| 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 | 38 | 2016 |
| Regulatory Technology Development Plan Sodium Fast Reactor: Mechanistic Source Term Development D Grabaskas, A Brunett, M Bucknor, J Sienick, T Sofu http://www.osti.gov/scitech/biblio/1179443, 2015 | 35 | 2015 |
| Regulatory Technology Development Plan-Sodium Fast Reactor. Mechanistic Source Term-Metal Fuel Radionuclide Release D Grabaskas, M Bucknor, J Jerden Argonne National Lab.(ANL), Argonne, IL (United States), 2016 | 24 | 2016 |
| Supervisory Control System for Multi-Modular Advanced Reactors SM Cetiner, MD Mulhlheim, A Guler-Yigitoglu, RJ Belles, SM Greenwood, ... https://www.ornl.gov/sites/default/files/M2AT-16OR2302013%20Milestone …, 2016 | 21 | 2016 |
| Advantages of variance reduction techniques in establishing confidence intervals for quantiles D Grabaskas, MK Nakayama, R Denning, T Aldemir Reliability Engineering & System Safety 149, 187-203, 2016 | 19 | 2016 |
| 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 |
| An assessment of fission product scrubbing in sodium pools following a core damage event in a sodium cooled fast reactor M Bucknor, M Farmer, D Grabaskas Argonne National Lab.(ANL), Argonne, IL (United States), 2017 | 11 | 2017 |
| A Pathway for the Development of Advanced Reactor Mechanistic Source Term Modeling and Simulation Capabilities S Shahbazi, D Grabaskas https://www.osti.gov/biblio/1812897-pathway-development-advanced-reactor …, 2021 | 10 | 2021 |
| A methodology for the development of a reliability database for an advanced reactor probabilistic risk assessment D Grabaskas, AJ Brunett, M Bucknor International Conference on Nuclear Engineering 50022, V002T06A031, 2016 | 9 | 2016 |
| Simplified Radionuclide Transport (SRT) Code: Users Manual D Grabaskas, M Bucknor, J Jerden, T Starkus, S Shahbazi ANL-SRT-4, Rev 2.0. 1, 2020 | 8 | 2020 |
| A Mechanistic Reliability Assessment of RVACS and Metal Fuel Inherent Reactivity Feedbacks D Grabaskas, AJ Brunett, S Passerini, A Grelle Argonne National Lab.(ANL), Argonne, IL (United States), 2017 | 8 | 2017 |
| A methodology for the integration of a mechanistic source term analysis in a probabilistic framework for advanced reactors D Grabaskas, AJ Brunett, M Bucknor International Conference on Nuclear Engineering 50022, 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 International Conference on Nuclear Engineering 50022, V002T06A029, 2016 | 8 | 2016 |
| Functional Requirements for the Modeling and Simulation of Advanced (Non-LWR) Reactor Mechanistic Source Term S Shahbazi, D Grabaskas https://publications.anl.gov/anlpubs/2020/06/160493.pdf, 2020 | 7 | 2020 |
| PRISM Balance-of-Plant Analysis Failure Modes and Reliability Data D Grabaskas, AJ Brunett interim report ORNL, Argonne National Laboratory, Argonne, IL (Aug. 2016), 2016 | 7 | 2016 |
| Review of Passive System Reliability Modeling Approaches for Advanced Small Modular Reactors D Grabaskas, T Sofu Proceedings of ANS PSA 2013 International Topical Meeting on Probabilistic …, 2013 | 7 | 2013 |
| 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 196 (sup1), 278-288, 2022 | 6 | 2022 |
| Technical Letter Report on The Assessment of Tritium Detection and Control in Molten Salt Reactors: Final Report D Grabaskas, T Fei, J Jerden https://www.nrc.gov/docs/ML2015/ML20157A155.pdf, 2020 | 6 | 2020 |
| Development of a mechanistic source term approach for liquid-fueled Molten Salt Reactors J Jerden, D Grabaskas, M Bucknor Argonne National Lab.(ANL), Argonne, IL (United States), 2019 | 6 | 2019 |
| Safety design strategy for the versatile test reactor DM Gerstner, J Andrus, D Grabaskas, M Bucknor Transactions of the American Nuclear Society 121, 1383-1386, 2019 | 6 | 2019 |
Matthew BucknorArgonne National LaboratoryVerified email at anl.gov
