The aim of the supercritical water reactor-fuel qualification test (SCWR-FQT) Euratom-China collaborative project is to design an experimental facility for qualification of fuel for the supercritical water-cooled reactor. The facility is intended to be operated in the LVR-15 research reactor in the Czech Republic. The pressure tube of the FQT facility encloses four fuel rods that will operate in similar conditions to the evaporator of the HPLWR reactor. This article deals with the three-dimensional (3D) coupled neutronic-thermohydraulic steady-state and transient analysis of LVR-15 with the fueled loop. Conservatively calculated enveloping parameters (e.g., reactivity coefficients) were determined for the safety analysis. The control rod withdrawal analysis of the FQT facility with and without reactor SCRAM was carried out with the KIKO3D-ATHLET-coupled dynamic code.

References

References
1.
Ruzickova
,
M.
,
Schulenberg
,
T.
,
Visser
,
D. C.
,
Novotny
,
R.
,
Kiss
,
A.
,
Maraczy
,
C.
, and
Toivonen
,
A.
,
2014
, “
Overview and Progress in the European Project: “Supercritical Water Reactor—Fuel Qualification Test”
,”
Prog. Nucl. Energy
,
77
, pp. 
381
389
.10.1016/j.pnucene.2014.01.011
2.
Ruzickova
,
M.
,
Vojacek
,
A.
,
Schulenberg
,
T.
,
Visser
,
D. C.
,
Novotny
,
R.
,
Kiss
,
A.
,
Maraczy
,
C.
, and
Toivonen
,
A.
,
2015
, “
European Project Supercritical Water Reactor—Fuel Qualification Test (SCWR-FQT): Overview, Results, Lessons Learnt and Future Outlook
,”
Proceedings of the 7th International Symposium on Supercritical Water-Cooled Reactors (ISSCWR-7)
,
VTT Technical Research Centre of Finland Ltd
,
Helsinki, Finland
, Mar.15–18 Paper No. ISSCWR7-1054.
3.
Keresztúri
,
A.
,
Hegyi
,
Gy.
,
Korpás
,
L.
,
Maráczy
,
Cs.
,
Makai
,
M.
, and
Telbisz
,
M.
,
2010
, “
General Features and Validation of the Recent KARATE-440 Code System
,”
Int. J. Nucl. Energy Sci. Technol.
,
5
(
3
), pp. 
207
238
.10.1504/IJNEST.2010.033476
4.
Hegedűs
,
Cs.
,
Hegyi
,
Gy.
,
Hordósy
,
G.
,
Keresztúri
,
A.
,
Makai
,
M.
,
Maráczy
,
Cs.
,
Telbisz
,
F.
,
Temesvári
,
E.
, and
Vértes
,
P.
,
2002
, “
The KARATE Program System
,”
Proceedings of the PHYSOR 2002
,
Seoul, Korea
, Oct. 7–10,
American Nuclear Society, Inc.
,
La Grange Park, IL
.
5.
Maráczy
,
Cs.
,
Hegyi
,
Gy.
,
Trosztel
,
I.
,
Hordósy
,
G.
, and
Brolly
,
A.
,
2014
, “
RIA Analysis of the SCWR-FQT Facility in the LVR-15 Research Reactor
,”
The 19th Pacific Basin Nuclear Conference
,
Vancouver, Canada
, Aug. 24–28,
Canadian Nuclear Society
,
Ottawa, ON
.
6.
Keresztúri
,
A.
,
Hegyi
,
Gy.
,
Maráczy
,
Cs.
,
Panka
,
I.
,
Telbisz
,
M.
,
Trosztel
,
I.
, and
Hegedűs
,
Cs.
,
2003
, “
Development and Validation of the Three-Dimensional Dynamic Code—KIKO3D
,”
Ann. Nucl. Energy
,
30
(
1
), pp.
93
120
. 0306-454910.1016/S0306-4549(02)00043-9
7.
Maráczy
,
Cs.
,
Keresztúri
,
A.
,
Trosztel
,
I.
, and
Hegyi
,
Gy.
,
2010
, “
Safety Analysis of Reactivity Initiated Accidents in a HPLWR Reactor by the Coupled ATHLET-KIKO3D Code
,”
Prog. Nucl. Energy
,
52
(
2
), pp.
190
196
. 10.1016/j.pnucene.2009.06.005
8.
Keresztúri
,
A.
,
Maráczy
,
Cs.
,
Hegyi
,
Gy.
,
Trosztel
,
I.
, and
Pataki
,
I.
,
2008
, “
Safety Analysis of Reactivity Initiated Accidents (RIA) and Anticipated Transients Without SCRAM (ATWS) of the Budapest Research Reactor
,”
RRFM 2008 Transactions
,
Hamburg, Germany
, Mar. 2–5,
European Nuclear Society
,
Brussels, Belgium
, pp.
122
132
.
You do not currently have access to this content.