keff uncertainty quantification and analysis due to nuclear data during the full lifetime burnup calculation for a small-sized prismatic high temperature gas-cooled reactor-Reference-Cited by-同舟云学术

keff uncertainty quantification and analysis due to nuclear data during the full lifetime burnup calculation for a small-sized prismatic high temperature gas-cooled reactor

Published:2021-11 Issue:11 Volume:32 Page:
ISSN:1001-8042
Container-title:Nuclear Science and Techniques
language:en
Short-container-title:NUCL SCI TECH

Author:

Yang Rong-Rui^ORCID,Yuan Yuan,Hao Chen,Ma Ji,Liu Guang-Hao

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://link.springer.com/content/pdf/10.1007/s41365-021-00969-w.pdf

Reference23 articles.

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3. F. Gou, Y. Liu, F.B. Chen et al., Thermal behavior of the HTR-10 under combined PLOFC and ATWS condition initiated by unscrammed control rod withdrawal. Nucl. Sci. Tech. 29, 123 (2018). https://doi.org/10.1007/s41365-018-0472-3

4. D. She, B. Xia, J. Guo et al., Prediction calculations for the first criticality of the HTR-PM using the PANGU code. Nucl. Sci. Tech. 32, 90 (2021). https://doi.org/10.1007/s41365-021-00936-5

5. P.M. Willianms, F.A. Silady, T.D. Dunn et al., MHTGR development in the United States. Prog. Nucl. Energ. 28, 265–346 (1994). https://doi.org/10.1016/0149-1970(94)90002-7

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