| An overview of dual coolant Pb–17Li breeder first wall and blanket concept development for the US ITER-TBM design CPC Wong, S Malang, M Sawan, M Dagher, S Smolentsev, B Merrill, ... Fusion Engineering and Design 81 (1-7), 461-467, 2006 | 138 | 2006 |
| First result of deuterium retention in neutron-irradiated tungsten exposed to high flux plasma in TPE M Shimada, Y Hatano, P Calderoni, T Oda, Y Oya, M Sokolov, K Zhang, ... Journal of Nuclear Materials 415 (1), S667-S671, 2011 | 92 | 2011 |
| Development path for Z-pinch IFE C Olson, G Rochau, S Slutz, C Morrow, R Olson, M Cuneo, D Hanson, ... Fusion Science and Technology 47 (3), 633-640, 2005 | 82 | 2005 |
| The deuterium depth profile in neutron-irradiated tungsten exposed to plasma M Shimada, G Cao, Y Hatano, T Oda, Y Oya, M Hara, P Calderoni Physica Scripta 2011 (T145), 014051, 2011 | 77 | 2011 |
| Comparison of deuterium retention for ion-irradiated and neutron-irradiated tungsten Y Oya, M Shimada, M Kobayashi, T Oda, M Hara, H Watanabe, Y Hatano, ... Physica Scripta 2011 (T145), 014050, 2011 | 76 | 2011 |
| Overview of fusion blanket R&D in the US over the last decade MA Abdou, NB Morley, AY Ying Nuclear Engineering and Technology 37 (5), 401-422, 2005 | 68 | 2005 |
| Measurement of tritium permeation in flibe (2LiF–BeF2) P Calderoni, P Sharpe, M Hara, Y Oya Fusion Engineering and Design 83 (7-9), 1331-1334, 2008 | 66 | 2008 |
| Overview of the US–Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten M Shimada, Y Hatano, Y Oya, T Oda, M Hara, G Cao, M Kobayashi, ... Fusion Engineering and Design 87 (7-8), 1166-1170, 2012 | 60 | 2012 |
| Retention behavior in tungsten and molybdenum exposed to high fluences of deuterium ions in TPE JP Sharpe, RD Kolasinski, M Shimada, P Calderoni, RA Causey Journal of nuclear materials 390, 709-712, 2009 | 57 | 2009 |
| Control of molten salt corrosion of fusion structural materials by metallic beryllium P Calderoni, P Sharpe, H Nishimura, T Terai Journal of Nuclear Materials 386, 1102-1106, 2009 | 44 | 2009 |
| Feasibility analysis of vacuum sieve tray for tritium extraction in the HCLL test blanket system F Okino, P Calderoni, R Kasada, S Konishi Fusion Engineering and Design 109, 1748-1753, 2016 | 25 | 2016 |
| Conceptual design of forced convection molten salt heat transfer testing loop MS Sohal, P Sabharwall, P Calderoni, AK Wertsching, SB Grover Idaho National Lab.(INL), Idaho Falls, ID (United States), 2010 | 25 | 2010 |
| Finalization of the conceptual design of the auxiliary circuits for the European test blanket systems A Aiello, BE Ghidersa, M Utili, L Vala, T Ilkei, G Di Gironimo, R Mozzillo, ... Fusion Engineering and Design 96, 56-63, 2015 | 24 | 2015 |
| Progresses and challenges in supporting activities toward a license to operate European TBM systems in ITER Y Poitevin, I Ricapito, M Zmitko, F Tavassoli, N Thomas, G De Dinechin, ... Fusion Engineering and Design 89 (7-8), 1113-1118, 2014 | 21 | 2014 |
| Current design of the European TBM systems and implications on DEMO breeding blanket P Calderoni, A Aiello, B Ghidersa, Y Poitevin, J Pacheco Fusion Engineering and Design 109, 1326-1330, 2016 | 19 | 2016 |
| Heat transfer salts for nuclear reactor systems-chemistry control, corrosion mitigation, and modeling M Anderson, K Sridharan, D Morgan, P Peterson, P Calderoni, R Scheele, ... Univ. of Wisconsin, Madison, WI (United States); Univ. of California …, 2015 | 19 | 2015 |
| Corrosion issues in molten salt reactor (MSR) systems P Calderoni, C Cabet Nuclear Corrosion Science and Engineering, 842-865, 2012 | 19 | 2012 |
| Solid breeder test blanket module design and analysis A Ying, M Abdou, P Calderoni, S Sharafat, M Youssef, Z An, A Abou-Sena, ... Fusion engineering and design 81 (1-7), 659-664, 2006 | 19 | 2006 |
| Technologies and modelling issues for tritium processing in the European Test Blanket Systems and perspectives for DEMO I Ricapito, P Calderoni, Y Poitevin, A Aiello Fusion Engineering and Design 89 (7-8), 1469-1475, 2014 | 18 | 2014 |
| Application of tritium imaging plate technique to examine tritium behaviors on the surface and in the bulk of plasma-exposed materials T Otsuka, M Shimada, R Kolasinski, P Calderoni, JP Sharpe, Y Ueda, ... Journal of nuclear materials 415 (1), S769-S772, 2011 | 18 | 2011 |
Masashi Shimada, Ph.DIdaho National Laboratory在 inl.gov 的电子邮件经过验证
