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在“Elsevier电子期刊”中，命中：191条，耗时：0.0849891 秒

在所有数据库中总计命中：423条

1.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

2.Assessment of TASS/SMR code for a loss of coolant flow transient using results of integral type test facility

作者：Young-Jong Chung ; ^{chung@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author} ; Soo Hyung Yang ; Kyoo Hwan Bae

关键词：TASS/SMR code ; Integral type pressurized water reactor ; SMART ; VISTA-ITL facility ; Loss of coolant flow transient

刊名：Annals of Nuclear Energy

出版年：2016

3.New burnable absorber for long-cycle low boron operation of PWRs

作者：Jiwon Choe^a ; Ho Cheol Shin^b ; Deokjung Lee^a ; ^{deokjung@unist.ac.kr" class="auth_mail" title="E-mail the corresponding author}

关键词：157Gd ; 167Er ; Burnable absorber ; Fuel cycle ; PWR fuel assembly ; PWR type reactor

刊名：Annals of Nuclear Energy

出版年：2016

4.Parametric studies of the PWR fuel assembly modeling with Monte-Carlo method

作者：Grzegorz Kępisty ; ^{gkepisty@agh.edu.pl" class="auth_mail" title="E-mail the corresponding author} ; Jerzy Cetnar ; Przemysław Stanisz

关键词：BOL ; beginning-of-life ; BWR ; Boiling Water Reactor ; CFD ; Computational Fluid Dynamics ; CRAM ; Chebyshew Rational Approximation Method ; ENDF ; Evaluated Nuclear Data File ; EOL ; end-of-life ; FA ; fuel assembly ; FIMA ; Fissions per Initial Metal Atom ; HTR ; High Temperature Reactor ; JEFF ; Joint Evaluated Fission and Fusion File ; JENDL ; Japanese Evaluated Nuclear Data Library ; LWR ; Light Water Reactor ; MC ; Monte Carlo ; PWR ; Pressurized Water Reactor ; RKG ; Runge&ndash ; Kutta method of Gauss type ; TTA ; Tran

刊名：Annals of Nuclear Energy

出版年：2016

5.VHTR, ADS, and PWR Spent Nuclear Fuel Analysis

作者：J.A.D. Salomé ; ^a ; ^b ; F. Cardoso^a ; ^b ; C.E. Velasquez^a ; ^b ; F. Pereira^a ; ^b ; G.P. Barros^c ; C. Pereira^a ; ^b ; ^{claubia@nuclear.ufmg.br}

关键词：Reactors VHTR ; ADS ; and PWR ; reprocessing fuel ; nuclear fuel cycle ; SCALE 6.0 ; MONTEBURNS and ORIGEN 2.1

刊名：Procedia Chemistry

出版年：2016

6.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

7.A Reduced-Boron OPR1000 Core Based on the BigT Burnable Absorber

作者：Hwanyeal Yu ; Mohd-Syukri Yahya ; Yonghee Kim ; ^{yongheekim@kaist.ac.kr" class="auth_mail" title="E-mail the corresponding author}

关键词：BigT Burnable Absorber ; Critical Boron Concentration ; Fuel Assembly ; OPR1000 ; PWR Type Reactor ; Serpent

刊名：Nuclear Engineering and Technology

出版年：2016

8.A Study of Neutronics Effects of the Spacer Grids in a Typical PWR via Monte Carlo Calculation

作者：Xuan Bach Tran¹ ; Nam Zin Cho ; ^{nzcho@kaist.ac.kr" class="auth_mail" title="E-mail the corresponding author}

关键词：Banded Dissolution Spacer Grids Modeling ; Volume-preserving Streamlined Heterogeneous Spacer Grids

刊名：Nuclear Engineering and Technology

出版年：2016

9.PWR and BWR spent fuel assembly gamma spectra measurements

作者：S. Vaccaro^a ; ; S.J. Tobin^b ; A. Favalli^b ; B. Grogan^c ; P. Jansson^d ; H. Liljenfeldt^c ; ¹ ; V. Mozin^f ; J. Hu^c ; P. Schwalbach^a ; A. Sjö ; land^e ; H. Trellue^b ; D. Vo^b

关键词：Passive gamma ; Burnup ; Cooling time ; Gamma spectroscopy ; Spent fuel ; Nuclear safeguards ; Germanium detector ; Final disposal ; Non-destructive assay

刊名：Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment

出版年：2016

10.Thermal Analysis of Spent Nuclear Fuels Repository

作者：Fernando Pereira^a ; ^b ; Jean Salomé ; ^a ; ^b ; Cristiane Viana^a ; Fabiano Cardoso^a ; ^b ; Carlos E. Velasquez^a ; ^b ; G.P. Barros^c ; Claubia Pereira^a ; ^b ; ^{claubia@nuclear.ufmg.br}

关键词：Thermal analysis ; Ansys CFX ; Ansys transient thermal ; Spent fuels ; Spent fuel pool ; Geological repository

刊名：Procedia Chemistry

出版年：2016

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