Abstract

In the framework of the Horizon 2020 project ESFR-SMART (2017-2021), the European Sodium Fast Reactor (ESFR) core was updated through a safety-related modification and optimization of the core design from the earlier FP7 CP-ESFR project (2009-2013). This study is dedicated to neutronic analyses of the improved ESFR core design. The conducted work is reported in two parts. Part I deals with the evaluation of the safety-related neutronic parameters of the fresh Beginning-of-Life (BOL) core carried out by 8 organizations using both continuous energy Monte Carlo and deterministic computer codes. In addition to the neutronics characterization of the core, a special emphasis was put on the calibration and verification of the computational tools involved in the analyses. Part II is devoted to once-through and realistic batch-wise burnup calculations aiming at the establishing of the equilibrium core state, which will later serve as a basis for detailed safety analyses.

References

1.
Mikityuk
,
K.
,
Girardi
,
E.
,
Krepel
,
J.
,
Bubelis
,
E.
,
Fridman
,
E.
,
Rineiski
,
A.
,
Girault
,
N.
,
Payot
,
F.
,
Buligins
,
L.
,
Gerbeth
,
G.
,
Chauvin
,
N.
,
Latge
,
C.
, and
Garnier
,
J.-C.
,
2017
, “
ESFR-SMART: New Horizon-2020 Project on SFR Safety
,”
Proc. IAEA FR2017
, Ekaterinburg, Russian Federation.https://www.researchgate.net/publication/315381003_ESFR-SMART_new_Horizon-2020_project_on_SFR_safety
2.
Fiorini
,
G. L.
, and
Vasile
,
A.
,
2011
, “
European Commission – 7th Framework Programme: The Collaborative Project on European Sodium Fast Reactor (CP ESFR)
,”
Nucl. Eng. Des.
,
241
(
9
), pp.
3461
3469
.10.1016/j.nucengdes.2011.01.052
3.
Rineiski
,
A.
,
Meriot
,
C.
,
Marchetti
,
M.
,
Krepel
,
J.
,
Tsige-Tamirat
,
H.
,
Alvarez
,
F.
,
Girardi
,
E.
, and
Mikityuk
,
K.
,
2020
, “
ESFR-SMART Core Safety Measures and Their Preliminary Assessment
,”
ASME J. Nucl. Eng. Radiat. Sci.
, ePub.
4.
Rineiski
,
A.
,
Meriot
,
C.
,
Marchetti
,
M.
, and
Krepel
,
J.
,
2018
, “
Core Safety Measures in ESFR-SMART
,”
Proc. PHYSOR 2018
, Cancun, Mexico, Apr. 22–26.https://inis.iaea.org/search/search.aspx?orig_q=RN:50009248
5.
Fridman
,
E.
,
Álvarez Velarde
,
F.
,
Romojaro Otero
,
P.
,
Tsige-Tamirat
,
H.
,
Jiménez-Carrascosa
,
A.
,
Garcia Herranz
,
N.
,
Bernard
,
F.
,
Gregg
,
R.
,
Davies
,
U.
,
Krepel
,
J.
,
Lindley
,
B.
,
Massara
,
S.
,
Poumerouly
,
S.
,
Girardi
,
E.
, and
Mikityuk
,
K.
,
2020
, “
Neutronic Analysis of the European Sodium Fast Reactor: Part II - Burnup Analysis
,”
ASME J. Nucl. Eng. Radiat. Sci.
, ePub.10.1115/1.4048765
6.
Koning
,
A. J.
,
Avrigeanu
,
M.
,
Avrigeanu
,
V.
,
Batistoni
,
P.
,
Bauge
,
E.
,
,
M.-M.
,
Bem
,
P.
,
Bernard
,
D.
,
Bersillon
,
O.
,
Bidaud
,
A.
,
Bouland
,
O.
,
Courcelle
,
A.
,
Dean
,
C. J.
,
Dos-Santos-Uzarralde
,
P.
,
Duchemin
,
B.
,
Duhamel
,
I.
,
Duijvestijn
,
M. C.
,
Dupont
,
E.
,
Fischer
,
U.
, and
Forrest
,
R. A.
,
2007
, “
The JEFF Evaluated Nuclear Data Project
,”
Proc. ND 2007
, Nice, France.10.1051/ndata:07476
7.
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
8.
Pelowitz
,
D. B.
,
2014
, MCNP6 User's Manual, Code version 6.1.1beta, Los Alamos, NM, Report No.
LA-CP-14-00745
.https://www.researchgate.net/publication/275354611_MCNP6TM_User's_Manual_Code_Version_611_Beta
9.
Goorley
,
J. T.
,
James
,
M. R.
,
Booth
,
T. E.
, Brown, F.,
Bull
,
J. S.
,
Cox
,
L. J.
,
Durkee
,
J. W.
, Jr.
Elson
,
J. S.
,
Fensin
,
M. L.
,
Forster
,
R. A. I.
,
Hendricks
,
J. S.
,
Hughes
,
H. G. I.
,
Johns
,
R. C.
,
Kiedrowski
,
B. C.
,
Martz
,
R. L.
,
Mashnik
,
S. G.
,
McKinney
,
G. W.
,
Pelowitz
,
D. B.
,
Prael
,
R. E.
,
Sweezy
,
J. E.
,
Waters
,
L. S.
,
Wilcox
,
T.
, and
Zukaitis
,
A. J.
,
2013
, Initial MCNP6 Release Overview - MCNP6 version 1.0, Los Alamos, NM.
10.
Cochet
,
B.
,
Jinaphanh
,
A.
,
Heulers
,
L.
, and
Jacquet
,
O.
,
2015
, “
Capabilities Overview of the MORET 5 Monte Carlo Code
,”
Ann. Nucl. Energy
,
82
, pp.
74
84
.10.1016/j.anucene.2014.08.022
11.
Rearden
,
B. T.
, and
Jessee
,
M. A.
,
2017
, SCALE Code System, 1800553684, Oak Ridge National Laboratory, Oak Ridge, TN, Report No. ORNL/TM-2005/39.
12.
Lindley
,
B.
,
Hosking
,
G.
,
Smith
,
P.
,
Powney
,
D.
,
Tollit
,
B.
,
Fry
,
T.
,
Perry
,
R.
,
Ware
,
T.
,
Murphy
,
C.
,
Grove
,
C.
,
Thomas
,
M.
,
Hesketh
,
K.
, and
Kotlyar
,
D.
,
2017
, “
Developments Within the WIMS Reactor Physics Code for Whole Core Calculations
,”
Proc. M&C 2017
, Jeju, South Korea, Apr. 16–20.https://www.semanticscholar.org/paper/Developments-within-the-WIMS-Reactor-Physics-Code-Lindley-Hosking/cc35f134ae5677daf81117c7d6cf3941d9af4534
13.
Ruggieri
,
J. M.
,
Tommasi
,
J.
,
Lebrat
,
J. F.
,
Suteau
,
C.
,
Plisson-Rieunier
,
D.
,
De Saint Jean
,
C.
,
Rimpault
,
G.
, and
Sublet
,
J. C.
,
2006
, “
ERANOS 2.1: International Code System for GEN IV Fast Reactor Analysis
,”
Proc. ICAPP 2006
, Reno, NV.https://www.researchgate.net/publication/236539019_ERANOS_21_International_Code_System_for_GEN_IV_Fast_Reactor_Analysis
14.
Kavenoky
,
A.
,
1978
, “
The SPH Homogenization Method
,”
Proc. A Specialists' Meeting on Homogenization Methods in Reactor Physics, IAEA-TECDOC-231
, Lugano, Switzerland, Nov. 13–15.https://inis.iaea.org/search/search.aspx?orig_q=RN:12619327
15.
Krepel
,
J.
,
Pelloni
,
S.
,
Bortot
,
S.
,
Panadero
,
A. L.
, and
Mikityuk
,
K.
,
2015
, “
Mapping of sodium void worth and doppler effect for sodium-cooled fast reactor - 15458
,”
Proc. ICAPP 2015
, Nice, France, May 3–6.https://inis.iaea.org/search/search.aspx?orig_q=RN:49004849
16.
Rineiski
,
A.
,
Meriot
,
C.
,
Coquelet-Pascal
,
C.
,
Krepel
,
J.
, and
Fridman
,
E.
,
2018
, “
Specification of the New Core Safety Measures, H2020 ESFR-SMART
,” Project Deliverable D1.1.2(D1.2).https://www.researchgate.net/publication/315381003_ESFR-SMART_new_Horizon-2020_project_on_SFR_safety
17.
MacFarlane
,
R. E.
, and
Kahler
,
A. C.
,
2010
, “
Methods for Processing ENDF/B-VII With NJOY
,”
Nucl. Data Sheets
,
111
(
12
), pp.
2739
2890
.10.1016/j.nds.2010.11.001
18.
Wiarda
,
D.
,
Dunn
,
M. E.
,
Green
,
N. M.
,
Williams
,
M. L.
,
Celik
,
C.
, and
Petrie
,
L. M.
,
2016
, AMPX-6: A Modular Code System for Processing ENDF/B evaluations, Oak Ridge, TN, Report No.
ORNL/TM-2016/43
.https://www.ornl.gov/sites/default/files/AMPX-6.pdf
19.
Jiménez-Carrascosa
,
A.
,
Fridman
,
E.
,
García-Herranz
,
N.
,
Alvarez-Velarde
,
F.
,
Romojaro
,
P.
, and
Bostelmann
,
F.
,
2019
, “
About the Impact of the Unresolved Resonance Region in Monte Carlo Simulations of Sodium Fast Reactors
,”
Proc. ICAPP 2019
, Nice, France, May 12–15.10.5281/zenodo.3324476
You do not currently have access to this content.