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在“Elsevier电子期刊”中，命中：653条，耗时：0.1379341 秒

在所有数据库中总计命中：818条

1.Fast neutron radiography and tomography at a 10 MW research reactor beamline

作者：R. Zboray^a ; ^{robert.zboray@psi.ch} ; R. Adams^b ; Z. Kis^c

关键词：Fast neutron imaging ; Plastic scintillator ; Tomography ; Beamline

刊名：Applied Radiation and Isotopes

出版年：2017

2.Analysis of operator support method based on intelligent dynamic interlock in lead-cooled fast reactor simulator

作者：Peng Xu ; Jianye Wang ; Minghan Yang ; Weitian Wang ; Yunqing Bai ; Yong Song ; ^{yong.song@fds.org.cn" class="auth_mail" title="E-mail the corresponding author}

关键词：Intelligent dynamic interlock ; Operator support ; Reactor ; Nuclear science &technology

刊名：Annals of Nuclear Energy

出版年：2017

3.First-principles and classical molecular dynamics study of threshold displacement energy in beryllium

作者：P.V. Vladimirov^a ; V.A. Borodin^b ; ^c ; ^{Borodin_VA@nrcki.ru}

关键词：Beryllium ; Irradiation ; Displacements ; Defects ; Modeling

刊名：Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms

出版年：2017

4.Development strategy and conceptual design of China Lead-based Research Reactor

作者：Yican Wu ; Yunqing Bai ; Yong Song ; Qunying Huang ; Zhumin Zhao ; Liqin Hu

关键词：Accelerator Driven System (ADS) ; Research reactor ; China LEAd-based Reactor (CLEAR)

刊名：Annals of Nuclear Energy

出版年：2016

5.Evaluation of JRC source term methodology using MAAP5 as a fast-running crisis tool for a BWR4 Mark I reactor

作者：M. Vela-Garcí ; a ; ^{monica.vela-garcia@ec.europa.eu" class="auth_mail" title="E-mail the corresponding author} ; K. Simola ^{kaisa.simola@ec.europa.eu" class="auth_mail" title="E-mail the corresponding author}

关键词：A ; activity ; AC ; alternating current ; ASTEC ; accident source term evaluation code ; BWR ; boiling water reactor is a type of light water nuclear reactor ; DC ; direct current ; DOSE ; MAAP5 module for the dose calculation ; ECCS ; emergency core cooling system ; EPRI ; electric power research institute ; FAI ; Fauske & Associates ; LLC is a world leader in nuclear ; industrial and chemical process safety what developed the MAAP code ; FASTNET ; FAST Nuclear Emergency Tools project ; FASTRUN ; TG FASTRUN ; Internat

刊名：Annals of Nuclear Energy

出版年：2016

6.Evaluation of a Sodium-Water Reaction Event Caused by Steam Generator Tubes Break in the Prototype Generation IV Sodium-cooled Fast Reactor

作者：Sang June Ahn ; ^{enginasj@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author} ; Kwi-Seok Ha ; Won-Pyo Chang ; Seok Hun Kang ; Kwi Lim Lee ; Chi-Woong Choi ; Seung Won Lee ; Jin Yoo ; Jae-Ho Jeong ; Taekyeong Jeong

关键词：Multidimensional Analysis of Reactor Safety-Liquid Metal Reactor ; Prototype Generation IV Sodium-Cooled Fast Reactor ; Sodium&ndash ; Water Advanced Analysis Method-II ; Sodium&ndash ; Water Reaction

刊名：Nuclear Engineering and Technology

出版年：2016

7.A Preliminary Safety Analysis for the Prototype Gen IV Sodium-Cooled Fast Reactor

作者：Kwi Lim Lee ; ^{kllee@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author} ; Kwi-Seok Ha ; Jae-Ho Jeong ; Chi-Woong Choi ; Taekyeong Jeong ; Sang June Ahn ; Seung Won Lee ; Won-Pyo Chang ; Seok Hun Kang ; Jaewoon Yoo

关键词：Anticipated Transient Without Scram ; Design Basis Accidents ; Design Extended Conditions ; MARS-LMR ; MATRA-LMR-FB ; Prototype Gen-IV Sodium-Cooled Fast Reactor ; Source Term

刊名：Nuclear Engineering and Technology

出版年：2016

8.Overall System Description and Safety Characteristics of Prototype Gen IV Sodium Cooled Fast Reactor in Korea

作者：Jaewoon Yoo ; ^{jwyoo@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author} ; Jinwook Chang ; Jae-Yong Lim ; Jin-Sik Cheon ; Tae-Ho Lee ; Sung Kyun Kim ; Kwi Lim Lee ; Hyung-Kook Joo

关键词：Inherent Safety ; Metal Fuel ; Passive Safety ; Pool Type ; Sodium Cooled Fast Reactor

刊名：Nuclear Engineering and Technology

出版年：2016

9.A preliminary stability analysis of MYRRHA Primary Heat Exchanger two-phase tube bundle

作者：Diego Castelliti^a ; ^b ; Guglielmo Lomonaco^b ; ^c ; ^{guglielmo.lomonaco@unige.it" class="auth_mail" title="E-mail the corresponding author}

关键词：ADS ; Accelerator-Driven System ; DHR ; Decay Heat Removal ; DWO ; Density Wave Oscillations ; EoL ; End of Life ; ETPP ; European Technology Pilot Plant ; HLM ; Heavy Liquid Metals ; HTC ; Heat Transfer Coefficient ; HX ; Heat eXchanger ; IPS ; In-Pile Section ; IVST ; In Vessel Storage Tank ; LBE ; Lead&ndash ; Bismuth Eutectic ; LFR ; Lead Fast Reactor ; MYRRHA ; Multi-purpose hYbrid Research Reactor for High-tech Applications ; PHX ; Primary Heat eXchanger ; PP ; Primary Pump ; RVACS ; Reactor Vessel Auxiliary Cooling Syste

刊名：Nuclear Engineering and Design

出版年：2016

10.Method for analyzing passive silicon carbide thermometry with a continuous dilatometer to determine irradiation temperature

作者：Anne A. Campbell^a ; ^{campbellaa@ornl.gov" class="auth_mail" title="E-mail the corresponding author} ; Wallace D. Porter^a ; Yutai Katoh^a ; Lance L. Snead^b

关键词：SiC ; silicon carbide ; XRD ; X-ray diffraction ; TM ; temperature monitor ; DMTR ; Dounreay Materials Testing Reactor ; DFR ; Dounreay Fast Reactor ; JRR-2 ; Japan Research Reactor No.2 ; JMTR ; Japan Materials Testing Reactor ; ORNL ; Oak Ridge National Laboratory ; HFIR ; High Flux Isotope Reactor ; LAMDA ; Low Activation Materials Development and Analysis Laboratory ; CTE ; coefficient of thermal expansion ; CVD ; chemical vapor deposition

刊名：Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms

出版年：2016

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