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- [6] Calculation and Uncertainty Analysis of Core Parameters of Advanced Lead-Cooled Modular Nuclear Reactor Using New Nuclear Data Libraries JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE, 2024, 10 (03):
- [7] Pressurized water reactor spent nuclear fuel data library produced with the Serpent2 code DATA IN BRIEF, 2020, 33
- [10] Evaluating the Effect of Decay and Fission Yield Data Uncertainty on Spent Nuclear Fuel Source Term Using Serpent 2 28TH INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE (NENE 2019), 2019,