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在“Elsevier电子期刊”中，命中：350条，耗时：0.0500101 秒

在所有数据库中总计命中：289条

1.A two-dimensional experimental investigation on debris bed formation behavior

作者：Shaopeng Lin ; Songbai Cheng ; ^{chengsb3@mail.sysu.edu.cn} ; Guangyu Jiang ; Ziyi Pan ; Hantao Lin ; Shixian Wang ; Li Wang ; Xiaoying Zhang ; Biao Wang

关键词：Sodium-cooled fast reactor ; Core disruptive accident ; Debris bed formation ; Experimental study

刊名：Progress in Nuclear Energy

出版年：2017

2.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

3.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

4.Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor

作者：Chan Bock Lee ; ^{cblee@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author} ; Jin Sik Cheon ; Sung Ho Kim ; Jeong-Yong Park ; Hyung-Kook Joo

关键词：Ferritic&ndash ; Martensitic Steel ; Irradiation Test ; Metal Fuel ; Pyroelectrochemical ; Sodium-cooled Fast Reactor ; Spent Fuel ; Transuranic Fuel

刊名：Nuclear Engineering and Technology

出版年：2016

5.On the Safety and Performance Demonstration Tests of Prototype Gen-IV Sodium-Cooled Fast Reactor and Validation and Verification of Computational Codes

作者：Jong-Bum Kim ; ^{jbkim@kaeri.re.kr" class="auth_mail" title="E-mail the corresponding author} ; Ji-Young Jeong ; Tae-Ho Lee ; Sungkyun Kim ; Dong-Jin Euh ; Hyung-Kook Joo

关键词：Dynamic Characteristic ; Inspection ; Performance Demonstration Test ; Prototype Sodium-Cooled Fast Reactor ; Thermal-Hydraulic ; Validation and Verification Test

刊名：Nuclear Engineering and Technology

出版年：2016

6.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

7.Uranium Enrichment Reduction in the Prototype Gen-IV Sodium-Cooled Fast Reactor (PGSFR) with PBO Reflector

作者：Chihyung Kim ; Donny Hartanto¹ ; Yonghee Kim ; ^{yongheekim@kaist.ac.kr" class="auth_mail" title="E-mail the corresponding author}

关键词：Fuel Cost ; Inverted Reflector ; PbO Reflector ; Prototype Gen-IV Sodium-Cooled Fast Reactor ; U Enrichment Reduction

刊名：Nuclear Engineering and Technology

出版年：2016

8.Delayed Neutron Detection with graphite moderator for clad failure detection in Sodium-Cooled Fast Reactors

关键词：Fast reactor ; Sodium ; Clad failure ; Fission products ; Neutron detection ; Photoneutron noise

刊名：Annals of Nuclear Energy

出版年：2016

9.Advanced materials for structural components of Indian sodium-cooled fast reactors

作者：A.K. Bhaduri ; ^{bhaduri@igcar.gov.in" class="auth_mail" title="E-mail the corresponding author} ; K. Laha ; V. Ganesan ; T. Sakthivel ; M. Nandagopal ; G.V. Prasad Reddy ; J. Ganesh Kumar ; V.D. Vijayanand ; S. Panneer Selvi ; G. Srinivasan ; C.R. Das ; A. Nagesha ; S. Ravi ; P. Parameswaran ; R. Sandhya ; Shaju K. Albert

关键词：Sodium-cooled fast reactors ; Austenitic stainless steel ; Nitrogen-enhanced ; Reactor structural ; Ferritic steel ; Boron-added ; Type-IV cracking ; Steam generator

刊名：International Journal of Pressure Vessels and Piping

出版年：2016

10.Fuel depletion analysis of a small sodium fast reactor with KANEXT and SERPENT

作者：R.C. Lopez-Solis^a ; ¹ ; ^{rcarlos.lope@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; J.L. Franç ; ois^a ; ^{juan.luis.francois@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; G.E. Bastida-Ortiz^a ; ^{gbo729@yahoo.com.mx" class="auth_mail" title="E-mail the corresponding author} ; M. Becker^b ; ^{maarten.becker@kit.edu" class="auth_mail" title="E-mail the corresponding author} ; V.H. Sá ; nchez-Espinoza^b ; ^{victor.sanchez@kit.edu" class="auth_mail" title="E-mail the corresponding author}

关键词：Sodium cooled fast reactor ; Depletion calculations ; KANEXT ; SERPENT

刊名：Annals of Nuclear Energy

出版年：2016

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