Development of V2UP (V&V plus uncertainty quantification and prediction) procedure for high cycle thermal fatigue in fast reactor—Framework for V&V and numerical prediction

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2015.07.010 ◽

2016 ◽

Vol 299 ◽

pp. 174-183 ◽

Cited By ~ 2

Author(s):

Masaaki Tanaka ◽

Shuji Ohno ◽

Hiroyuki Ohshima

Keyword(s):

Uncertainty Quantification ◽

Fast Reactor ◽

Thermal Fatigue ◽

Numerical Prediction ◽

High Cycle Thermal Fatigue

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Investigation of V&V process for thermal fatigue issue in a sodium cooled fast reactor – Application of uncertainty quantification scheme in verification and validation with fluid-structure thermal interaction problem in T-junction piping system

Nuclear Engineering and Design ◽

10.1016/j.nucengdes.2014.03.006 ◽

2014 ◽

Vol 279 ◽

pp. 91-103 ◽

Cited By ~ 6

Author(s):

Masaaki Tanaka

Keyword(s):

Uncertainty Quantification ◽

Fast Reactor ◽

Thermal Fatigue ◽

Verification And Validation ◽

Piping System ◽

Thermal Interaction ◽

Fluid Structure ◽

Reactor Application ◽

Interaction Problem

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Computational Experiment of Multidisciplinary Phenomena in Fast Reactor Applications : (1) High-Cycle Thermal Fatigue and Thermohydraulics

The Proceedings of The Computational Mechanics Conference ◽

10.1299/jsmecmd.2002.15.765 ◽

2002 ◽

Vol 2002.15 (0) ◽

pp. 765-766

Author(s):

Toshiharu MURAMATSU

Keyword(s):

Fast Reactor ◽

Thermal Fatigue ◽

Computational Experiment ◽

High Cycle Thermal Fatigue

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S0803-1-2 Investigation on High Cycle Thermal Fatigue Evaluation Method against Temperature Fluctuation near Core Outlet in Sodium Cooled Fast Reactor

The proceedings of the JSME annual meeting ◽

10.1299/jsmemecjo.2009.3.0_163 ◽

2009 ◽

Vol 2009.3 (0) ◽

pp. 163-164

Author(s):

Nobuyuki KIMURA ◽

Jun Kobayashi ◽

Hideki KAMIDE

Keyword(s):

Fast Reactor ◽

Thermal Fatigue ◽

Temperature Fluctuation ◽

Evaluation Method ◽

Fatigue Evaluation ◽

High Cycle Thermal Fatigue

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B134 Establishment of Numerical Estimation Method for High Cycle Thermal Fatigue Estimation in Sodium-cooled Fast Reactor : (1) Conceptual Model Development for Numerical Estimation by using PIRT Method

The Proceedings of the National Symposium on Power and Energy Systems ◽

10.1299/jsmepes.2015.20.55 ◽

2015 ◽

Vol 2015.20 (0) ◽

pp. 55-58

Author(s):

Masaaki TANAKA

Keyword(s):

Conceptual Model ◽

Fast Reactor ◽

Thermal Fatigue ◽

Model Development ◽

Estimation Method ◽

Numerical Estimation ◽

Fatigue Estimation ◽

High Cycle Thermal Fatigue

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S0301-6-6 Development of elevated temperature structural design method for fast reactor vessels : Part 3 Critical temperature difference of 316FR steel and Inconel-718 for high-cycle thermal fatigue

The proceedings of the JSME annual meeting ◽

10.1299/jsmemecjo.2009.1.0_125 ◽

2009 ◽

Vol 2009.1 (0) ◽

pp. 125-126

Author(s):

Satoshi OKAJIMA ◽

Nobuhiro ISOBE ◽

Nobuchika KAWASAKI ◽

Masayuki SUKEKAWA

Keyword(s):

Elevated Temperature ◽

Critical Temperature ◽

Temperature Difference ◽

Fast Reactor ◽

Thermal Fatigue ◽

Structural Design ◽

Inconel 718 ◽

Design Method ◽

High Cycle Thermal Fatigue

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Establishment of Numerical Estimation Method for High Cycle Thermal Fatigue in Sodium-cooled Fast Reactor

The Proceedings of the National Symposium on Power and Energy Systems ◽

10.1299/jsmepes.2017.22.a215 ◽

2017 ◽

Vol 2017.22 (0) ◽

pp. A215

Author(s):

Masaaki TANAKA ◽

Jun KOBAYASHI ◽

Kazuyoshi NAGASAWA

Keyword(s):

Fast Reactor ◽

Thermal Fatigue ◽

Estimation Method ◽

Numerical Estimation ◽

High Cycle Thermal Fatigue

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Assessment study about the risk of Wilks’ formula for uncertainty quantification of design extension condition scenarios in prototype Gen-IV sodium fast reactor

Journal of Nuclear Science and Technology ◽

10.1080/00223131.2018.1435317 ◽

2018 ◽

Vol 55 (7) ◽

pp. 746-755

Author(s):

Sarah Kang ◽

Jaeseok Heo ◽

ChiWoong Choi ◽

Kwi-Seok Ha ◽

Sung Won Bae

Keyword(s):

Uncertainty Quantification ◽

Fast Reactor ◽

Assessment Study ◽

Sodium Fast Reactor ◽

Gen Iv

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ICONE15-10296 Control Technique of High-Cycle Thermal Fatigue at a Mixing Tee With a 90-degree Bend Upstream by Changing its Location

The Proceedings of the International Conference on Nuclear Engineering (ICONE) ◽

10.1299/jsmeicone.2007.15._icone1510_150 ◽

2007 ◽

Vol 2007.15 (0) ◽

pp. _ICONE1510-_ICONE1510

Author(s):

Hiroshi Ohara ◽

Kazuhisa Yuki ◽

Hoseini Seyed Mohammad ◽

Hidetoshi Hashizume ◽

Masaaki Tanaka

Keyword(s):

Thermal Fatigue ◽

Control Technique ◽

High Cycle Thermal Fatigue

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Fatigue Damage Assessment for High-Cycle Thermal Fatigue at Mixing Tee

The Proceedings of Mechanical Engineering Congress Japan ◽

10.1299/jsmemecj.2016.j0310303 ◽

2016 ◽

Vol 2016 (0) ◽

pp. J0310303

Author(s):

Masayuki KAMAYA

Keyword(s):

Fatigue Damage ◽

Thermal Fatigue ◽

Damage Assessment ◽

High Cycle Thermal Fatigue

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High Cycle Thermal Fatigue Failure Experiences in Process Plant

The Proceedings of Mechanical Engineering Congress Japan ◽

10.1299/jsmemecj.2018.j0320304 ◽

2018 ◽

Vol 2018 (0) ◽

pp. J0320304

Author(s):

Shinichiro KANAMARU ◽

Yoshinori YAMADA ◽

Shaoxing QIAN

Keyword(s):

Fatigue Failure ◽

Thermal Fatigue ◽

Process Plant ◽

High Cycle Thermal Fatigue

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