Abstract
Thermal molten salt reactors can be designed in many configurations. This paper investigates the optimal geometry of a one fluid molten salt reactor (OFMSR) in a virtual one-and-half fluid configuration with a fixed fuel salt volume. Two primary configurations were studied, axial blanket (three models) and radial blanket (two models). Neutronic calculations were performed using Monte Carlo N-particle 6.2 (MCNP6.2) and Serpent-2 reactor physics codes with evaluated nuclear data files/B-VII.0 continuous neutron library. The analysis comprises criticality calculation, temperature coefficient of reactivity (TCR), breeding ratio (BR), and kinetic parameters. The results imply a good agreement between MCNP and Serpent calculations. TCR values show a different pattern between axial and radial blanket configuration. While the correlation between TCR and BR is inversely correlated in axial blanket, it is linear in radial blanket configuration. Overall, radial blanket configuration seemed to show better neutronic performance than axial blanket configuration, with comparably strong negative TCR and large BR.
References
1.
Serp
,
J.
,
Allibert
,
M.
,
Beneš
,
O.
,
Delpech
,
S.
,
Feynberg
,
O.
,
Ghetta
,
V.
,
Heuer
,
D.
, et al., 2014
, “
The Molten Salt Reactor (MSR) in Generation IV: Overview and Perspectives
,” Prog. Nucl. Energy
,
77
, pp. 308
–319
.10.1016/j.pnucene.2014.02.0142.
Křepel
,
J.
,
Hombourger
,
B.
,
Fiorina
,
C.
,
Mikityuk
,
K.
,
Rohde
,
U.
,
Kliem
,
S.
, and
Pautz
,
A.
, 2014
, “
Fuel Cycle Advantages and Dynamics Features of Liquid Fueled MSR
,” Ann. Nucl. Energy
,
64
, pp. 380
–397
.10.1016/j.anucene.2013.08.0073.
Hombourger
,
B.
,
Křepel
,
J.
, and
Pautz
,
A.
, 2020
, “
The EQL0D Fuel Cycle Procedure and Its Application to the Transition to Equilibrium of Selected Molten Salt Reactor Designs
,” Ann. Nucl. Energy
,
144
, p. 107504
.10.1016/j.anucene.2020.1075044.
LeBlanc
,
D.
, 2010
, “
Molten Salt Reactors: A New Beginning for an Old Idea
,” Nucl. Eng. Des.
,
240
(6
), pp. 1644
–1656
.10.1016/j.nucengdes.2009.12.0335.
Heuer
,
D.
,
Merle-Lucotte
,
E.
,
Allibert
,
M.
,
Brovchenko
,
M.
,
Ghetta
,
V.
, and
Rubiolo
,
P.
, 2014
, “
Towards the Thorium Fuel Cycle With Molten Salt Fast Reactors
,” Ann. Nucl. Energy
,
64
, pp. 421
–429
.10.1016/j.anucene.2013.08.0026.
Mathieu
,
L.
,
Heuer
,
D.
,
Brissot
,
R.
,
Garzenne
,
C.
,
Le Brun
,
C.
,
Lecarpentier
,
D.
,
Liatard
,
E.
, et al., 2006
, “
The Thorium Molten Salt Reactor: Moving on From the MSBR
,” Prog. Nucl. Energy
,
48
(7
), pp. 664
–679
.10.1016/j.pnucene.2006.07.0057.
Liaoyuan
,
H.
,
Shaopeng
,
X.
,
Jingen
,
C.
,
Guimin
,
L.
,
Jianhui
,
W.
, and
Yang
,
Z.
, 2021
, “
Th-U Breeding Performances in an Optimized Molten Chloride Salt Fast Reactor
,” Nucl. Sci. Eng.
,
195
(2
), pp. 185
–202
.10.1080/00295639.2020.17987288.
Jeong
,
Y.
,
Park
,
J.
,
Lee
,
H. C.
, and
Lee
,
D.
, 2016
, “
Equilibrium Core Design Methods for Molten Salt Breeder Reactor Based on Two-Cell Model
,” J. Nucl. Sci. Technol.
,
53
(4
), pp. 529
–536
.10.1080/00223131.2015.10628129.
Zou
,
C. Y.
,
Cai
,
X. Z.
,
Jiang
,
D. Z.
,
Yu
,
C. G.
,
Li
,
X. X.
,
Ma
,
Y. W.
,
Han
,
J. L.
, and
Chen
,
J. G.
, 2015
, “
Optimization of Temperature Coefficient and Breeding Ratio for a Graphite-Moderated Molten Salt Reactor
,” Nucl. Eng. Des.
,
281
, pp. 114
–120
.10.1016/j.nucengdes.2014.11.02210.
Dwijayanto
,
R. A. P.
, and
Hermawan
,
D. P.
, 2020
, “
Investigation on Inherent Safety of One Fluid-Molten Salt Reactor (OF-MSR) With Various Starting Fuel
,” Tri Dasa Mega
,
22
(2
), p. 54
.10.17146/tdm.2020.22.2.589311.
Huke
,
A.
,
Ruprecht
,
G.
,
Weißbach
,
D.
,
Gottlieb
,
S.
,
Hussein
,
A.
, and
Czerski
,
K.
, 2015
, “
The Dual Fluid Reactor – A Novel Concept for a Fast Nuclear Reactor of High Efficiency
,” Ann. Nucl. Energy
,
80
, pp. 225
–235
.10.1016/j.anucene.2015.02.01612.
Ifthacharo
,
M.
,
Permana
,
S.
, and
Saputra
,
G.
, 2020
, “
A Comparative Study of Th-U 233 and Th-Pu Molten-Salt Reactor (MSR) With 2-Region Core
,” J. Phys.: Conf. Ser.
,
1493
(1
), p. 012015
.10.1088/1742-6596/1493/1/01201513.
Singh
,
V.
,
Lish
,
M. R.
,
Chvála
,
O.
, and
Upadhyaya
,
B. R.
, 2017
, “
Dynamics and Control of Molten-Salt Breeder Reactor
,” Nucl. Eng. Technol.
,
49
(5
), pp. 887
–895
.10.1016/j.net.2017.06.00314.
Li
,
G. C.
,
Cong
,
P.
,
Yu
,
C. G.
,
Zou
,
Y.
,
Sun
,
J. Y.
,
Chen
,
J. G.
, and
Xu
,
H. J.
, 2018
, “
Optimization of Th-U Fuel Breeding Based on a Single-Fluid Double-Zone Thorium Molten Salt Reactor
,” Prog. Nucl. Energy
,
108
, pp. 144
–151
.10.1016/j.pnucene.2018.04.01715.
Harto
,
A. W.
, 2012
, “
Passive Compact Molten Salt Reactor (PCMSR), Modular Thermal Breeder Reactor With Totally Passive Safety System
,” The Third International Conference on Advances in Nuclear Science and Engineering,
Bali, Indonesia
, pp. 82
–95
.16.
Wu
,
J.
,
Chen
,
J.
,
Kang
,
X.
,
Li
,
X.
,
Yu
,
C.
,
Zou
,
C.
, and
Cai
,
X.
, 2019
, “
A Novel Concept for a Molten Salt Reactor Moderated by Heavy Water
,” Ann. Nucl. Energy
,
132
, pp. 391
–403
.10.1016/j.anucene.2019.04.04317.
Zhang
,
Y.-P.
,
Ma
,
Y.-W.
,
Wu
,
J.-H.
,
Chen
,
J.-G.
, and
Cai
,
X.-Z.
, 2020
, “
Preliminary Analysis of Fuel Cycle Performance for a Small Modular Heavy Water-Moderated Thorium Molten Salt Reactor
,” Nucl. Sci. Tech.
,
31
(11
), p. 108
.10.1007/s41365-020-00823-518.
Imron
,
M. M.
, and
Harto
,
A. W.
, 2010
, “
Analisis Transien Pada Passive Compact Molten Salt Reactor (PCMSR)
,” Tri Dasa Mega
,
12
(2
), pp. 75
–92.
19.
Dwijayanto
,
R. A. P.
,
Hermawan
,
D. P.
, and
Harto
,
A. W.
, 2020
, “
Preliminary Investigation on Neutronic Performance of Pu-Started One Fluid-Molten Salt Reactor (OF-MSR)
,” Prosiding Seminar Nasional Teknologi Nuklir 2020
, Serpong, Indonesia
, Nov. 18
, pp. 141
–147
.https://www.researchgate.net/publication/353452647_Preliminary_Investigation_on_Neutronic_Performance_of_Pu-started_One_Fluid-Molten_Salt_Reactor_OF-MSR20.
Rykhlevskii
,
A.
,
Bae
,
J. W.
, and
Huff
,
K. D.
, 2019
, “
Modeling and Simulation of Online Reprocessing in the Thorium-Fueled Molten Salt Breeder Reactor
,” Ann. Nucl. Energy
,
128
, pp. 366
–379
.10.1016/j.anucene.2019.01.03021.
Robertson
,
R. C.
, 1971
, “Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor, ORNL-4511
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
.22.
Park
,
J.
,
Jeong
,
Y.
,
Lee
,
H. C.
, and
Lee
,
D.
, 2015
, “
Whole Core Analysis of Molten Salt Breeder Reactor With Online Fuel Reprocessing: Whole Core Analysis of MSBR With Online Fuel Reprocessing
,” Int. J. Energy Res.
, 39, p. 1673
.10.1002/er.337123.
Ashraf
,
O.
,
Rykhlevskii
,
A.
,
Tikhomirov
,
G. V.
, and
Huff
,
K. D.
, 2020
, “
Whole Core Analysis of the Single-Fluid Double-Zone Thorium Molten Salt Reactor (SD-TMSR)
,” Ann. Nucl. Energy
,
137
, p. 107115
.10.1016/j.anucene.2019.10711524.
Harto
,
A. W.
, 2016
, “
Nuclide Composition Analysis of PCMSR Fuel Using Thorium as Sustainable Fuel And Low Enrich Uranium As Starting Fuel
,” ARPN J. Eng. Appli. Sci.
,
11
(6
), p. 3993
.25.
Widiharto
,
A.
, 2018
, “
Study on the Ability of PCMSR to Produce Valuable Isotopes as a By Product of Energy Generation
,” IJPNA
,
3
(1
), pp. 7
–14
.10.24246/ijpna.v3i1.7-1426.
Harto
,
A. W.
, 2015
, “
Sustainable Criticality Analysis of PCMSR Fuel Using Thorium as Sustainable Fuel and Low Enriched Uranium as Starting Fuel
,” IJNEST
,
9
(3
), p. 224
.10.1504/IJNEST.2015.07409827.
Dwijayanto
,
R. A. P.
,
Oktavian
,
M. R.
,
Putra
,
M. Y. A.
, and
Harto
,
A. W.
, 2021
, “
Model Comparison of Passive Compact-Molten Salt Reactor Neutronic Design Using MCNP6 and Serpent-2
,” Atom Indones.
,
47
(3
), p. 191
.10.17146/aij.2021.112228.
Zuhair, Suwoto, Setiadipura
,
T.
, and
Kuijper
,
J. C.
, 2019
, “
Study on the Characteristics of Effective Delayed Neutron Fraction (βeff) for Pebble-Bed Reactor With Plutonium Fuel
,” Iran J. Sci. Technol. Trans. Sci.
,
43
(6
), pp. 3037
–3045
.10.1007/s40995-019-00772-829.
Sembiring
,
T. M.
,
Susilo
,
J.
, and
Pinem
,
S.
, 2018
, “
Evaluation of the AP1000 Delayed Neutron Parameters Using MCNP6
,” J. Phys.: Conf. Ser.
,
962
, p. 012030
.10.1088/1742-6596/962/1/01203030.
Du Toit
,
M. H.
, and
Naicker
,
V. V.
, 2018
, “
Neutronic Design of Homogeneous Thorium/Uranium Fuel for 24 Month Fuel Cycles in the European Pressurized Reactor Using MCNP6
,” Nucl. Eng. Des.
,
337
, pp. 394
–405
.10.1016/j.nucengdes.2018.07.02331.
Jaradat
,
S. Q.
, and
Alajo
,
A. B.
, 2017
, “
Studies on the Liquid Fluoride Thorium Reactor: Comparative Neutronics Analysis of MCNP6 Code With SRAC95 Reactor Analysis Code Based on FUJI-U3-(0)
,” Nucl. Eng. Des.
,
314
, pp. 251
–255
.10.1016/j.nucengdes.2017.02.01332.
Ashraf
,
O.
,
Rykhlevskii
,
A.
,
Tikhomirov
,
G. V.
, and
Huff
,
K. D.
, 2020
, “
Strategies for Thorium Fuel Cycle Transition in the SD-TMSR
,” Ann. Nucl. Energy
,
148
, p. 107656
.10.1016/j.anucene.2020.10765633.
Rykhlevskii
,
A.
,
Lindsay
,
A.
, and
Huff
,
K. D.
, 2017
, “
Full-Core Analysis of Thorium-Fueled Molten Salt Breeder Reactor Using the SERPENT 2 Monte Carlo Code
,” Transactions of the American Nuclear Society
, Vol.
117
, Washington, DC, Oct. 29–Nov. 2, pp. 1343
–1346
.https://arfc.github.io/papers/rykhlevskii_full-core_2017.pdf34.
Lamarsh
,
J. R.
, 2002
, Introduction to Nuclear Reactor Theory
,
Addison-Wesley Publishing Company
, Boston, MA.35.
Hartanto
,
D.
,
Alshamsi
,
A.
,
Alsuwaidi
,
A.
,
Bilkhair
,
A.
,
Hukal
,
H. A.
, and
Zubair
,
M.
, 2020
, “
Neutronics Assessment of Accident-Tolerant Fuel in Advanced Power Reactor 1400 (APR1400)
,” Atom Indones.
,
46
(3
), p. 177
.10.17146/aij.2020.107336.
Gentry
,
C.
,
Kim
,
K. S.
, and
Maldonado
,
G. I.
, 2018
, “
Two-Step Procedure for Liquid-Salt-Cooled-Reactor Analysis
,” Nucl. Technol.
,
204
(3
), pp. 299
–317
.10.1080/00295450.2018.1486158
