| Technical basis for extended dry storage of aluminum-clad spent nuclear fuel E Eidelpes, JJ Jarrell, TE Lister, GP Horne, EH Parker-Quaife, JK Conrad, ... Journal of Nuclear Materials 577, 154299, 2023 | 10 | 2023 |
| Ring compression tests on un-irradiated nuclear fuel rod cladding considering fuel pellet support E Eidelpes, LF Ibarra, RA Medina Journal of Nuclear Materials 510, 446-459, 2018 | 10 | 2018 |
| Probabilistic assessment of peak cladding hoop stress and hydrogen content of PWR SNF rod cladding E Eidelpes, LF Ibarra, RA Medina Nuclear Technology, 2019 | 9 | 2019 |
| Assessment of Critical Experiment Benchmark Applicability to a Large-Capacity HALEU Transportation Package Concept RA Hall, WJ Marshall, E Eidelpes, BM Hom Nuclear Science and Engineering 195 (3), 310-319, 2021 | 5 | 2021 |
| A probabilistic assessment of PWR SNF pinching failure considering hydride-related cladding embrittlement E Eidelpes, LF Ibarra, RA Medina Nuclear Engineering and Design 351, 116-130, 2019 | 5 | 2019 |
| Probabilistic assessment of peak cladding hoop stress and hydrogen content of PWR SNF rod cladding-Research data E Eidelpes, LF Ibarra, RA Medina Mendeley Data, 2018 | 5 | 2018 |
| A probabilistic risk assessment for spent nuclear fuel transportation casks after long-term dry storage considering hydride-related cladding embrittlement E Eidelpes, LF Ibarra, RA Medina IASMiRT, 2017 | 5 | 2017 |
| Fission Battery transportation and siting aspects E Eidelpes, C Bolisetti, A Gupta, A Shafieezadeh Progress in Nuclear Energy 152, 104362, 2022 | 4 | 2022 |
| A High-Assay Low-Enriched Uranium Fuel Transportation Concept E Eidelpes, BM Hom, RA Hall, HE Adkins, JJ Jarrell Nuclear Science and Engineering 195 (3), 279-299, 2021 | 4 | 2021 |
| A probabilistic assessment of PWR SNF cladding pinching failure considering potential transportation accident conditions E Eidelpes, LF Ibarra, RA Medina Nuclear Engineering and Design 358, 110423, 2020 | 4 | 2020 |
| Probabilistic investigations on pinching failure of PWR SNF rods considering hydride-related cladding embrittlement E Eidelpes, LF Ibarra, RA Medina 17th International High-Level Radioactive Waste Management Conference …, 2019 | 4 | 2019 |
| UO2 HALEU Transportation Package Evaluation and Recommendations EF Eidelpes, JJ Jarrell, HE Adkins, BM Hom, JM Scaglione, RA Hall, ... Idaho National Lab.(INL), Idaho Falls, ID (United States), 2019 | 3 | 2019 |
| PRA-Radial hydride embrittlement in spent PWR nuclear fuel cladding E Eidelpes, LF Ibarra, RA Medina 16th International High-Level Radioactive Waste Management Conference …, 2017 | 3 | 2017 |
| Structural, Criticality, and Radiation Dose Calculations to Support SNF Loading into a DOE Standard Canister-21113 E Eidelpes, GM Petersen, ED Kitcher | 3 | |
| Degradation mechanisms in overpack concrete of spent nuclear fuel dry storage systems: A review MT Elshazli, A Ibrahim, E Eidelpes, GO Ilevbare Nuclear Engineering and Design 414, 112632, 2023 | 2 | 2023 |
| Bounding Pressure and Flammability Evaluations for a Department of Energy Standard Canister Loaded with Aluminum-Clad Spent Fuel EF Eidelpes, GM Petersen Idaho National Laboratory (INL), Idaho Falls, ID (United States), 2023 | 2 | 2023 |
| A Probabilistic Assessment of the Structural Integrity of Spent Nuclear Fuel Casks Under Accident Conditions After Long-Term Storage EF Eidelpes The University of Utah, 2019 | 2 | 2019 |
| A risk-informed assessment tool to support review of license amendment requests for spent nuclear fuel dry cask storage systems E Eidelpes, JM Biersdorf Nuclear Engineering and Design 394, 111809, 2022 | 1 | 2022 |
| Development of Dry Cask Risk Tools JM Biersdorf, EF Eidelpes Idaho National Lab.(INL), Idaho Falls, ID (United States), 2020 | 1 | 2020 |
| Probability of pinching failure in PWR SNF after long-term storage E Eidelpes, LF Ibarra, RA Medina WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States), 2019 | 1 | 2019 |
Luis IbarraUniversity of UtahVerified email at utah.edu
