Preparation of spherical fuel elements for HTR-PM in INET-Reference-Cited by-同舟云学术

Preparation of spherical fuel elements for HTR-PM in INET

Published:2013-10 Issue: Volume:263 Page:456-461
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Xiangwen Zhou,Zhenming Lu,Jie Zhang,Bing Liu,Yanwen Zou,Chunhe Tang,Yaping Tang

Funder

large advanced pressurized water reactor and high temperature gas-cooled reactor nuclear power plants

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference15 articles.

1. Research and development of fuel element for Chinese 10 MW high temperature gas-cooled reactor;Chunhe;J. Nucl. Sci. Technol.,1999

2. Research and development of fuel element for Chinese 10 MW high temperature gas-cooled reactor;Chunhe;J. Nucl. Sci. Technol.,2000

3. Comparison of HTGR fuel design, manufacture and quality control method between Japan and China;Fu Xiaoming,2002

4. Status of qualification of high-temperature reactor fuel element spheres;Heit;Nucl. Technol.,1977

5. High temperature gas cooled reactor fuels and materials. IAEA-TECDOC-1645,2010

Cited by 48 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Multiphysics and multi-scale design and analysis of nuclear thermal propulsion pellet bed reactor based on spherical cermet fuel element;Annals of Nuclear Energy;2024-07

2. Fabrication of matrix graphite with a high degree of graphitization for spherical fuel elements by using natural microcrystalline graphite fillers;Nuclear Engineering and Technology;2024-06

3. Studying on the upper limit of the coarse-grained DEM model for simulating mixing processes in a rolling drum with complex wall boundary;Advanced Powder Technology;2024-01

4. Optimization of preparation process and study on the properties and microstructures of nuclear natural graphite powder for HTR pebble fuel elements;Nuclear Engineering and Design;2024-01

5. Pore Structure Evolution Of A3-3 Matrix Graphite For the Pebble Fuel Elements of High-Temperature Gas-Cooled Reactors During Heat Treatment;2024