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Nuclear Engineering And DesignSCIE

國際簡稱：NUCL ENG DES 參考譯名：核工程與設(shè)計

中科院分區(qū)
3區(qū)
CiteScore分區(qū)
Q2
JCR分區(qū)
Q1

基本信息：: ISSN：0029-5493; E-ISSN：1872-759X; 是否OA：未開放; 是否預(yù)警：否; TOP期刊：否

出版信息：: 出版地區(qū)：SWITZERLAND; 出版商：Elsevier BV; 出版語言：English; 出版周期：Monthly; 出版年份：1964; 研究方向：工程技術(shù)-核科學技術(shù)

評價信息：: 影響因子：1.9; H-index：87; CiteScore指數(shù)：3.4; SJR指數(shù)：0.83; SNIP指數(shù)：1.406

發(fā)文數(shù)據(jù)：: Gold OA文章占比：22.13%; 研究類文章占比：98.66%; 年發(fā)文量：598; 自引率：0.1176...; 開源占比：0.0808; 出版撤稿占比：0.0022...; 出版國人文章占比：0.18; OA被引用占比：0.0361...

投稿咨詢加急見刊

英文簡介期刊介紹 CiteScore數(shù)據(jù) 中科院SCI分區(qū) JCR分區(qū) 發(fā)文數(shù)據(jù) 常見問題

英文簡介Nuclear Engineering And Design期刊介紹

Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology.

Fundamentals of Reactor Design include:

? Thermal-Hydraulics and Core Physics

? Safety Analysis, Risk Assessment (PSA)

? Structural and Mechanical Engineering

? Materials Science

? Fuel Behavior and Design

? Structural Plant Design

? Engineering of Reactor Components

? Experiments

Aspects beyond fundamentals of Reactor Design covered:

? Accident Mitigation Measures

? Reactor Control Systems

? Licensing Issues

? Safeguard Engineering

? Economy of Plants

? Reprocessing / Waste Disposal

? Applications of Nuclear Energy

? Maintenance

? Decommissioning

Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.

期刊簡介Nuclear Engineering And Design期刊介紹

《Nuclear Engineering And Design》自1964出版以來，是一本工程技術(shù)優(yōu)秀雜志。致力于發(fā)表原創(chuàng)科學研究結(jié)果，并為工程技術(shù)各個領(lǐng)域的原創(chuàng)研究提供一個展示平臺，以促進工程技術(shù)領(lǐng)域的的進步。該刊鼓勵先進的、清晰的闡述，從廣泛的視角提供當前感興趣的研究主題的新見解，或?qū)彶槎嗄陙砟硞€重要領(lǐng)域的所有重要發(fā)展。該期刊特色在于及時報道工程技術(shù)領(lǐng)域的最新進展和新發(fā)現(xiàn)新突破等。該刊近一年未被列入預(yù)警期刊名單，目前已被權(quán)威數(shù)據(jù)庫SCIE收錄，得到了廣泛的認可。

該期刊投稿重要關(guān)注點：

預(yù)計審稿時間：約5.4個月
工程技術(shù)
NUCLEAR SCIENCE & TECHNOLOGY
SCIE
中科院3區(qū)
非預(yù)警

Cite Score數(shù)據(jù)（2024年最新版）Nuclear Engineering And Design Cite Score數(shù)據(jù)

CiteScore：3.4
SJR：0.83
SNIP：1.406

學科類別	分區(qū)	排名	百分位
大類：Energy 小類：Nuclear Energy and Engineering	Q2	26 / 77	66%
大類：Energy 小類：Safety, Risk, Reliability and Quality	Q2	81 / 207	61%
大類：Energy 小類：Nuclear and High Energy Physics	Q2	34 / 87	60%
大類：Energy 小類：Mechanical Engineering	Q2	295 / 672	56%
大類：Energy 小類：Waste Management and Disposal	Q3	73 / 134	45%
大類：Energy 小類：General Materials Science	Q3	257 / 463	44%

CiteScore 是由Elsevier(愛思唯爾)推出的另一種評價期刊影響力的文獻計量指標。反映出一家期刊近期發(fā)表論文的年篇均引用次數(shù)。CiteScore以Scopus數(shù)據(jù)庫中收集的引文為基礎(chǔ)，針對的是前四年發(fā)表的論文的引文。CiteScore的意義在于，它可以為學術(shù)界提供一種新的、更全面、更客觀地評價期刊影響力的方法，而不僅僅是通過影響因子(IF)這一單一指標來評價。

歷年Cite Score趨勢圖

中科院SCI分區(qū)Nuclear Engineering And Design 中科院分區(qū)

中科院 2023年12月升級版 綜述期刊：否 Top期刊：否

大類學科	分區(qū)	小類學科	分區(qū)
工程技術(shù)	3區(qū)	NUCLEAR SCIENCE & TECHNOLOGY 核科學技術(shù)	2區(qū)

中科院分區(qū)表 是以客觀數(shù)據(jù)為基礎(chǔ)，運用科學計量學方法對國際、國內(nèi)學術(shù)期刊依據(jù)影響力進行等級劃分的期刊評價標準。它為我國科研、教育機構(gòu)的管理人員、科研工作者提供了一份評價國際學術(shù)期刊影響力的參考數(shù)據(jù)，得到了全國各地高校、科研機構(gòu)的廣泛認可。

中科院分區(qū)表 將所有期刊按照一定指標劃分為1區(qū)、2區(qū)、3區(qū)、4區(qū)四個層次，類似于“優(yōu)、良、及格”等。最開始，這個分區(qū)只是為了方便圖書管理及圖書情報領(lǐng)域的研究和期刊評估。之后中科院分區(qū)逐步發(fā)展成為了一種評價學術(shù)期刊質(zhì)量的重要工具。

歷年中科院分區(qū)趨勢圖

JCR分區(qū)Nuclear Engineering And Design JCR分區(qū)

2023-2024 年最新版

按JIF指標學科分區(qū)	收錄子集	分區(qū)	排名	百分位
學科：NUCLEAR SCIENCE & TECHNOLOGY	SCIE	Q1	10 / 40	76.3%

按JCI指標學科分區(qū)	收錄子集	分區(qū)	排名	百分位
學科：NUCLEAR SCIENCE & TECHNOLOGY	SCIE	Q1	9 / 40	78.75%

JCR分區(qū)的優(yōu)勢在于它可以幫助讀者對學術(shù)文獻質(zhì)量進行評估。不同學科的文章引用量可能存在較大的差異，此時單獨依靠影響因子(IF)評價期刊的質(zhì)量可能是存在一定問題的。因此，JCR將期刊按照學科門類和影響因子分為不同的分區(qū)，這樣讀者可以根據(jù)自己的研究領(lǐng)域和需求選擇合適的期刊。

歷年影響因子趨勢圖

發(fā)文數(shù)據(jù)

2023-2024 年國家/地區(qū)發(fā)文量統(tǒng)計

國家/地區(qū)數(shù)量
CHINA MAINLAND306
USA301
South Korea141
France118
GERMANY (FED REP GER)104
Japan98
India75
Italy65
Switzerland60
Canada50

本刊中國學者近年發(fā)表論文

1、Local modified mesh deformation based on radial basis functions for fluid solid interaction in reactor core
Author: Miao, Xue; Wang, Zhaoshun; Zhu, Ying; Jiang, Zhangcheng; Dong, Lingyu; Wu, Mingyu; Hu, Changjun

Journal: NUCLEAR ENGINEERING AND DESIGN. 2023; Vol. 401, Issue , pp. -. DOI: 10.1016/j.nucengdes.2022.112076
2、Experimental investigation on critical heat flux enhancement by mixing-vanes spacer grid in a vertical annular geometry
Author: Gui, Miao; Liu, Wei; Guo, Junliang; Liu, Yang; Shan, Jianqiang; Kong, Huanjun

Journal: NUCLEAR ENGINEERING AND DESIGN. 2023; Vol. 401, Issue , pp. -. DOI: 10.1016/j.nucengdes.2022.112087
3、The direct measurement of HTR-10 in-core neutron flux
Author: Zhang, Youjie; Fang, Xiang; Jiang, Shengyao; Ma, Tao; Xia, Bing; Guo, Jiong; Liu, Zhiyong

Journal: NUCLEAR ENGINEERING AND DESIGN. 2023; Vol. 401, Issue , pp. -. DOI: 10.1016/j.nucengdes.2022.112085
4、Experimental and numerical study on the length of LZVV in the bubble separator for molten salt reactor
Author: Zeng, Xiaobo; Fan, Guangming; Wang, Meng; Zhao, Le; Yan, Changqi

Journal: NUCLEAR ENGINEERING AND DESIGN. 2023; Vol. 401, Issue , pp. -. DOI: 10.1016/j.nucengdes.2022.112100
5、Engineering uncertainty analysis of the heat transfer of fuel plates
Author: Xu, Wei; Xie, Heng; Li, Jian; Xie, Fei; Shi, Lei

Journal: NUCLEAR ENGINEERING AND DESIGN. 2023; Vol. 402, Issue , pp. -. DOI: 10.1016/j.nucengdes.2022.112117
6、Sensitivity study of thermal hydraulics to corrosion of heat exchange tubes in steam generator
Author: Wang, Weibing; Cheng, Kun; Wang, Bo; Zhang, Meng; Tian, Ruifeng

Journal: NUCLEAR ENGINEERING AND DESIGN. 2023; Vol. 402, Issue , pp. -. DOI: 10.1016/j.nucengdes.2022.112081
7、An energy-group structure optimization from seven to four for PWR-core pin-by-pin calculation
Author: Wang, Sicheng; Cao, Liangzhi; Li, Yunzhao; Wu, Hongchun

Journal: NUCLEAR ENGINEERING AND DESIGN. 2023; Vol. 402, Issue , pp. -. DOI: 10.1016/j.nucengdes.2022.112115
8、Experimental study on flow rate distortion of natural circulation reduced-height scaling
Author: Cheng, Cheng; Lu, Donghua; Su, Qianhua; Huang, Yaji; Zhang, Ge

Journal: NUCLEAR ENGINEERING AND DESIGN. 2023; Vol. 402, Issue , pp. -. DOI: 10.1016/j.nucengdes.2022.112122