| Numerical simulation of droplet deposition onto a liquid film by VOF–MPS hybrid method N Erkan, T Kawakami, H Madokoro, P Chai, Y Ishiwatari, K Okamoto Journal of visualization 18, 381-391, 2015 | 16 | 2015 |
| Estimation of the core degradation and relocation at the Fukushima Daiichi Nuclear Power Station Unit 2 based on RELAP/SCDAPSIM analysis H Madokoro, I Sato Nuclear Engineering and Design 376, 111123, 2021 | 13 | 2021 |
| Dynamic visualization of eutectic reaction between boron carbide and stainless steel S Ueda, H Madokoro, B Jo, M Kondo, N Erkan, K Okamoto Journal of Nuclear Science and Technology 54 (1), 81-88, 2017 | 13 | 2017 |
| Assessment of RELAP/SCDAPSIM/MOD3. 5 against the BWR core degradation experiment CORA-17 H Madokoro, K Okamoto, C Allison, L Siefken, J Hohorst, S Hagen 10th International Topical Meeting on Nuclear Thermal-Hydraulics, Operation …, 2014 | 13 | 2014 |
| SCDAP model improvement with QUENCH-06 analysis H Madokoro, K Okamoto, Y Ishiwatari International Conference on Nuclear Engineering 45950, V005T17A010, 2014 | 12 | 2014 |
| Assessment of the models in RELAP/SCDAPSIM with QUENCH-06 analysis H Madokoro, N Erkan, K Okamoto Journal of Nuclear Science and Technology 52 (11), 1417-1424, 2015 | 9 | 2015 |
| A thermal structural analysis tool for RPV lower head behavior during severe accidents with core melt H MADOKORO, A MIASSOEDOV, T SCHULENBERG Mechanical Engineering Letters 4, 18-00038-18-00038, 2018 | 7 | 2018 |
| RELAP/SCDAPSIM/MOD3. 5 analysis of KIT's QUENCH-14 experiment O Dutkiewicz, KM Marcinkiewicz, H Madokoro, S Shumski, CM Allison, ... EPJ Nuclear Sciences & Technologies 3, 25, 2017 | 7 | 2017 |
| LIVE-J1 experiment on debris melting behavior toward understanding late in-vessel accident progression of the Fukushima Daiichi Nuclear Power Station H Madokoro, T Yamashita, I Sato, X Gaus-Liu Proceedings of 19th International Topical Meeting on Nuclear Reactor Thermal …, 2022 | 6 | 2022 |
| Assessment of a lower head molten pool analysis module using LIVE experiment H Madokoro, A Miassoedov, T Schulenberg Nuclear Engineering and Design 330, 51-58, 2018 | 6 | 2018 |
| Post-Test Analyses of the CMMR-4 Test T Yamashita, H Madokoro, I Sato Journal of Nuclear Engineering and Radiation Science 8 (2), 021701, 2022 | 5 | 2022 |
| BWR lower head penetration failure test focusing on eutectic melting T Yamashita, T Sato, H Madokoro, Y Nagae Annals of Nuclear Energy 173, 109129, 2022 | 4 | 2022 |
| Coupling of a reactor analysis code and a lower head thermal analysis solver H Madokoro, A Miassoedov, T Schulenberg Journal of Nuclear Engineering and Radiation Science 5 (1), 011017, 2019 | 2 | 2019 |
| Time-resolved visualization technique for eutectic reaction between boron carbide and stainless steel at high temperatures S Ueda, H Madokoro, B Jo, M Kondo, N Erkan, K Okamoto Mechanical Engineering Letters 2, 16-00056-16-00056, 2016 | 2 | 2016 |
| The Experimental and Simulation Results of LIVE-J2 Test—Investigation on Heat Transfer in a Solid–Liquid Mixture Pool H Madokoro, T Yamashita, X Gaus-Liu, T Cron, B Fluhrer, I Sato, ... Nuclear Technology 209 (2), 144-168, 2023 | 1 | 2023 |
| Estimation of debris relocation and structure interaction in the pedestal of Fukushima Daiichi Nuclear Power Plant Unit-3 with Moving Particle Semi-implicit (MPS) method X Li, A Yamaji, G Duan, I Sato, M Furuya, H Madokoro, Y Ohishi Annals of Nuclear Energy 169, 108923, 2022 | 1 | 2022 |
| Estimation of long-term ex-vessel debris cooling behavior in Fukushima Daiichi Nuclear Power Plant unit 3 I SATO, A YAMAJI, X LI, H MADOKORO Mechanical Engineering Journal 9 (2), 21-00436-21-00436, 2022 | 1 | 2022 |
| Estimation of Long-Term Ex-Vessel Debris Cooling by Water in Fukushima Daiichi Nuclear Power Plant Unit-3 I Sato, A Yamaji, X Li, H Madokoro International Conference on Nuclear Engineering 85260, V003T12A016, 2021 | 1 | 2021 |
| Preliminary Evaluation on the Relocation Phase of Ex-Vessel Debris of Fukushima Daiichi Nuclear Power Plant Unit-3 X Li, A Yamaji, M Furuya, I Sato, H Madokoro, Y Ohishi International Conference on Nuclear Engineering 85260, V003T12A027, 2021 | 1 | 2021 |
| Modelling of RPV lower head under core melt severe accident condition using OpenFOAM H Madokoro, F Kretzschmar, A Miassoedov | 1 | 2017 |
