Publication & Citation Trends
Publications
0 total
Carbon materials in a high temperature gas-cooled reactor pebble-bed module
Cited by 24
Semantic Scholar
Nuclear graphite for high temperature gas-cooled reactors
Cited by 96
Semantic Scholar
Oxidation Behavior of Matrix Graphite and Its Effect on Compressive Strength OA
Cited by 19
Semantic Scholar
ヒナギキョウのメタノール抽出物の肝臓保護作用と化学成分【JST・京大機械翻訳】
Cited by 0
Semantic Scholar
A3‐3マトリックス黒鉛の酸化挙動を【JST・京大機械翻訳】
Cited by 0
Semantic Scholar
The oxidation behavior of A3-3 matrix graphite
Cited by 9
Semantic Scholar
Study on the carbonization process in the fabrication of pebble fuel elements
Cited by 8
Semantic Scholar
Research on the overcoating process in the manufacture of spherical fuel elements for HTGR
Cited by 3
Semantic Scholar
Preparation of spherical fuel elements for HTR-PM in INET
Cited by 60
Semantic Scholar
Research Topics
Graphite, nuclear technology, radiation studies
(23)
Nuclear Materials and Properties
(17)
Nuclear reactor physics and engineering
(12)
Nuclear and radioactivity studies
(12)
Carbon Nanotubes in Composites
(8)
Affiliations
Key Laboratory of Nuclear Radiation and Nuclear Energy Technology
Beijing Obstetrics and Gynecology Hospital
State Key Laboratory of New Ceramics and Fine Processing
Beijing Sport University
Tsinghua University