Abstract
Description of the TVS-K fuel assembly designed for operation in PWR cores is presented. Results of experimental and computational justification of thermal-hydraulic characteristics of the TVS-K are given. It is shown that the design characteristics of the TVS-K provide the necessary thermal-hydraulic parameters and do not impose additional limitations on operation of homogeneous and mixed PWR cores.
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Abbreviations
- CHF:
-
Critical heat flux
- DNBR:
-
Departure from nucleate boiling ratio
- EPRI:
-
Electric Power Research Institute
- IFM:
-
Intermediate flow mixing
- FA:
-
Fuel assembly
- MDNBR:
-
Minimal departure from nucleate boiling ratio
- NPP:
-
Nuclear power plant
- PWR:
-
Pressurized water reactor
- SG:
-
Spacer grids
- STDP:
-
Statistical thermal design procedure
References
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J. Robeyns, F. Parmentier, G. Peeters. Application of a statistical thermal design procedure to evaluate the PWR DNBR Safety Analysis Limits. In: 9th International Conference on Nuclear Engineering (ICONE 9) on Proceedings, Nice, France, April 8–12 (2001).
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© 2024 The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.
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Lukyanov, V.E. (2024). Thermal-Hydraulic Characteristics of TVS-K Fuel Assembly. In: Liu, J., Jiao, Y. (eds) Proceedings of the 2023 Water Reactor Fuel Performance Meeting. WRFPM 2023. Springer Proceedings in Physics, vol 299. Springer, Singapore. https://doi.org/10.1007/978-981-99-7157-2_24
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DOI: https://doi.org/10.1007/978-981-99-7157-2_24
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Online ISBN: 978-981-99-7157-2
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