@article{MTMT:34735228, title = {Discussion and perspectives for improvements of heat transfer correlation capabilities for fluids at supercritical pressures}, url = {https://m2.mtmt.hu/api/publication/34735228}, author = {Varju, Tamás and Csige, András and Kiss, Attila and Filonov, V. and Filonova, Y. and Fedorov, D. and Pucciarelli, A. and Kassem, S. and Ambrosini, W.}, doi = {10.1016/j.nucengdes.2024.113085}, journal-iso = {NUCL ENG DES}, journal = {NUCLEAR ENGINEERING AND DESIGN}, volume = {421}, unique-id = {34735228}, issn = {0029-5493}, year = {2024}, eissn = {1872-759X}, orcid-numbers = {Varju, Tamás/0000-0002-2969-1867; Kiss, Attila/0000-0002-8600-2300} } @inbook{MTMT:31818516, title = {TWO CFD BENCHMARKS FOR TUBE AND ANNULUS GEOMETRIES}, url = {https://m2.mtmt.hu/api/publication/31818516}, author = {Kiss, Attila}, booktitle = {Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs)}, unique-id = {31818516}, year = {2020}, pages = {375-399}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} } @inbook{MTMT:31818496, title = {OVERVIEW OF PAST EXPERIMENTAL WORKS ON HEAT TRANSFER OF SCW FLOW IN TUBES}, url = {https://m2.mtmt.hu/api/publication/31818496}, author = {Kiss, Attila}, booktitle = {Understanding and Prediction of Thermohydraulic Phenomena Relevant to Supercritical Water Cooled Reactors (SCWRs)}, unique-id = {31818496}, year = {2020}, pages = {38-43}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} } @article{MTMT:31448845, title = {Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle}, url = {https://m2.mtmt.hu/api/publication/31448845}, author = {Kiss, Attila and Mervay, Bence}, doi = {10.1115/1.4046842}, journal-iso = {J NUCLEAR ENG RAD SCI}, journal = {JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE}, volume = {6}, unique-id = {31448845}, issn = {2332-8983}, abstract = {The application of relatively simple and cheap wrapped wire spacer in the European supercritical water-cooled reactor (SCWR) (high-performance light water reactor (HPLWR)) has been proposed in order to provide enhanced heat transfer in the fuel assembly without unacceptable penalty in pressure loss. The wires cause twisting flow in the fuel assembly, which means the coolant not only flows straight in the axial direction but also has a significant transverse velocity component, and strong mixing between neighboring subchannels occurs. The aim of this ongoing research is to numerically investigate the effect of wrapped wire spacers on thermal hydraulics of the turbulent coolant flow and its heat transfer in a small bundle of four fuel rods. One bare and six-wired geometries with varying wire pitches (1-6 turn(s) of wires) have been studied. It was found that the wires generate significant amount of transverse velocity, decrease the wall temperature, and increase the heat transfer coefficient mostly in corner subchannels which were the hottest in bare geometry. Thus, the presence of wires enhances heat transfer where it is most needed. Temperature hot spots with moderate values have been identified on the cladding wall of fuel rods. Based on the results, a technically optimal choice of number of wire turns from thermal hydraulic sense has been proposed.}, year = {2020}, eissn = {2332-8975}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} } @article{MTMT:31448267, title = {About the Thermal Hydraulic Analysis Part of a Coupled Study on a Thorium-Fueled SCWR Concept}, url = {https://m2.mtmt.hu/api/publication/31448267}, author = {Kiss, Attila and Hegyesi, Bela and Ujváry, Patrik Richárd and Ványi, András Szabolcs and Csom, Gyula}, doi = {10.1115/1.4046904}, journal-iso = {J NUCLEAR ENG RAD SCI}, journal = {JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE}, volume = {6}, unique-id = {31448267}, issn = {2332-8983}, abstract = {Inherently poorer moderation in supercritical water-cooled reactors (SCWRs) due to average density lower than in light water reactors and the resulted spectral shift can be useful when we apply thorium fuel-cycle instead of uranium-plutonium one, according to an ongoing study in Budapest University of Technology and Economics (BME) Institute of Nuclear Techniques (NTI). Upon this conclusion, a thorium-fueled SCWR design (Th-SCWR) has been proposed by BME NTI. In the current feasibility study phase, detailed three-dimensional (3D) computational fluid dynamics (CFD) calculations with novel neutronics analysis were coupled and conducted separately. Neutronics calculations provided the distribution of heat source, while the CFD analysis gave back axial distribution of coolant density (this iteration was repeated until an acceptable convergence). This paper presents the CFD analysis on thermal hydraulics of the initial design (two CFD models without any spacer device and one model with wrapped wire spacer) of Th-SCWR fuel assembly. As results of the preliminary design of Th-SCWR cladding wall, coolant and fuel temperatures have been determined; the flow field with and without spacer device has been showed, and the application of wrapped wire spacer has been proposed.}, year = {2020}, eissn = {2332-8975}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} } @article{MTMT:30511130, title = {Numerical analysis on the thermal hydraulic effect of wrapped wire spacer in a four rod fuel bundle}, url = {https://m2.mtmt.hu/api/publication/30511130}, author = {Kiss, Attila and Mervay, Bence}, doi = {10.1016/j.nucengdes.2018.11.024}, journal-iso = {NUCL ENG DES}, journal = {NUCLEAR ENGINEERING AND DESIGN}, volume = {342}, unique-id = {30511130}, issn = {0029-5493}, abstract = {The application of relatively simple and cheap wrapped wire spacer in the European supercritical-water-cooled reactor has been proposed in order to provide enhanced heat transfer in the fuel assembly without unacceptable penalty in pressure loss. The wires cause twisting flow in fuel assembly, which means the coolant flows not only straight in the axial direction but has a significant transverse velocity component and strong mixing between neighbouring sub-channels occurs. The aim of this ongoing research is to numerically investigate the effect of wrapped wire spacers on thermal hydraulics of turbulent coolant flow and its heat transfer in a small bundle with four fuel rods. One bare and six wired geometry with different wire pitches (1-6 turn(s) of wires) have been studied. Unstructured volume mesh of tetrahedral elements with fine near wall boundary mesh of prism elements for fluid domain and structured mesh of hexahedral elements for solid domains of fuel rods, wires, etc. have been used to discretize the computational domain. After an extensive mesh and turbulence model sensitivity study, the M4 mesh resolution and the most advanced BSL Reynolds Stress turbulence model were selected for the further CFD calculations. The validation of the model with 3 turns of wires has been performed. The wires generate significant amount of transverse velocity and decrease the wall temperature most in corner subchannels which was hottest in bare geometry. The heat transfer coefficient has been increased also most in corner sub-channels by 60-145% depending on the number of turns of wires. The other two types of sub-channel showed moderated (wall type) or negligible (central type) decrease in wall temperature and enhancement in heat transfer. Temperature hot spots with moderate values have been identified on the wall of fuel rods. The optimal technical choice from thermal hydraulic sense seems to be three turns of wires due to the pressure drop is only 18% higher than in bare geometry but maximum wall temperature is 32 degrees C lower while the average heat transfer coefficient is 95% higher where it is most needed, in the corner sub-channels. For these thermal benefits, the 18% penalty in the pressure drop seems to be acceptable. The outcome of this technical optimization needs further confirmation by an economic analysis while the possible long term effect of revealed hot spots on integrity of fuel rod cladding has to be investigated as well.}, keywords = {CFD ANALYSIS; SCWR (HPLWR); Thermal hydraulics of supercritical water; Wrapped wire spacer; Wire effect}, year = {2019}, eissn = {1872-759X}, pages = {276-307}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} } @mastersthesis{MTMT:31347384, title = {Thermal hydraulic investigations of the coolant flow in Supercritical Water-cooled Reactor relevant geometries}, url = {https://m2.mtmt.hu/api/publication/31347384}, author = {Kiss, Attila}, publisher = {Budapest University of Technology and Economics}, unique-id = {31347384}, year = {2018}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} } @article{MTMT:3332032, title = {Summary on the Results of Two Computational Fluid Dynamic Benchmarks of Tube and Different Channel Geometries}, url = {https://m2.mtmt.hu/api/publication/3332032}, author = {Kiss, Attila and Churkin, A and Pilkhwal, DS and Vaidya, AM and Ambrosini, W and Pucciarelli, A and Podila, K and Rao, YF and Leung, L and Chen, YZ and Anderson, M and Zhao, M}, doi = {10.1115/1.4038162}, journal-iso = {J NUCLEAR ENG RAD SCI}, journal = {JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE}, volume = {4}, unique-id = {3332032}, issn = {2332-8983}, year = {2018}, eissn = {2332-8975}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} } @inproceedings{MTMT:3337182, title = {Two CFD benchmarks on SCWR related tube and different channel geometries}, url = {https://m2.mtmt.hu/api/publication/3337182}, author = {Kiss, Attila and Andrey, Churkin and Alexey, Krutikov and Luka, Golibrodo and Vasilii, Volkov and Darwan, S Pilkhwal and Abhijeet, M Vaidya and Walter, Ambrosini and Andrea, Pucciarelli and Krishna, Podila and Yanfei, Rao and Laurence, Leung and Chen, Yuzhou and Mark, Anderson and Meng, Zhao}, booktitle = {Proceedings of the twenty-seventh Symposium of AER}, unique-id = {3337182}, year = {2017}, pages = {993-1024}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} } @misc{MTMT:3252895, title = {Study on the thermal hydraulics of supercritical water under natural circulation flowing in a closed loop}, url = {https://m2.mtmt.hu/api/publication/3252895}, author = {Kiss, Attila and Balaskó, Márton and Horváth, László and Kis, Zoltán and Bartos, Júlia and Aszódi, Attila}, unique-id = {3252895}, year = {2017}, orcid-numbers = {Kiss, Attila/0000-0002-8600-2300} }