| Regulatory Technology Development Plan-Sodium Fast Reactor: Mechanistic Source Term–Trial Calculation D Grabaskas, M Bucknor, J Jerden, AJ Brunett, M Denman, A Clark, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 50* | 2016 |
| Regulatory Technology Development Plan-Sodium Fast Reactor: Mechanistic Source Term-Trial Calculation: Work Plan D Grabaskas, M Bucknor, J Jerden, AJ Brunett Argonne National Laboratory (ANL), 2016 | 50* | 2016 |
| Regulatory Technology Development Plan-Sodium Fast Reactor: Mechanistic Source Term Development-Trial Calculation D Grabaskas, M Bucknor, J Jerden, AJ Brunett, M Denman, A Clark, ... Argonne National Laboratory, ANL-ART-49, 2016 | 38* | 2016 |
| Conceptual Design of a Pilot-Scale Pyroprocessing Facility YI Chang, RW Benedict, MD Bucknor, J Figueroa, JE Herceg, TR Johnson, ... Nuclear Technology, 1-19, 2018 | 35 | 2018 |
| Regulatory Technology Development Plan Sodium Fast Reactor. Mechanistic Source Term Development DS Grabaskas, AJ Brunett, MD Bucknor, JJ Sienicki, T Sofu Argonne National Laboratory (ANL), 2015 | 35 | 2015 |
| A status review on the thermal stratification modeling methods for Sodium-cooled Fast Reactors Z Wu, C Lu, S Morgan, SB y Leon, M Bucknor Progress in Nuclear Energy 125, 103369, 2020 | 27 | 2020 |
| Regulatory Technology Development Plan-Sodium Fast Reactor: Mechanistic Source Term-Metal Fuel Radionuclide Release D Grabaskas, M Bucknor, J Jerden Argonne National Laboratory (ANL), 2016 | 24 | 2016 |
| Final Project Report on RCCS Testing with Air-based NSTF DD Lisowski, CD Gerardi, DJ Kilsdonk, NC Bremer, SW Lomperski, R Hu, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 18 | 2016 |
| Modeling of Electrical Cable Failure in a Dynamic Assessment of Fire Risk MD Bucknor The Ohio State University, 2013 | 13 | 2013 |
| An Efficient 1-D Thermal Stratification Model for Pool-Type Sodium-Cooled Fast Reactors C Lu, Z Wu, S Morgan, J Schneider, M Anderson, L Xu, E Baglietto, ... Nuclear Technology, 1-16, 2020 | 12 | 2020 |
| Advanced Reactor Passive System Reliability Demonstration Analysis for an External Event M Bucknor, D Grabaskas, AJ Brunett, A Grelle Nuclear Engineering and Technology 49 (2), 360-372, 2017 | 12 | 2017 |
| Thermal Stratification Analysis for Sodium Fast Reactors J Schneider, M Anderson, E Baglietto, S Bilbao y Leon, M Bucknor, ... 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018), 2018 | 11 | 2018 |
| Water NSTF Design, Instrumentation, and Test Planning DD Lisowski, CD Gerardi, R Hu, DJ Kilsdonk, NC Bremer, SW Lomperski, ... Argonne National Lab.(ANL), Argonne, IL (United States), 2017 | 11 | 2017 |
| An Assessment of Fission Product Scrubbing in Sodium Pools Following a Core Damage Event in a Sodium Cooled Fast Reactor M Bucknor, MT Farmer, D Grabaskas International Confernce on Fast Reactors and Related Fuel Cycles: Next …, 2017 | 11 | 2017 |
| Experimental observations of natural circulation flow in the NSTF DD Lisowski, AR Kraus, MD Bucknor, R Hu, MT Farmer Nuclear Engineering and Design 306, 124-132, 2016 | 11 | 2016 |
| Progress Report on Computational Analyses of Water-Based NSTF Q Lv, A Kraus, R Hu, M Bucknor, D Lisowski, D Nunez Argonne National Lab.(ANL), Argonne, IL (United States), 2017 | 9 | 2017 |
| A Methodology for the Development of a Reliability Database for an Advanced Reactor Probabilistic Risk Assessment D Grabaskas, AJ Brunett, M Bucknor 2016 24th International Conference on Nuclear Engineering, V002T06A031 …, 2016 | 9 | 2016 |
| A Methodology for the Integration of a Mechanistic Source Term Analysis in a Probabilistic Framework for Advanced Reactors D Grabaskas, AJ Brunett, M Bucknor 2016 24th International Conference on Nuclear Engineering, V002T06A030 …, 2016 | 8 | 2016 |
| A Methodology for the Integration of Passive System Reliability With Success Criteria in a Probabilistic Framework for Advanced Reactors AJ Brunett, D Grabaskas, M Bucknor, S Passerini 2016 24th International Conference on Nuclear Engineering, V002T06A029 …, 2016 | 8 | 2016 |
| Development of the Versatile Test Reactor Probabilistic Risk Assessment D Grabaskas, J Andrus, D Henneke, J Li, M Bucknor, M Warner Nuclear Science and Engineering, 1-11, 2022 | 6 | 2022 |
Dave GrabaskasArgonne National LaboratoryVerified email at anl.gov
