0
Special Section on Research Center Řež: Nuclear-Engineering Activities in 2018

Assessment of the TRACE Code for the He-Cooled Systems Simulation Capability Against Some He-FUS3 Experimental Measurements

[+] Author and Article Information
Guido Mazzini

Centrum Vyzkumu Řež (CVŘ),
Hlavní 130,
Husinec-Řež 250 68, Czech Republic
e-mail: guido.mazzini@cvrez.cz

Miloš Kynčl, Marek Ruščák, Miroslav Hrehor, Alis Musa, Antonio Dambrosio, Vincenzo Romanello

Centrum Vyzkumu Řež (CVŘ),
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 5(3), 030914 (May 10, 2019) (8 pages) Paper No: NERS-18-1085; doi: 10.1115/1.4043377 History: Received September 13, 2018; Revised March 29, 2019

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.

FIGURES IN THIS ARTICLE
<>
Copyright © 2019 by ASME
Your Session has timed out. Please sign back in to continue.

References

Berka, J. , Hlinčík, T. , Víden, I. , Hudský, T. , and Vít, J. , 2015, “ The Design and Utilization of a High-Temperature Helium Loop and Other Facilities for the Study of Advanced Gas-Cooled Reactors in the Czech Republic,” Prog. Nucl. Energy, 85, pp. 156–163. [CrossRef]
Mikula, P. , and Kysela, J. , 1997, “ Řež's Medium Power Research Reactor LVR-15 Opened for External Users,” Phys. B, 241–243, pp. 39–41. [CrossRef]
Dambrosio, A. , Ruščák, M. , Mazzini, G. , and Musa, A. , 2018, “ Neutronic Analysis of the LVR-15 Research Reactor Using the PARCS Code,” Ann. Nucl. Energy, 117, pp. 145–154. [CrossRef]
U.S. Nuclear Regulatory Commission, 2013, “TRACE V5.840. Theory Manual. Field Equations, Solution Methods and Physical Model,” U.S. Nuclear Regulatory Commission, Division of Risk Assessment and Special Projects, Washington, DC.
U.S. Nuclear Regulatory Commission, 2014, “TRACE V5.840 User's Manual, Volume 1: Input Specification,” U.S. Nuclear Regulatory Commission, Division of Risk Assessment and Special Projects, Washington, DC.
U.S. Nuclear Regulatory Commission, 2014, “TRACE V5.840 User's Manual, Volume 2: Modeling Guidelines,” U.S. Nuclear Regulatory Commission, Division of Risk Assessment and Special Projects, Washington, DC.
Polidori, M. , 2011, “ He-FUS3 Benchmark Specifications, GoFastR-DEL-1.5-01, Rev. 0,” ENEA, Brasimone, Italy.
Meloni, P. , and Polidori, M. , 2009, “ HE-FUS3 Experimental Campaign for the Assessment of Thermal-Hydraulic Codes: Post-Test Analysis,” Brasimone, Italy, Report No. RSE/2009/89.
Polidori, M. , 2012, “ He-FUS3 Benchmark Results,” Brasimone, Italy, Report No. 10840/4341.
Barone, G. , Coscarelli, E. , Forgione, N. , Martelli, D. , Del Nevo, A. , Tarantino, M. , Utili, M. , Ricapito, I. , and Calderoni, P. , 2015, “ Development of a Model for the Thermal-Hydraulic Characterization of the He-FUS3 Loop,” Fusion Eng. Des., 96–97, pp. 212–216. [CrossRef]
Geffraye, G. , Kalitvianski, V. , Maas, L. , Meloni, P. , Polidori, M. , Tauveron, N. , and Cochemé, F. , 2012, “ CATHARE 2 Code Validation on HE-FUS3 Loop,” Nucl. Eng. Des., 249, pp. 237–247. [CrossRef]
Sallus, L. , and Van Hove, W. , 2008, “ MELCOR Code Validation on HE-FUS3 Loop,” ASME Paper No. HTR2008-58258.
EUROfusion, 2018, “ European Consortium for the Development of Fusion Energy,” EUROfusion, Garching, Germany, accessed Aug, 20, 2009, https://www.euro-fusion.org/
Porfiri, M. T. , and Mazzini, G. , 2018, “ DEMO BB Safety Data List (SDL),” Version 4.1, Roma, Italy, Report No. 2MF8KU.
ITER, 2018, “ITER Organization,” ITER, Cadarache, France, accessed Apr. 3, 2019, https://www.iter.org/.
Hernandez, F. A. , Arbeiter, F. , Boccaccini, L. V. , Bubelis, E. , Chakin, V. P. , Cristescu, I. , Ghidersa, B. E. , Gonzalez, M. , Hering, W. , Hernandez, T. , Jin, X. Z. , Kamlah, M. , Kiss, B. , Knitter, R. , Kolb, M. H. H. , Kurinskiy, P. , Leys, O. , Maione, I. A. , Moscardini, M. , Nadasi, G. , Neuberger, H. , Pereslavtsev, P. , Pupeschi, S. , Rolli, R. , Ruck, S. , Spagnuolo, G. A. , Vladimirov, P. V. , Zeile, C. , and Zhou, G. , 2018, “ Overview of the HCPB Research Activities in EUROfusion,” IEEE Trans. Plasma Sci., 46(6), pp. 2247–2261. [CrossRef]
Francisco, A. H. , Gonzalez, Q. K. B. , Kiss, H. , Neuberger, G. N. , Pavel, P. , and Christian, Z. , 2016, “ Integration for HCPB/DDD 2015 for HCPB,” Version 1.1, Karlsruhe, Germany, Report No. 2MRQ4E.

Figures

Grahic Jump Location
Fig. 1

He-FUS3 facility configuration [7]

Grahic Jump Location
Fig. 2

He-FUS3 piping layout 3D sketch (with height values (m), in black, and length values (m), in red in the online version) [7]

Grahic Jump Location
Fig. 3

He-FUS3 nodalization scheme—scheme 1

Grahic Jump Location
Fig. 4

He-FUS3 nodalization—scheme 2

Grahic Jump Location
Fig. 5

He-FUS3 nodalization—scheme 3

Grahic Jump Location
Fig. 6

TRACE He-FUS3 thermo-hydraulic model verification—economizer; hot side; Calc #1_2

Grahic Jump Location
Fig. 7

TRACE HE-FUS3 thermal-hydraulic model verification—economizer; cold side; Calc #1_2

Tables

Errata

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related Journal Articles
Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In