of UB2 via conventional sintering techniques
- (2021) Jennifer K. Watkins et al. JOURNAL OF NUCLEAR MATERIALS
- UO2 + 5 vol% ZrB2 nano composite nuclear fuels with full boron retention and enhanced oxidation resistance
- (2020) Tiankai Yao et al. CERAMICS INTERNATIONAL
- U3Si2 and UO2 composites densified by spark plasma sintering for accident-tolerant fuels
- (2020) Bowen Gong et al. JOURNAL OF NUCLEAR MATERIALS
- Optimization of thermal conductivity of UO2–Mo composite with continuous Mo channel based on finite element method and machine learning
- (2020) Biaojie Yan et al. INTERNATIONAL JOURNAL OF HEAT AND MASS TRANSFER
- Impact of uranium oxide (UO2) fuel with molybdenum (Mo) inserts on pressurized water reactor performance and safety
- (2020) Jacob P. Gorton et al. JOURNAL OF NUCLEAR MATERIALS
- Fabrication and thermophysical properties of UO2-UB2 and UO2-UB4 composites sintered via spark plasma sintering
- (2020) E. Kardoulaki et al. JOURNAL OF NUCLEAR MATERIALS
- Fabrication of UO2-Mo composite fuel with enhanced thermal conductivity from sol-gel feedstock
- (2019) S.C. Finkeldei et al. JOURNAL OF NUCLEAR MATERIALS
- Uranium dioxide - Molybdenum composite fuel pellets with enhanced thermal conductivity manufactured via spark plasma sintering
- (2019) J. Buckley et al. JOURNAL OF NUCLEAR MATERIALS
- Fission gas release in the micro-cell fuel pellet under normal operating conditions: A simplified approach based on UO2 pellet experience
- (2019) Yang-Hyun Koo et al. JOURNAL OF NUCLEAR MATERIALS
- Conductive inserts to reduce nuclear fuel temperature
- (2019) Pavel G. Medvedev et al. JOURNAL OF NUCLEAR MATERIALS
- Enhanced thermal conductivity accident tolerant fuels for improved reactor safety – A comprehensive review
- (2018) Wei Zhou et al. ANNALS OF NUCLEAR ENERGY
- Development status of microcell UO 2 pellet for accident-tolerant fuel
- (2018) Dong-Joo Kim et al. Nuclear Engineering and Technology
- Irradiation testing of enhanced uranium oxide fuels
- (2018) Klara Insulander Björk et al. ANNALS OF NUCLEAR ENERGY
- Numerical characterization of micro-cell UO 2 Mo pellet for enhanced thermal performance
- (2016) Heung Soo Lee et al. JOURNAL OF NUCLEAR MATERIALS
- Synthesis and preservation of graphene-supported uranium dioxide nanocrystals
- (2016) Hanyu Ma et al. JOURNAL OF NUCLEAR MATERIALS
- Development Status of Accident-tolerant Fuel for Light Water Reactors in Korea
- (2016) Hyun-Gil Kim et al. Nuclear Engineering and Technology
- Fabrication methods and thermal hydraulics analysis of enhanced thermal conductivity UO2–BeO fuel in light water reactors
- (2015) Wenzhong Zhou et al. ANNALS OF NUCLEAR ENERGY
- Synthesis and sintering of UN-UO 2 fuel composites
- (2015) Brian J. Jaques et al. JOURNAL OF NUCLEAR MATERIALS
- UO 2 –UN composites with enhanced uranium density and thermal conductivity
- (2015) Jae Ho Yang et al. JOURNAL OF NUCLEAR MATERIALS
- The behaviour under irradiation of molybdenum matrix for inert matrix fuel containing americium oxide (CerMet concept)
- (2015) E. D'Agata et al. JOURNAL OF NUCLEAR MATERIALS
- Fabrication of micro-cell UO 2 –Mo pellet with enhanced thermal conductivity
- (2015) Dong-Joo Kim et al. JOURNAL OF NUCLEAR MATERIALS
- Spark plasma sintering of diamond-reinforced uranium dioxide composite fuel pellets
- (2015) Zhichao Chen et al. NUCLEAR ENGINEERING AND DESIGN
- Influence of Carbon Nanotube Dispersion in UO2–Carbon Nanotube Ceramic Matrix Composites Utilizing Spark Plasma Sintering
- (2015) Andrew Cartas et al. NUCLEAR TECHNOLOGY
- The influence of SiC particle size and volume fraction on the thermal conductivity of spark plasma sintered UO2–SiC composites
- (2013) Sunghwan Yeo et al. JOURNAL OF NUCLEAR MATERIALS
- Enhanced thermal conductivity of uranium dioxide–silicon carbide composite fuel pellets prepared by Spark Plasma Sintering (SPS)
- (2012) S. Yeo et al. JOURNAL OF NUCLEAR MATERIALS
- Modeling thermal conductivity in UO2 with BeO additions as a function of microstructure
- (2009) D.S. Li et al. JOURNAL OF NUCLEAR MATERIALS
- Modeling and Measurement of Thermal Properties of Ceramic Composite Fuel for Light Water Reactors
- (2008) Ryan Latta et al. HEAT TRANSFER ENGINEERING
Add your recorded webinar
Do you already have a recorded webinar? Grow your audience and get more views by easily listing your recording on Peeref.
Upload NowBecome a Peeref-certified reviewer
The Peeref Institute provides free reviewer training that teaches the core competencies of the academic peer review process.
Get Started