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Article

Validation of the New TLANESY Thermal–Hydraulic Code with Data from the QUENCH-01 Experiment

by
Nahum Contreras-Pérez
1,
Heriberto Sánchez-Mora
2,*,
Sergio Quezada-García
1,
Armando Miguel Gómez Torres
3 and
Ricardo Isaac Cázares Ramírez
1
1
Facultad de Ingeniería, Universidad Nacional Autónoma de México, Ciudad de México 04510, Mexico
2
Departamento de Ingeniería de Procesos e Hidráulica, Universidad Autónoma Metropolitana-Iztapalapa, Ciudad de México 09310, Mexico
3
Instituto Nacional de Investigaciones Nucleares, Carretera México-Toluca, La Marquesa s/n, Ocoyoacac, Ciudad de México 52750, Mexico
*
Author to whom correspondence should be addressed.
J. Nucl. Eng. 2025, 6(3), 32; https://doi.org/10.3390/jne6030032
Submission received: 10 May 2025 / Revised: 9 July 2025 / Accepted: 31 July 2025 / Published: 12 August 2025
(This article belongs to the Special Issue Validation of Code Packages for Light Water Reactor Physics Analysis)
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Abstract

Hydrogen generation and the correct simulation of severe accidents have been of utmost importance since the Fukushima Dai-ichi accident. QUENCH experiments are quite useful for validating mathematical models implemented in system codes for early-phase severe accidents, where hydrogen generation, fuel rod temperature, and their deterioration during these conditions are of vital importance. This paper presents a new system code, TLANESY, designed for the simulation of thermal–hydraulic systems with two-phase flow (mainly water) and with application in the analysis of severe accidents during the early phase. The computational implementation consists of fast-running numerical methods and their validation with experimental data from the QUENCH-01 experiment. The results showed an error with respect to the total hydrogen generation of approximately 0.6%. A stand-alone sensitivity analysis was also performed with some parameters related to the cladding, where it was shown that variation in the thermal conductivity by 15% can alter the total hydrogen generation by up to 5%, indicating that impurities in this material can have a significant impact on this Figure of Merit.
Keywords: light water reactor; validation; sensitivity analysis; reactor physics light water reactor; validation; sensitivity analysis; reactor physics

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MDPI and ACS Style

Contreras-Pérez, N.; Sánchez-Mora, H.; Quezada-García, S.; Gómez Torres, A.M.; Cázares Ramírez, R.I. Validation of the New TLANESY Thermal–Hydraulic Code with Data from the QUENCH-01 Experiment. J. Nucl. Eng. 2025, 6, 32. https://doi.org/10.3390/jne6030032

AMA Style

Contreras-Pérez N, Sánchez-Mora H, Quezada-García S, Gómez Torres AM, Cázares Ramírez RI. Validation of the New TLANESY Thermal–Hydraulic Code with Data from the QUENCH-01 Experiment. Journal of Nuclear Engineering. 2025; 6(3):32. https://doi.org/10.3390/jne6030032

Chicago/Turabian Style

Contreras-Pérez, Nahum, Heriberto Sánchez-Mora, Sergio Quezada-García, Armando Miguel Gómez Torres, and Ricardo Isaac Cázares Ramírez. 2025. "Validation of the New TLANESY Thermal–Hydraulic Code with Data from the QUENCH-01 Experiment" Journal of Nuclear Engineering 6, no. 3: 32. https://doi.org/10.3390/jne6030032

APA Style

Contreras-Pérez, N., Sánchez-Mora, H., Quezada-García, S., Gómez Torres, A. M., & Cázares Ramírez, R. I. (2025). Validation of the New TLANESY Thermal–Hydraulic Code with Data from the QUENCH-01 Experiment. Journal of Nuclear Engineering, 6(3), 32. https://doi.org/10.3390/jne6030032

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