Projects per year
Overview
Education/Academic qualification
Eng-Nuclear, Doctorate Degree
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Dive into the research topics where Germina Procop is active. These topic labels come from the works of this person. Together they form a unique fingerprint.
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Researcher collaborations from the last five years
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Projects
- 1 Active
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Molten Salt Reactor Experiment Benchmark Evaluation
Fratoni, M. M. (PI), Procop, G. (CoPI), Powers, J. J. J. J. (CoPI) & Bidaud, A. A. (CoPI)
Nuclear Energy University Program
01/1/16 → …
Project: Research
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Decay Heat Analysis of Non-LWR Spent Fuel Using SCALE
Robert, Y. & Procop, G., 2025, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025. American Nuclear Society, p. 211-220 10 p. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
1 Scopus citations -
Development of a Representative Molten Chloride Fast Reactor Model to Assess the Impact of Nuclear Data
Hirji, R., Procop, G., Bostelmann, F. & Elzohery, R., 2025, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025. American Nuclear Society, p. 1427-1436 10 p. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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EDIM Local Power History and Burnup Inference Based on Destructive Assay Data
Yin, S., Islam, T., Mertyurek, U., Procop, G. & Abdel-Khalik, H., 2025, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025. American Nuclear Society, p. 2176-2185 10 p. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review
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Extending the Nuclide Inventory Validation Basis for High-Burnup Fuel with New Radiochemical Assay Data
Procop, G., Bevard, B. B. & Giaquinto, J. M., 2025, (Accepted/In press) In: Nuclear Science and Engineering.Research output: Contribution to journal › Article › peer-review
Open Access -
Nuclear Data Impact on HTR-10 Pebble Bed Reactor Metrics
Elzohery, R., Bostelmann, F. & Procop, G., 2025, Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025. American Nuclear Society, p. 1636-1645 10 p. (Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2025).Research output: Chapter in Book/Report/Conference proceeding › Conference contribution › peer-review