Abstract

An ex-core neutron flux measurement is a crucial system for all common power reactors. It is necessary to monitor the neutron flux and control the chain reaction, therefore, the ex-core neutron flux measurement is one of the main safety and control systems. The main advantage of this arrangement of detectors is a fast response to neutron flux change, which determines the reactor power change. Regarding to the new reactor concepts, it is important to deal with improved detection systems suitable for these reactors. Many of the modern reactor concepts are based on a graphite moderator or reflector, which is also the case of the TEPLATOR. The TEPLATOR is a solution of a district heating system based on heavy water as a moderator and graphite as a reflector. The TEPLATOR is designed to use irradiated fuel from the commercial pressurized water reactor or boiling water reactor, which has low to intermediate burnup. This work is focused on the verification of the possible use of the special neutron measuring system placed in the graphite reflector. The Monte Carlo code serpent was used for the calculations performed in this work.

References

1.
Skoda
,
R.
,
Fortova
,
A.
,
Masata
,
D.
,
Zavorka
,
J.
,
Lovecky
,
M.
,
Skarohlid
,
J.
,
Vilimova
,
E.
,
Peltan
,
T.
,
Burian
,
O.
, and
Jirickova
,
J.
,
2020
, “
TEPLATOR: Nuclear District Heating Solution
,”
Proceedings of International Conference Nuclear Energy for New Europe
, Portoroz, Slovenia, Sept. 7–10, pp.
221
228
.http://home.zcu.cz/~masata/NENE2020_408.pdf
2.
Mašata
,
D.
,
Jiřičková
,
J.
, and
Škoda
,
R.
,
2020
, “
TEPLATOR: Basic Economic Study for the Construction and Operation
,”
Proceedings of International Conference Nuclear Energy for New Europe
, Portoroz, Slovenia, Sept. 7–10, pp.
185
191
.http://hdl.handle.net/11025/42636
3.
Skarohlid
,
J.
,
Burian
,
O.
,
Fortova
,
A.
,
Zeman
,
M.
, and
Skoda
,
R.
,
2020
, “
Thermal Energy Storage for TEPLATOR: Technology, Utilisation and Economics
,”
Proceedings of International Conference Nuclear Energy for New Europe
, Portoroz, Slovenia, Sept. 7–10, pp.
192
196
.http://hdl.handle.net/11025/42637
4.
Fortova
,
A.
,
Zeman
,
M.
, and
Jirickova
,
J.
,
2020
, “
TEPLATOR: Residual Heat Dissipation Using Energy Storage
,”
Proceedings of International Conference Nuclear Energy for New Europe
, Portoroz, Slovenia, Sept. 7–10, pp.
248
255
.
5.
Závorka
,
J.
,
Lovecký
,
M.
, and
Škoda
,
R.
,
2020
, “
Basic Design of the TEPLATOR Core—Construction
,”
Proceedings of International Conference Nuclear Energy for New Europe
, Portoroz, Slovenia, Sept. 7–10, pp.
178
184
.http://hdl.handle.net/11025/42635
6.
Wieselquist
,
W. A.
,
Lefebvre
,
L. A.
, and
Jessee
,
M. A.
, eds.,
2020
, “
SCALE Code System
,”
ORNL/TM-2005/39, Version 6.2.4
,
Oak Ridge National Laboratory
,
Oak Ridge, TN
.
7.
Haralampieva
,
T.
,
Spassova
,
V.
,
Georgieva
,
N.
,
Antov
,
A.
,
Stojanova
,
I.
,
Stefanova
,
S.
,
Passage
,
G.
,
Drenska
,
M.
, and
Lassmann
,
K.
,
2002
, “
Management of the Fuel Cycles and Fuel Performance Analyses in the Kozloduy NPP WWER-440 Reactors
,”
Proceedings of a Technical Committee Meeting Held in San Carlos de Bariloche
, International Atomic Energy Agency, Argentina, Paper No. IAEA-TECDOC-1299. https://inis.iaea.org/search/search.aspx?orig_q=RN:33035555
8.
Jutier
,
L.
,
Riffard
,
C.
,
Santamarina
,
A.
,
Guillou
,
E.
,
Grassi
,
G.
,
Lecarpentier
,
D.
,
Lauvaud
,
F.
,
Coulaud
,
A.
,
Hampartzounian
,
M.
,
Tardy
,
M.
, and
Kitsos
,
S.
,
2015
, “
Burnup Credit Implementation for PWR UOX Used Fuel Assemblies in France: From Study to Practical Experience
,”
Nucl. Sci. Eng.
,
181
(
2
), pp.
105
136
.10.13182/NSE14-51
9.
Peltan
,
T.
,
Vilímová
,
E.
, and
Škoda
,
R.
,
2020
, “
Natural Uranium as Alternative Fuel for TEPLATOR
,”
Proceedings of International Conference Nuclear Energy for New Europe
, Portoroz, Slovenia, Sept. 7–10, pp.
205
212
.http://hdl.handle.net/11025/42639
10.
Fořtová
,
A.
,
Závorka
,
J.
, and
Škoda
,
R.
,
2019
, “
Ex-Core Neutron Flux Monitoring System in Graphite Prism for Gen. IV Reactors
,”
Proceedings of 27th International Conference of Nuclear Engineering
, Tsukuba Ibaraki, Japan, May 19–24, Paper No.
ICONE27-1627
.10.1299/jsmeicone.2019.27.1627
11.
Leppänen
,
J.
,
Pusa
,
M.
,
Viitanen
,
T.
,
Valtavirta
,
V.
, and
Kaltiaisenaho
,
T.
,
2015
, “
The Serpent Monte Carlo Code: Status, Development and Applications in 2013
,”
Ann. Nucl. Energy
,
82
, pp.
142
150
.10.1016/j.anucene.2014.08.024
12.
Zeman
,
M.
,
Fortova
,
A.
, and
Skoda
,
R.
,
2020
, “
TEPLATOR DEMO: Basic Design of the Primary Circuit
,”
Proceedings of International Conference Nuclear Energy for New Europe
, Portoroz, Slovenia, Sept. 7–10, pp.
170
177
.https://arhiv.djs.si/proc/nene2020/pdf/NENE2020_0401.pdf
13.
Brown
,
D. A.
,
Chadwick
,
M. B.
,
Capote
,
R.
,
Kahler
,
A. C.
,
Trkov
,
A.
,
Herman
,
M. W.
,
Sonzogni
,
A. A.
,
Danon
,
Y.
,
Carlson
,
A. D.
,
Dunn
,
M.
,
Smith
,
D. L.
,
Hale
,
G. M.
,
Arbanas
,
G.
,
Arcilla
,
R.
,
Bates
,
C. R.
,
Beck
,
B.
,
Becker
,
B.
,
Brown
,
F.
,
Casperson
,
R. J.
,
Conlin
,
J.
,
Cullen
,
D. E.
,
Descalle
,
M.-A.
,
Firestone
,
R.
,
Gaines
,
T.
,
Guber
,
K. H.
,
Hawari
,
A. I.
,
Holmes
,
J.
,
Johnson
,
T. D.
,
Kawano
,
T.
,
Kiedrowski
,
B. C.
,
Koning
,
A. J.
,
Kopecky
,
S.
,
Leal
,
L.
,
Lestone
,
J. P.
,
Lubitz
,
C.
,
Márquez Damián
,
J. I.
,
Mattoon
,
C. M.
,
McCutchan
,
E. A.
,
Mughabghab
,
S.
,
Navratil
,
P.
,
Neudecker
,
D.
,
Nobre
,
G. P. A.
,
Noguere
,
G.
,
Paris
,
M.
,
Pigni
,
M. T.
,
Plompen
,
A. J.
,
Pritychenko
,
B.
,
Pronyaev
,
V. G.
,
Roubtsov
,
D.
,
Rochman
,
D.
,
Romano
,
P.
,
Schillebeeckx
,
P.
,
Simakov
,
S.
,
Sin
,
M.
,
Sirakov
,
I.
,
Sleaford
,
B.
,
Sobes
,
V.
,
Soukhovitskii
,
E. S.
,
Stetcu
,
I.
,
Talou
,
P.
,
Thompson
,
I.
,
van der Marck
,
S.
,
Welser-Sherrill
,
L.
,
Wiarda
,
D.
,
White
,
M.
,
Wormald
,
J. L.
,
Wright
,
R. Q.
,
Zerkle
,
M.
,
Žerovnik
,
G.
, and
Zhu
,
Y.
,
2018
, “
ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library With CIELO-Project Cross Sections, New Standards and Thermal Scattering Data
,”
Nucl. Data Sheets
,
148
, pp.
1
142
.10.1016/j.nds.2018.02.001
14.
Farkas
,
G.
, and
Slugeň
,
V.
,
2006
, “
Modelling of the WWER-440 Reactor for Determination of the Spatial Weight Function of Ex-Core Detectors Using MCNP-4C2 Code
,”
Proceedings of the 16 Symposium of Atomic Energy Research
, Kiadja and KFKI Atomenergia Kutatointezet, Hungary, p.
753
.https://inis.iaea.org/collection/NCLCollectionStore/_Public/38/071/38071923.pdf
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