Thermal Hydraulic Analysis of Sub-channel Blockage Accident Using RELAP5/MOD3.2 in a Pool Type Research Reactor
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Publisher
Springer Nature Singapore
Link
https://link.springer.com/content/pdf/10.1007/978-981-97-3087-2_68
Reference7 articles.
1. Hyung Min Son (2015) Soo Hyung Yang, Cheol Park, Byung Chul Lee: transient thermal–hydraulic analysis of complete single channel blockage accident of generic 10 MW research reactor. Ann Nucl Energy 75:44–53
2. Yuchuan G, Guanbo W et al (2018) Analysis of flow blockage of a single fuel assembly in the JRR-3 20 MW research reactor. In: Proceedings of the 26th international conference on nuclear engineering, ICONE 26
3. Adorni et al (2005) Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core. Ann Nucl Energy 32:1679–1692
4. Veluri VK, Sengupta S (2023) Thermal hydraulic transient analyses for primary coolant system of HFRR using RELAP5. Nuclear Technol 209:765–776
5. RELAP5 Code Manual Volume I (1999) RELAP5/MOD3.2 code manual, code structure, system models, and solution methods. Idaho Falls, USA
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