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Ikuo Kinoshita
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Proceedings Papers

Application of Sparse Estimation for Best Estimate Plus Uncertainty Analysis of a Small Break LOCA in PWRs

Ikuo Kinoshita
Proc. ASME. IMECE2023, Volume 13: Research Posters; Safety Engineering, Risk and Reliability Analysis, V013T15A017, October 29–November 2, 2023
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2023-111094
https://doi.org/10.1115/IMECE2023-111094
View Paper titled, Application of Sparse Estimation for Best Estimate Plus Uncertainty Analysis of a Small Break LOCA in PWRs
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Topics: Loss of coolant accidents, Pressurized water reactors, Uncertainty analysis, Cladding systems (Building), Errors, Polynomials, Regression models, Temperature, Uncertainty, Uncertainty quantification
Proceedings Papers

Time Series Clustering and Classification for Uncertainty Analysis by MAAP5 Code

Ikuo Kinoshita
Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T01A009, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16437
https://doi.org/10.1115/ICONE2020-16437
View Paper titled, Time Series Clustering and Classification for Uncertainty Analysis by MAAP5 Code
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Topics: Time series, Uncertainty analysis, Uncertainty, Hydrogen, Errors, Regression models, Algorithms, Damage, Fuels
Proceedings Papers

Uncertainty Analysis of Scaling Calculations From LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization Applying to a Four-Loop PWR

Ikuo Kinoshita
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A012, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81920
https://doi.org/10.1115/ICONE26-81920
View Paper titled, Uncertainty Analysis of Scaling Calculations From LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization Applying to a Four-Loop PWR
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Topics: Boilers, Pressurized water reactors, Uncertainty analysis, Uncertainty, Accidents, Accident management, Coolants, High pressure (Physics), Reliability, System failures
Proceedings Papers

RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization and its Uncertainty Quantification by Monte Carlo Method and Wilks Formula Approach

Ikuo Kinoshita, Michio Murase
Proc. ASME. IMECE2016, Volume 6B: Energy, V06BT08A035, November 11–17, 2016
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2016-66638
https://doi.org/10.1115/IMECE2016-66638
View Paper titled, RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization and its Uncertainty Quantification by Monte Carlo Method and Wilks Formula Approach
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Topics: Boilers, Monte Carlo methods, Uncertainty quantification, Uncertainty, Accidents, Temperature, Accident management, Cladding systems (Building), Coolants, Experimental analysis
Proceedings Papers

RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure

Ikuo Kinoshita, Toshihide Torige
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A035, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60525
https://doi.org/10.1115/ICONE24-60525
View Paper titled, RELAP5 Code Uncertainty Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure
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Topics: Accident management, Boilers, Uncertainty analysis, Uncertainty, Accidents, Cladding systems (Building), Coolants, Experimental analysis, High pressure (Physics), Reliability
Journal Articles

Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry

Ikuo Kinoshita, Toshihide Torige, Minoru Yamada
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research-Article
ASME J of Nuclear Rad Sci. April 2016, 2(2): 021003.
Paper No: 15-1012
https://doi.org/10.1115/1.4031377
Published Online: February 29, 2016
View Article titled, Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry
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Topics: Friction, Fuel rods, Porosity, Uncertainty, Uncertainty quantification, Geometry, Flow (Dynamics)
Journal Articles

Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows

Michio Murase, Ikuo Kinoshita, Takayoshi Kusunoki, Dirk Lucas, Akio Tomiyama
Journal: Journal of Nuclear Engineering and Radiation Science
Publisher: ASME
Article Type: Research Papers
ASME J of Nuclear Rad Sci. October 2015, 1(4): 041009.
Paper No: NERS-15-1019
https://doi.org/10.1115/1.4031032
Published Online: September 3, 2015
View Article titled, Countercurrent Flow Limitation in Slightly Inclined Pipes With Elbows
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Topics: Computation, Flow (Dynamics), Pipes, Surges, Water, Boundary-value problems, Drag (Fluid dynamics), Friction, Pressure
Proceedings Papers

Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry

Ikuo Kinoshita, Toshihide Torige, Minoru Yamada
Proc. ASME. IMECE2014, Volume 6B: Energy, V06BT07A025, November 14–20, 2014
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2014-38114
https://doi.org/10.1115/IMECE2014-38114
View Paper titled, Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry
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Topics: Friction, Fuel rods, Geometry, Uncertainty quantification, Uncertainty, Numerical analysis, Accident management, Accidents, Boilers, Cladding systems (Building)
Proceedings Papers

RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure: Investigation on Base Case Result Appropriate for the Best Estimate Plus Uncertainty (BEPU) Application

Ikuo Kinoshita, Toshihide Torige, Michio Murase, Yoshitaka Yoshida, Takeshi Takeda, Akira Satou, Hideo Nakamura
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A022, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30559
https://doi.org/10.1115/ICONE22-30559
View Paper titled, RELAP5 Code Analysis of LSTF Small Break LOCA Tests With Steam Generator Intentional Depressurization as an Accident Management Procedure: Investigation on Base Case Result Appropriate for the Best Estimate Plus Uncertainty (BEPU) Application
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Topics: Accident management, Boilers, Uncertainty, Accidents, Condensation, Coolants, Flow (Dynamics), High pressure (Physics), Pressure, Simulation analysis
Proceedings Papers

Development of the PIRT for the Small-Break Loss-of-Coolant Accident With High Pressure Injection Failure

Ikuo Kinoshita, Minoru Yamada, Toshihide Torige, Michio Murase, Yoshitaka Yoshida
Proc. ASME. IMECE2013, Volume 6B: Energy, V06BT07A047, November 15–21, 2013
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2013-63682
https://doi.org/10.1115/IMECE2013-63682
View Paper titled, Development of the PIRT for the Small-Break Loss-of-Coolant Accident With High Pressure Injection Failure
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Topics: Accidents, Coolants, Failure, High pressure (Physics), Safety, Uncertainty, Accident management, Boilers, Boiling, Cladding systems (Building)
Proceedings Papers

Application of the Statistical Safety Evaluation Method to the Small Break Loca With High Pressure Injection Failure: Quantification of the Uncertainty of Uncovered Core Heat Transfer Model

Toshihide Torige, Ikuo Kinoshita
Proc. ASME. IMECE2013, Volume 6B: Energy, V06BT07A052, November 15–21, 2013
Publisher: American Society of Mechanical Engineers
Paper No: IMECE2013-64305
https://doi.org/10.1115/IMECE2013-64305
View Paper titled, Application of the Statistical Safety Evaluation Method to the Small Break Loca With High Pressure Injection Failure: Quantification of the Uncertainty of Uncovered Core Heat Transfer Model
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Topics: Evaluation methods, Failure, Heat transfer, High pressure (Physics), Safety, Uncertainty, Accident management, Accidents, Boilers, Cladding systems (Building)
Proceedings Papers

Numerical Calculations for Air-Water Tests on CCFL in Different-Scale Models of a PWR Hot Leg

Michio Murase, Ikuo Kinoshita, Yoichi Utanohara, Dirk Lucas, Christophe Valle´e, Akio Tomiyama
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 123-131, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29092
https://doi.org/10.1115/ICONE18-29092
View Paper titled, Numerical Calculations for Air-Water Tests on CCFL in Different-Scale Models of a PWR Hot Leg
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Topics: Pressurized water reactors, Water, Flow (Dynamics), Fluids, Steam
Proceedings Papers

Numerical Calculations on Countercurrent Air-Water Flow in Small-Scale Models of a PWR Hot Leg Using a VOF Model

Michio Murase, Yoichi Utanohara, Ikuo Kinoshita, Noritoshi Minami, Akio Tomiyama
Proc. ASME. ICONE17, Volume 3: Thermal Hydraulics; Current Advanced Reactors: Plant Design, Construction, Workforce and Public Acceptance, 141-148, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75116
https://doi.org/10.1115/ICONE17-75116
View Paper titled, Numerical Calculations on Countercurrent Air-Water Flow in Small-Scale Models of a PWR Hot Leg Using a VOF Model
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Topics: Flow (Dynamics), Pressurized water reactors, Water, Pipes, Two-phase flow, Boilers, Cooling, Heat, Steam, Transient analysis
Proceedings Papers

Quantification of the RELAP5 Model Uncertainty for Application to the Loss-of-RHR Event During the Mid-Loop Operation

Ikuo Kinoshita, Hiroichi Nagumo, Minoru Yamada, Yasuhiro Sasaki, Yoshitaka Yoshida
Proc. ASME. ICONE17, Volume 2: Structural Integrity; Safety and Security; Advanced Applications of Nuclear Technology; Balance of Plant for Nuclear Applications, 611-621, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75550
https://doi.org/10.1115/ICONE17-75550
View Paper titled, Quantification of the RELAP5 Model Uncertainty for Application to the Loss-of-RHR Event During the Mid-Loop Operation
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Topics: Uncertainty, Heat transfer, Condensation, Cooling, Flow (Dynamics), Safety, Stratified flow, Water, Boilers, Boiling