| An investigation of thermal stress characteristics by wall temperature measurements at a mixing tee K Miyoshi, M Kamaya, Y Utanohara, A Nakamura Nuclear Engineering and Design 298, 109-120, 2016 | 57 | 2016 |
| Numerical simulation of long-period fluid temperature fluctuation at a mixing tee for the thermal fatigue problem Y Utanohara, A Nakamura, K Miyoshi, N Kasahara Nuclear Engineering and Design 305, 639-652, 2016 | 34 | 2016 |
| An investigation of wall temperature characteristics to evaluate thermal fatigue at a T-junction pipe K Miyoshi, A Nakamura, Y Utanohara, N Takenaka Mechanical Engineering Journal 1 (5), TEP0050-TEP0050, 2014 | 32 | 2014 |
| Conjugate numerical simulation of wall temperature fluctuation at a T-junction pipe Y Utanohara, K Miyoshi, A Nakamura Mechanical Engineering Journal 5 (3), 18-00044-18-00044, 2018 | 24 | 2018 |
| Thermal fatigue damage assessment at mixing tees (elastic-plastic deformation effect on stress and strain fluctuations) M Kamaya, K Miyoshi Nuclear Engineering and Design 318, 202-212, 2017 | 19 | 2017 |
| A review of evaluation methods developed for numerical simulation of the temperature fluctuation contributing to thermal fatigue of a T-junction pipe A Nakamura, Y Utanohara, K Miyoshi, N Kasahara E-Journal of Advanced Maintenance 6 (4), 118-130, 2015 | 17 | 2015 |
| Numerical evaluation of wall temperature measurement method developed to estimate thermal stress at T-junction pipe K Miyoshi, A Nakamura, N Takenaka Mechanical Engineering Journal 1 (2), TEP0006-TEP0006, 2014 | 16 | 2014 |
| Monitoring of inside surface crack growth by strain measurement of the outside surface: a feasibility study M Kamaya, K Miyoshi Nuclear engineering and design 241 (1), 1-11, 2011 | 12 | 2011 |
| Penetration flow into a branch pipe causing thermal fatigue at a mixing tee K Miyoshi, Y Utanohara, M Kamaya Nuclear Engineering and Design 360, 110496, 2020 | 11 | 2020 |
| Temperature fluctuation phenomena in a normally stagnant pipe connected downward to a high velocity and high temperature main pipe A Nakamura, K Miyoshi, T Oumaya, N Takenaka, S Hosokawa, ... Nuclear Engineering and Design 269, 360-373, 2014 | 11 | 2014 |
| Numerical simulation of fluid and wall temperature fluctuation downstream from a mixing tee Y Utanohara, A Nakamura, K Miyoshi 11th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation …, 2016 | 8 | 2016 |
| Experimental study on penetration length in a small size branch pipe in a nuclear power plant T Iguchi, A Saito, N Takenaka, K Miyoshi, A Nakamura | 8 | 2011 |
| Numerical evaluation of wall temperature measurement methods developed to investigate thermal fatigue at T-junction pipe K Miyoshi, A Nakamura, N Takenaka International Conference on Nuclear Engineering 44977, 55-64, 2012 | 6 | 2012 |
| Experimental study on temperature fluctuation phenomena in a closed branch pipe connecting to high velocity and high temperature flow in a main pipe N Takenaka, S Hosokawa, A Saito, T Oumaya, A Nakamura, K Miyoshi International Heat Transfer Conference 49422, 353-362, 2010 | 6 | 2010 |
| Simulation of thermal striping at T-junction pipe using LES with Smagorinsky constants and temperature diffusion schemes A Nakamura, Y Utanohara, K Miyoshi, N Kasahara Proceeding of the Experiment al Validation and Application of CFD and CMFD …, 2012 | 5 | 2012 |
| Crack Growth Monitoring by Strain Measurement of the External Surface of Cracked Pipes: A Feasibility Study M Kamaya, K Miyoshi International Conference on Nuclear Engineering 49293, 289-294, 2010 | 5 | 2010 |
| Heat transfer coefficient suitable for thermal fatigue assessment at a T-junction K Miyoshi, M Kamaya, Y Utanohara, A Nakamura Nuclear Engineering and Design 370, 110916, 2020 | 4 | 2020 |
| I. & Sakaguchi, T.,“ A Tomiyama, K Miyoshi, HZ Tamai A Bubble Tracking Method for the Prediction of Spatial-Evolution of Bubble …, 1998 | 4 | 1998 |
| Temperature characteristics of penetration flow into a branch pipe causing thermal fatigue at a T-junction K Miyoshi Nuclear Engineering and Design 403, 112157, 2023 | 3 | 2023 |
| Investigation of temperature fluctuation phenomena in a stratified steam-water two-phase flow in a simulating pressurizer spray pipe of a pressurized water reactor K Miyoshi, N Takenaka, T Ishida, K Sugimoto Nuclear Engineering and Design 316, 38-45, 2017 | 3 | 2017 |
