发文分析
近年国家/地区发文量统计
| 国家/地区 | 数量 |
|---|---|
| USA | 671 |
| CHINA MAINLAND | 481 |
| France | 183 |
| Japan | 166 |
| GERMANY (FED REP GER) | 147 |
| England | 146 |
| South Korea | 88 |
| India | 86 |
| Russia | 69 |
| Belgium | 63 |
近年机构发文量统计
| 机构 | 数量 |
|---|---|
| UNITED STATES DEPARTMENT OF ENERGY (DOE) | 451 |
| CHINESE ACADEMY OF SCIENCES | 160 |
| CEA | 121 |
| CENTRE NATIONAL DE LA RECHERCHE SCIENTIFIQUE (... | 109 |
| HELMHOLTZ ASSOCIATION | 74 |
| UNIVERSITY OF TENNESSEE SYSTEM | 73 |
| UNIVERSITE PARIS SACLAY | 68 |
| CHINESE ACADEMY OF ENGINEERING PHYSICS | 60 |
| BHABHA ATOMIC RESEARCH CENTER (BARC) | 55 |
| UNIVERSITY OF CALIFORNIA SYSTEM | 55 |
近年文章引用他刊数据
| 文章名称 | 引用次数 |
|---|---|
| Accident tolerant fuel cladding development: Promise, st... | 74 |
| Primary radiation damage: A review of current understand... | 51 |
| Oxide inclusions in laser additive manufactured stainles... | 32 |
| Early studies on Cr-Coated Zircaloy-4 as enhanced accide... | 28 |
| Recent progress in the development of SiC composites for... | 21 |
| Behavior of tungsten under irradiation and plasma intera... | 19 |
| Response of Cr and Cr-Al coatings on Zircaloy-2 to high ... | 16 |
| Fission gas release from UO2 nuclear fuel: A review | 16 |
| The thermo-mechanical behaviour of W-Cu metal matrix com... | 15 |
| Development of low-Cr ODS FeCrAl alloys for accident-tol... | 14 |
近年被他刊引用数据
| 期刊名称 | 引用次数 |
|---|---|
| J NUCL MATER | 6944 |
| FUSION ENG DES | 1155 |
| NUCL MATER ENERGY | 924 |
| NUCL FUSION | 902 |
| ACTA MATER | 818 |
| NUCL INSTRUM METH B | 790 |
| J ALLOY COMPD | 556 |
| COMP MATER SCI | 492 |
| MAT SCI ENG A-STRUCT | 487 |
| CORROS SCI | 485 |