This paper focuses on the TRACE code assessment for helium-cooled systems thermal-hydraulic analysis. In the frame of the GoFastR (gas cooled fast reactor) European Collaborative Project, ENEA has offered some selected experimental data for the organization of a benchmark exercise aimed at the validation of the system and CFD codes for the gas reactor transient analyses. One of the Research Center Řež teams participated in it with a CFD code application. Now, the experimental data are used in order to assess the TRACE code for the ongoing high-temperature helium loop (HTHL-2) licensing process. The results of the TRACE calculations agreed very well with the experimental measurements (often within the experimental uncertainties) data provided by the He-FUS3 facility, indicating that the code, despite developed for water coolant applications, if an appropriately tuned input is adopted, it can also be suitable for reasonably accurate gas technology thermo-hydraulic simulations.
Skip Nav Destination
Article navigation
July 2019
Research-Article
Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements
Guido Mazzini,
Guido Mazzini
Centrum Vyzkumu Řež (CVŘ),
Hlavní 130,
Husinec-Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz
Hlavní 130,
Husinec-Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz
1Corresponding author.
Search for other works by this author on:
Miloš Kynčl,
Miloš Kynčl
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Search for other works by this author on:
Marek Ruščák,
Marek Ruščák
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Search for other works by this author on:
Miroslav Hrehor,
Miroslav Hrehor
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Search for other works by this author on:
Alis Musa,
Alis Musa
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Search for other works by this author on:
Antonio Dambrosio,
Antonio Dambrosio
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Search for other works by this author on:
Vincenzo Romanello
Vincenzo Romanello
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Search for other works by this author on:
Guido Mazzini
Centrum Vyzkumu Řež (CVŘ),
Hlavní 130,
Husinec-Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz
Hlavní 130,
Husinec-Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz
Miloš Kynčl
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Marek Ruščák
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Miroslav Hrehor
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Alis Musa
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Antonio Dambrosio
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
Vincenzo Romanello
Centrum Vyzkumu Řež (CVŘ),
Husinec-Řež 250 68, Czech Republic
Hlavní 130
,Husinec-Řež 250 68, Czech Republic
1Corresponding author.
Manuscript received September 13, 2018; final manuscript received March 29, 2019; published online May 10, 2019. Assoc. Editor: Martin Schulc.
ASME J of Nuclear Rad Sci. Jul 2019, 5(3): 030914 (8 pages)
Published Online: May 10, 2019
Article history
Received:
September 13, 2018
Revised:
March 29, 2019
Citation
Mazzini, G., Kynčl, M., Ruščák, M., Hrehor, M., Musa, A., Dambrosio, A., and Romanello, V. (May 10, 2019). "Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements." ASME. ASME J of Nuclear Rad Sci. July 2019; 5(3): 030914. https://doi.org/10.1115/1.4043377
Download citation file:
Get Email Alerts
Cited By
Studies of the Thermalhydraulics Subchannel Code ASSERT-PV 3.2-SC for Supercritical Applications
ASME J of Nuclear Rad Sci
Related Articles
Theoretical, Numerical, and Experimental Study of the Time of Flight Flowmeter
J. Fluids Eng (April,2011)
Thermal Hydraulic Safety Assessment of LLCB Test Blanket System in ITER Using Modified relap/scdapsim/mod4.0 Code
ASME J of Nuclear Rad Sci (April,2018)
Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code
ASME J of Nuclear Rad Sci (April,2021)
Operational Limits for Gas Turbine Compressors During Transient Conditions in a Helium Cooled Reactor
J. Eng. Power (October,1974)
Related Proceedings Papers
Related Chapters
The Special Characteristics of Closed-Cycle Gas Turbines
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Studies Performed
Closed-Cycle Gas Turbines: Operating Experience and Future Potential
Control and Operational Performance
Closed-Cycle Gas Turbines: Operating Experience and Future Potential