Every year, several important international and national conferences and meetings take place. Our scientists, post docs and students are regularly invited to take part, write a conference paper and have presentations.
2024
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Ramos Perez A, Lind T, Petrov V, Manera A, Prasser HM
Aerosol retention measurements with Wire-mesh sensors: an experimental and computational approach
In: SWINTH-2024: Specialist workshop on advanced instrumentation and measurement techniques for nuclear reactor thermal hydraulics and severe accidents. Dresden: K.I.T. Group; 2024:002 (14 pp.).
DORA PSI -
Ramos Perez A, Lind T, Petrov V, Manera A, Prasser H-M
Local measurements on particle mass transfer in gas-liquid flows
In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 11th European review meeting on severe accidents research (ERMSAR2024). Stockholm: Karlsruher Institut für Technologie (KIT); 2024:015 (12 pp.).
DORA PSI
2023
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Ahn T, Petrov V, Manera A
Comparison between high-resolution gamma-ray tomography and wire-mesh sensor for air-water flow in a rod bundle geometry
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2196-2209. https://doi.org/10.13182/NURETH20-40846
DORA PSI -
Grasso M, Petrov V, Manera A, Rivera Y
Experimental velocity profile reconstruction in thin water films
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). ; 2023:1516-1529. https://doi.org/10.13182/NURETH20-40771
DORA PSI -
Huang P-H, Ahn T, Manera A, Petrov V
Experimental study on the start-up characteristics and performance of a ten sodium heat pipe bundle array
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3479-3492. https://doi.org/10.13182/NURETH20-40775
DORA PSI -
Mao J, Petrov V, Manera A
High-resolution experiments for mixing in large enclosures
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2152-2165. https://doi.org/10.13182/NURETH20-40559
DORA PSI -
Petrov V, Ding Y
Passive temperature-sensitive flow-controlling device based on bimetallic membrane deflection, FEM, and CFD feasibility study
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3690-3700. https://doi.org/10.13182/NURETH20-40808
DORA PSI -
Ramos Perez A, Lind T, Manera A, Petrov V, Prasser H-M
Measurement of aerosol mass transfer and hydrodynamics in a bubble column using Wire-Mesh sensors
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2402-2415. https://doi.org/10.13182/NURETH20-40223
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Rivera Y, Matteo G, Petrov V, Manera A
Three-dimensional multiphase CFD simulation of a thin liquid film flowing down an inclined plate
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:874-885. https://doi.org/10.13182/NURETH20-40779
DORA PSI -
Valori V, Qin S, Petrov V, Manera A
High-fidelity experiments of turbulent buoyant jets from simultaneous particle image velocimetry and laser induced fluorescence
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:2430-2443. https://doi.org/10.13182/NURETH20-41310
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Welker Z, Manera A, Petrov V, Balestra P
The effects of depressurizing into a cavity for small and medium sized break air ingress accident scenarios
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). Illinois: American Nuclear Society; 2023:3440-3453. https://doi.org/10.13182/NURETH20-40616
DORA PSI -
Welker Z, Manera A, Petrov V, Balestra P
The refractive index matched pebble bed facility for high resolution experiments of DLOFC and PLOFC accidents in MPBRs
In: 20th international topical meeting on nuclear reactor thermal hydraulics (NURETH-20). ; 2023:3252-3260. https://doi.org/10.13182/NURETH20-40614
DORA PSI
2022
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Ahn T, Huang P-H, Diaz J, Manera A, Petrov V
Experimental study on start-up characteristics of a sodium-filled heat pipe, using in-house high-resolution and high-speed radiation-based imaging system
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35742 (15 pp.).
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Che S, Mao J, Sun X, Manera A, Petrov V
Design of high-resolution experiments for extended LOFC accidents HTGRS
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35301 (16 pp.).
DORA PSI -
Diaz J, Serrano-Aguilera JJ, Petrov V, Manera A
Dynamic bias error arising from two-phase flow measurements performed with radiation transmission
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:37372 (16 pp.).
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Diaz J, Liu Q, Petrov V, Manera A, Sun X
High-resolution X-ray radiography methods developed for post-chf experiment
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35375 (16 pp.).
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Diaz J, Ahn T, Adams R, Petrov V, Manera A
High-resolution tomographic measurements of adiabatic rod bundle
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35374 (17 pp.).
DORA PSI -
Huang PH, Ahn T, Manera A, Petrov V
The effect of cooling efficiency on the startup characteristic and performance of the sodium heat pipes for the special purpose reactor with different filling ratio
In: Proceedings of advances in thermal hydraulics (ATH 2022) - Embedded with the 2022 ANS annual meeting. American Nuclear Society (ANS); 2022:120-132. https://doi.org/10.13182/T126-38145
DORA PSI -
Huxford A, Petrov V, Manera A, Grunloh T
A spectral shift closure model for use in proper orthogonal decomposition-based reduced order models
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35387 (9 pp.).
DORA PSI -
Huxford A, Coppo Leite V, Merzari E, Zou L, Petrov V, Manera A
Development of innovative overlapping-domain coupling between SAM and NekRS
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35819 (15 pp.).
DORA PSI -
Lind T, Kalilainen J, Nichenko S
MSR simulation with cGEMS: salt and fission product evaporation
In: Gabrielli F, Herranz LE, Paci S, eds. Proceedings of the 10th European review meeting on severe accidents research (ERMSAR2022). Severe accident research eleven years after the Fukushima accident. Karlsruhe: Karlsruher Institut für Technologie (KIT); 2022:272 (12 pp.).
DORA PSI -
Mao J, Petrov V, Manera A
High-resolution experiments on flow mixing in the scaled-down upper plenum of high-temperature gas-cooled reactors under accident scenario
In: Proceedings of advances in thermal hydraulics (ATH 2022) - Embedded with the 2022 ANS annual meeting. sine loco: American Nuclear Society (ANS); 2022:374-387. https://doi.org/10.13182/T126-37683
DORA PSI -
Mao J, Petrov V, Manera A, Howard T, Cetiner SM
On the development of a novel acoustic flow meter for high-temperature gas-cooled reactors
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35300 (14 pp.).
DORA PSI -
Mao J, Welker Z, Nunez D, Petrov V, Manera A
Validation of rans-based turbulence models against high-resolutional experimental data for buoyancy-driven flow with stratified fronts
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35611 (16 pp.).
DORA PSI -
Welker Z, Balestra P, Manera A, Petrov V
Oxygen ingress measurements of a scales HTGR facility for small and medium break size DLOFC and air ingress accident scenarios
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35717 (12 pp.).
DORA PSI -
Welker Z, Balestra P, Manera A, Petrov V
PIV measurements of a depressurizing jet to study helium-air mixing during HTGR depressurization accidents
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35718 (15 pp.).
DORA PSI -
Yeo D, Petrov V, Manera A
Application of machine learning for online discovery of component degradation dynamics
In: 19th international topical meeting on nuclear reactor thermal hydraulics (NURETH-19). Illinois: American Nuclear Society; 2022:35385 (16 pp).
DORA PSI -
Yeo D, Petrov V, Manera A
Development of the methodology for degradation emulation of primary salt pump in high-temperature fluoride salt test facility
In: Transactions of the American nuclear society. ANS winter meeting and technology expo 2022. Vol. 127. Transactions of the American Nuclear Society. American Nuclear Society; 2022:268-271. https://doi.org/10.13182/T127-39667
DORA PSI