Follow
Dave Grabaskas
Dave Grabaskas
Verified email at anl.gov
Title
Cited by
Cited by
Year
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
382016
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
362015
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
242016
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
212016
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
192016
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
122017
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
112017
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
102021
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
92016
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
82020
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
82017
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
82016
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
82016
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
72020
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
72020
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
72016
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
72013
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
62022
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
62019
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
62019
The system can't perform the operation now. Try again later.
Articles 1–20