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SpringerLink电子期刊(118)	NATURE电子期刊(10)	Elsevier电子期刊(797)
ProQuest学位论文(3)	GSW全文库(1)	ACS电子期刊(7)

在“Elsevier电子期刊”中，命中：797条，耗时：0.0689697 秒

在所有数据库中总计命中：936条

1.Method for monitoring the cotton plant vigor based on the WSN technology

作者：Rongbiao Zhang ; ^{867674439@qq.com} ; ^{zrb@ujs.edu.cn} ; Zuowei Ren ; Jian Sun ; Wenjing Tang ; Dongmin Ning ; Yang Qian

关键词：Plant vigor ; Function leaf angle ; Chlorophyll concentration ; Fusion data

刊名：Computers and Electronics in Agriculture

出版年：2017

2.Thermal design of helium cooled divertor for reliable operation

作者：Namkyu Lee^a ; ^{motivebuzz@yonsei.ac.kr" class="auth_mail" title="E-mail the corresponding author} ; Beom Seok Kim^b ; ^{b.s.kim@ifw-dresden.de" class="auth_mail" title="E-mail the corresponding author} ; Taehwan Kim^a ; ^{kimth0610@yonsei.ac.kr" class="auth_mail" title="E-mail the corresponding author} ; Ji-Yeul Bae^a ; ^{jyb1988@yonsei.ac.kr" class="auth_mail" title="E-mail the corresponding author} ; Hyung Hee Cho^a ; ^{hhcho@yonsei.ac.kr" class="auth_mail" title="E-mail the corresponding author}

关键词：Thermal design ; Divertor ; Nuclear fusion ; Heat transfer ; Thermal stress

刊名：Applied Thermal Engineering

出版年：2017

3.Impact analysis of the time trend of TBR and irradiation damage assessment of HCSB blanket for CFETR

作者：Qin Zeng ; ^{zengqin@ustc.edu.cn} ; Hongli Chen ; Zhongliang Lv ; Lei Pan ; Haoran Zhang ; Wei Shi

关键词：Helium cooled solid breeder blanket ; the time trend of TBR ; Irradiation damage ; 3D neutronics model

刊名：Fusion Engineering and Design

出版年：2017

4.Limitation of fusion power plant installation on future power grids under the effect of renewable and nuclear power sources

作者：Shutaro Takeda^a ; ^{takeda.shutarou.55r@st.kyoto-u.ac.jp" class="auth_mail" title="E-mail the corresponding author} ; Shigeki Sakurai^a ; Yasushi Yamamoto^b ; Ryuta Kasada^c ; Satoshi Konishi^c

关键词：Plant design ; Grid stability ; Plasma disruption ; Renewable ; Nuclear power plant

刊名：Fusion Engineering and Design

出版年：2016

5.Supercritical CO₂ Brayton power cycles for DEMO (demonstration power plant) fusion reactor based on dual coolant lithium lead blanket

作者：José ; Ignacio Linares^a ; ^{linares@comillas.edu" class="auth_mail" title="E-mail the corresponding author} ; Alexis Cantizano^a ; ^{alexis.cantizano@comillas.edu" class="auth_mail" title="E-mail the corresponding author} ; Beatriz Yolanda Moratilla^a ; ^{ymoratilla@comillas.edu" class="auth_mail" title="E-mail the corresponding author} ; Ví ; ctor Martí ; n-Palacios^a ; ^{victor.marpal@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; Lluis Batet^b ; ^{lluis.batet@upc.edu" class="auth_mail" title="E-mail the corresponding author}

关键词：Balance of plant ; Fusion power ; Supercritical CO2 Brayton cycle ; DCLL lead (dual coolant lithium-lead) ; DEMO (demonstration power plant)

刊名：Energy

出版年：2016

6.‿/span>PROCESS‿/span>: A systems code for fusion power plants - Part 2: Engineering

作者：M. Kovari ; ^{michael.kovari@ccfe.ac.uk" class="auth_mail" title="E-mail the corresponding author} ; F. Fox ; C. Harrington ; R. Kembleton ; P. Knight ; H. Lux ; J. Morris

关键词：Fusion reactor ; Thermonuclear ; Deuterium ; Tritium ; Economics ; Magnet ; Neutronics ; Reliability ; Availability ; Capacity factor ; Blanket ; Divertor ; DEMO

刊名：Fusion Engineering and Design

出版年：2016

7.Improvement of system code importing evaluation of Life Cycle Analysis of tokamak fusion power reactors

作者：Hikaru Kobori^a ; Ryuta Kasada^a ; ^{r-kasada@iae.kyoto-u.ac.jp" class="auth_mail" title="E-mail the corresponding author} ; Ryoji Hiwatari^b ; Satoshi Konishi^a

关键词：Tokamak ; System code ; CO2 emission ; LCA

刊名：Fusion Engineering and Design

出版年：2016

8.Study of the Fe-Ti/W system for joining applications in high-temperature fusion reactor components

作者：J. de Prado^a ; ^{javier.deprado@urjc.es" class="auth_mail" title="E-mail the corresponding author} ; M. Sá ; nchez^a ; P. Alvaredo^b ; E. Gordo^b ; A. Ureñ ; a^a

关键词：Brazing ; Tungsten ; Thermo-Calc ; DICTRA ; Fusion power plant

刊名：Fusion Engineering and Design

出版年：2016

9.A novel integrated approach for the hazardous radioactive dust source terms estimation in future nuclear fusion power plants

作者：L.A. Poggi ; ^{poggi@ing.uniroma2.it" class="auth_mail" title="E-mail the corresponding author} ; A. Malizia ; J.F. Ciparisse ; P. Gaudio

关键词：Plasma physics ; Physics methods ; Nuclear physics ; Nonlinear physics ; Engineering

刊名：Heliyon

出版年：2016

10.Neutronic performance issues of the breeding blanket options for the European DEMO fusion power plant

作者：U. Fischer^a ; ^{ulrich.fischer@kit.edu" class="auth_mail" title="E-mail the corresponding author} ; C. Bachmann^b ; J.-C. Jaboulay^c ; F. Moro^d ; I. Palermo^e ; P. Pereslavtsev^a ; R. Villari^d

关键词：Neutronics ; DEMO ; Tritium breeding ; Shielding

刊名：Fusion Engineering and Design

出版年：2016

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