| Neutronic analysis of candidate accident-tolerant cladding concepts in pressurized water reactors NM George, K Terrani, J Powers, A Worrall, I Maldonado Annals of Nuclear Energy 75, 703-712, 2015 | 261 | 2015 |
| Molten salt reactor neutronics and fuel cycle modeling and simulation with SCALE BR Betzler, JJ Powers, A Worrall Annals of Nuclear Energy 101, 489-503, 2017 | 103 | 2017 |
| What are the most important unanswered research questions in trial retention? A James Lind Alliance Priority Setting Partnership: the PRioRiTy II (Prioritising Retention in … D Brunsdon, L Biesty, P Brocklehurst, V Brueton, D Devane, J Elliott, ... Trials 20, 1-12, 2019 | 73 | 2019 |
| Preconceptual design of a fluoride high temperature salt-cooled engineering demonstration reactor: Motivation and overview AL Qualls, BR Betzler, NR Brown, JJ Carbajo, MS Greenwood, R Hale, ... Annals of Nuclear Energy 107, 144-155, 2017 | 44 | 2017 |
| The AP1000 reactor-the nuclear renaissance option RA Matzie, A Worrall Nuclear Energy 43 (1), 33-45, 2004 | 41 | 2004 |
| Impact of thermal spectrum small modular reactors on performance of once-through nuclear fuel cycles with low-enriched uranium NR Brown, A Worrall, M Todosow Annals of Nuclear Energy 101, 166-173, 2017 | 39 | 2017 |
| Sustainable thorium nuclear fuel cycles: A comparison of intermediate and fast neutron spectrum systems NR Brown, JJ Powers, B Feng, F Heidet, NE Stauff, G Zhang, M Todosow, ... Nuclear Engineering and design 289, 252-265, 2015 | 39 | 2015 |
| Fuel cycle and neutronic performance of a spectral shift molten salt reactor design BR Betzler, S Robertson, EE Davidson, JJ Powers, A Worrall, L Dewan, ... Annals of Nuclear Energy 119, 396-410, 2018 | 38 | 2018 |
| Categorization of used nuclear fuel inventory in support of a comprehensive national nuclear fuel cycle strategy J Wagner | 33 | 2012 |
| Standardized verification of fuel cycle modeling B Feng, B Dixon, E Sunny, A Cuadra, J Jacobson, NR Brown, J Powers, ... Annals of Nuclear Energy 94, 300-312, 2016 | 31 | 2016 |
| Fuel cycle performance of fast spectrum molten salt reactor designs A Rykhlevskii, B Betzler, A Worrall, KD Huff Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | 30 | 2019 |
| Technology Implimentation Plan-ATF FeCrAl Cladding for LWR Application MA Snead, L Snead, KA Terrani, KG Field, A Worrall, KR Robb, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015 | 29* | 2015 |
| A framework for the definition and interpretation of the use of surrogate endpoints in interventional trials O Ciani, AM Manyara, P Davies, D Stewart, CJ Weir, AE Young, J Blazeby, ... EClinicalMedicine 65, 2023 | 26 | 2023 |
| Safeguards challenges for molten salt reactors DN Kovacic, A Worrall, LG Worrall, G Flanagan, D Holcomb, R Bari, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 24 | 2018 |
| Assessment of the Technical Maturity of Generation IV Concepts for Test or Demonstration Reactor Applications HD Gougar, R Bari, T Kim, TE Sowinski, A Worrall Idaho National Laboratory. INL, 2015 | 22 | 2015 |
| Molten salt reactors and associated safeguards challenges and opportunities A Worrall, B Betzler, G Flanagan, D Holcomb, J Hu, DN Kovacic, A Qualls, ... Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2018 | 20 | 2018 |
| Assessment of the Neutronic and Fuel Cycle Performance of the Transatomic Power Molten Salt Reactor Design BR Betzler, S Robertson, EE Davidson, JJ Powers, A Worrall, L Dewan, ... Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), Tech. Rep …, 2017 | 19 | 2017 |
| Experimental and analytical plans for the non-destructive assay system of the swedish encapsulation and repository facilities S Tobin, H Trellue, A Belian, T Burr, M Fensin, A Favalli, J Galloway, ... | 18 | 2015 |
| Reporting of surrogate endpoints in randomised controlled trial reports (CONSORT-Surrogate): extension checklist with explanation and elaboration AM Manyara, P Davies, D Stewart, CJ Weir, AE Young, J Blazeby, ... bmj 386, 2024 | 17 | 2024 |
| Molten salt reactor neutronic and fuel cycle sensitivity and uncertainty analysis JW Bae, B Betzler, A Worrall Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States), 2019 | 17 | 2019 |
Jeffrey J PowersOak Ridge National LaboratoryVerified email at ornl.gov