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Elsevier电子期刊(909)

在“Elsevier电子期刊”中，命中：909条，耗时：小于0.01 秒

在所有数据库中总计命中：909条

1.Microstructure and hydrothermal corrosion behavior of NITE-SiC with various sintering additives in LWR coolant environments

作者：Chad M. Parish^a ; ^{parishcm@ornl.gov} ; Kurt A. Terrani^a ; Young-Jin Kim^b ; Takaaki Koyanagi^a ; Yutai Katoh^a

关键词：Silicon carbide ; Liquid phase sintering ; Sintering aid ; Hydrothermal corrosion ; Light water reactor ; Scanning transmission electron microscopy ; Multivariate statistical analysis

刊名：Journal of the European Ceramic Society

出版年：2017

2.Short Communication on “In-situ TEM ion irradiation investigations on U₃Si₂ at LWR temperatures”

作者：Yinbin Miao^a ; ^{ymiao@anl.gov} ; Jason Harp^b ; Kun Mo^a ; Sumit Bhattacharya^c ; Peter Baldo^a ; Abdellatif M. Yacout^a

关键词：Nuclear fuel ; Accident tolerant fuel ; Uranium silicide ; Ion irradiation ; In-situ TEM

刊名：Journal of Nuclear Materials

出版年：2017

3.A fully-implicit high-order system thermal-hydraulics model for advanced non-LWR safety analyses

作者：Rui Hu ^rhu@anl.gov

关键词：High-order ; Fully-implicit ; FEM ; System thermal-hydraulics

刊名：Annals of Nuclear Energy

出版年：2017

4.Total sensitivity and uncertainty analysis for LWR pin-cells with improved UNICORN code

作者：Chenghui Wan^a ; Liangzhi Cao^a ; ^{caolz@mail.xjtu.edu.cn" class="auth_mail" title="E-mail the corresponding author} ; Hongchun Wu^a ; Wei Shen^a ; ^b

关键词：Total sensitivity analysis ; Total uncertainty analysis ; NR approximation ; Neutron slowing-down equation

刊名：Annals of Nuclear Energy

出版年：2017

5.Nuclear Data Uncertainties for Typical LWR Fuel Assemblies and a Simple Reactor Core

作者：D. Rochman^a ; ^{dimitri-alexandre.rochman@psi.ch} ; O. Leray^a ; M. Hursin^a ; H. Ferroukhi^a ; A. Vasiliev^a ; A. Aures^b ; F. Bostelmann^b ; W. Zwermann^b ; O. Cabellos^c ; C.J. Diez^c ; J. Dyrda^c ; N. Garcia-Herranz^d ; E. Castro^d ; S. van der Marck^e ; H. Sjö ; strand^f ; A. Hernandez^f ; M. Fleming^g ; J.-Ch. Sublet^g ; L. Fiorito^h

刊名：Nuclear Data Sheets

出版年：2017

6.A passive decay-heat removal system for an ABWR based on air cooling

作者：Hiroyasu Mochizuki^a ; ^{mochizki@u-fukui.ac.jp}Author Vitae ; Takahiro Yano^bAuthor Vitae

关键词：ABWR ; advanced boiling water reactor ; AC ; air cooler ; ACS ; air cooling system ; CFD ; computational fluid dynamics ; DC ; direct current ; DHRS ; decay heat removal system ; FBR ; fast breeder reactor ; HTT ; heat transfer tube ; IC ; isolation condenser ; LWR ; light water reactor ; MSIV ; main steam isolation valve ; PWR ; pressurized water reactor ; RCIC ; reactor core isolation cooling ; RHR ; residual heat remover ; SBO ; station blackout ; SCAC ; steam condensing-type air cooler ; SP ; suppression pool ; SRV ; safety r

刊名：Nuclear Engineering and Design

出版年：2017

7.Analgesic effect of coumarins from Radix angelicae pubescentis is mediated by inflammatory factors and TRPV1 in a spared nerve injury model of neuropathic pain

作者：Ruili Li^a ; ¹ ; Chao Zhao^a ; ¹ ; Minna Yao^a ; Ying Song^b ; Yin Wu^a ; ; Aidong Wen^a ; ^{lwrcll@163.com}

关键词：CRAP ; Coumarins from Radix angelicae pubescentis ; SNI ; spared nerve injury ; DRG ; dorsal root ganglion ; CRAP ; coumarins from Radix angelicae pubescentis ; IL-1β ; interleukin-1β ; IL-6 ; interleukin-6 ; TNF-α ; tumor necrosis factor-α ; TRPV1 ; Transient receptor potential cation channel 1 ; pERK ; Phosphorylated extracellular regulated protein kinases ; PKC ; protein kinase C ; MAPKs ; mitogen-activated protein kinases ; LOD ; limit of detection ; LOQ ; limit of quantification ; ELISA ; Enzyme-linked immunosorbent

刊名：Journal of Ethnopharmacology

出版年：2017

8.Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE

作者：Benjamin R. Betzler ; ^{betzlerbr@ornl.gov} ; Jeffrey J. Powers ; Andrew Worrall

关键词：Molten salt reactors ; Fuel cycle ; Depletion ; Salt treatment ; Salt separations

刊名：Annals of Nuclear Energy

出版年：2017

9.Screening the design space for optimized plutonium incineration performance in the thorium-based I²S-LWR

刊名：Annals of Nuclear Energy

出版年：2017

10.Use of multiscale zirconium alloy deformation models in nuclear fuel behavior analysis

作者：Robert Montgomery^a ; ^{robert.montgomery@pnnl.gov" class="auth_mail" title="E-mail the corresponding author} ; Carlos Tomé ; ^b ; ^{tome@lanl.gov" class="auth_mail" title="E-mail the corresponding author} ; Wenfeng Liu^c ; ^{wenfeng.liu@anatech.com" class="auth_mail" title="E-mail the corresponding author} ; Alankar Alankar^d ; ^{alankar.alankar@iitb.ac.in" class="auth_mail" title="E-mail the corresponding author} ; Gopinath Subramanian^e ; ^{gopinath.subramanian@usm.edu" class="auth_mail" title="E-mail the corresponding author} ; Christopher Stanek^b ; ^{stanek@lanl.gov" class="auth_mail" title="E-mail the corresponding author}

关键词：Nuclear fuel modeling ; Microstructure deformation modeling ; Zirconium alloy ; Irradiation growth ; Irradiation creep ; Plasticity

刊名：Journal of Computational Physics

出版年：2017

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