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.

References

1.
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
.
2.
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
.
3.
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
.
4.
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
.
5.
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
.
6.
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
.
7.
Polidori
,
M.
,
2011
, “
He-FUS3 Benchmark Specifications, GoFastR-DEL-1.5-01, Rev. 0
,” ENEA, Brasimone, Italy.
8.
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.
9.
Polidori
,
M.
,
2012
, “
He-FUS3 Benchmark Results
,” Brasimone, Italy, Report No. 10840/4341.
10.
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
.
11.
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
.
12.
Sallus
,
L.
, and
Van Hove
,
W.
,
2008
, “
MELCOR Code Validation on HE-FUS3 Loop
,”
ASME
Paper No. HTR2008-58258.
13.
EUROfusion
,
2018
, “
European Consortium for the Development of Fusion Energy
,” EUROfusion, Garching, Germany, accessed Aug, 20, 2009, https://www.euro-fusion.org/
14.
Porfiri
,
M. T.
, and
Mazzini
,
G.
, 2018, “
DEMO BB Safety Data List (SDL)
,” Version 4.1, Roma, Italy, Report No. 2MF8KU.
15.
ITER
,
2018
, “ITER Organization,”
ITER
, Cadarache, France, accessed Apr. 3, 2019, https://www.iter.org/.
16.
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
.
17.
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.
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