Molten salt reactor (MSR) has been recognized as one of the next-generation nuclear power systems. Most MSR concepts are the variants evolved from the Oak Ridge National Laboratory (ORNL's) molten-salt breeder reactor (MSBR), which employs molten-salt as both fuel and coolant, and normally graphite is used as moderator. Many evaluations have revealed that such concepts have low breeding ratio and might present positive power coefficient. Facing these impediments, thorium molten salt reactor (TMSR) with redesigned lattice is proposed in this paper. Based on comprehensive investigation and screening, important lattice parameters including molten salt fuel composition, solid moderator material, lattice size, structure and lattice pitch to channel diameter (P/D) ratio are redesigned. In this paper, a fuel composition without BeF2 is adopted to increase the solubility for actinides (ThF4, UF4), and BeO is introduced as moderator to improve neutron economy. Moreover, lattice size and structure with cladding to separate fuel and moderator were also optimized. With these lattice parameters, TMSR has a high breeding ratio close to 1.14 and a short doubling time about 15 years. Meanwhile, a negative power coefficient is maintained. Based on this lattice design, TMSR can have excellent performance of safety and sustainability. SONG/TANG-MSR codes system is applied in the simulation, which is independently developed by Shanghai Nuclear Engineering Research & Design Institute (SNERDI).

References

References
1.
GIF
,
2002
, “
A Technology Roadmap for Generation IV Nuclear Energy Systems
,” Generation IV International Forum, U.S. DOE, Washington, DC, Report No. GIF-002-00.
2.
Lecarpentier
,
D.
, and
Vergnes
,
J.
,
2002
, “
The AMSTER (Actinide Molten Salt TransmutER) Concept
,”
Nucl. Eng. Des.
,
216
(
1–3
), pp.
43
67
.
3.
Mathieu
,
L.
,
Heuer
,
D.
,
Nuttin
,
A.
,
Perdu
,
F.
, and
Billebaud
,
A.
,
2003
, “
Thorium Molten Salt Reactor: From High Breeding to Simplified Reprocessing
,”
Global 2003
, New-Orleans, LA, Nov. 16–20.http://hal.in2p3.fr/in2p3-00020302/document
4.
Mathieu
,
L.
,
Heuer
,
D.
,
Nuttin
,
A.
,
Perdu
,
F.
, and
Billebaud
,
A.
,
2005
, “
Proposition for a Very Simple Thorium Molten Salt Reactor
,”
Global Conference
,
Tsukuba, Japan
.
5.
Mathieu
,
L.
,
Heuer
,
D.
,
Nuttin
,
A.
,
Perdu
,
F.
, and
Billebaud
,
A.
,
2005
, “
The Thorium Molten Salt Reactor: Moving on From the MSBR
,”
Prog. Nucl. Energy
,
48
(
7
), pp.
664
679
.
6.
Robertson
,
R. C.
,
1971
, “
Conceptual Design Study of a Single Fluid Molten Salt Breeder Reactor
,” Oak Ridge National Laboratory, Oak Ridge, TN, Report No.
ORNL-4541
.http://moltensalt.org/references/static/downloads/pdf/ORNL-4541.pdf
7.
Rothental
,
M. W.
,
Haubenreich
,
P. N.
, and
Briggs
,
R. B.
,
1972
, “
The Development Status of Molten-Salt Breeder Reactors
,” Oak Ridge National Laboratory, Oak Ridge, TN, Report No. ORNL-4812.
8.
Nuttin
,
A.
,
Heuer
,
D.
,
Billebaud
,
A.
,
Brissot
,
R.
, and
Brun
,
C. L.
,
2004
, “
Potential of Thorium Molten Salt Reactors: Detailed Calculations and Concept Evolution With a View to Large Scale Production Energy
,”
Prog. Nucl. Energy
,
46
(
1
), pp.
77
99
.
9.
Furukawaa
,
K.
,
Erbay
,
L. B.
, and
Aykol
,
A.
,
2012
, “
A Study on a Symbiotic Thorium Breeding Fuel-Cycle: THORIMS-NES through FUJI
,”
Energy Convers. Manage.
,
63
, pp.
51
54
.
10.
Si
,
S.
,
Chen
,
Q.
,
Bei
,
H.
, and
Zhao
,
J.
,
2015
, “
New Exploration on TMSR: Modelling and Simulation
,”
Seventh International Conference on Modelling and Simulation in Nuclear Science and Engineering
,
Ottawa, ON, Canada
,
Oct. 18–21
.
11.
Auger
,
T.
,
Barreau
,
G.
, and
Chevalier
,
J. P.
,
2008
, “
Thorium Cycle and the Molten Salt Reactors
,” CRNS, Paris, France.
12.
Si
,
S.
,
Chen
,
Q.
,
Bei
,
H.
, and
Zhao
,
J.
,
2014
, “
SONG-Description of Multi-Functional Lattice Code
,”
Nucl. Power Eng.
,
35
(
s2
), pp.
112
115
.
13.
Bei
,
H.
,
Zhao
,
J.
,
Chen
,
Q.
, and
Si
,
S.
,
2014
, “
Design and Processing of Multi-Group Cross Section Library for SONG
,”
Nucl. Power Eng.
,
35
(
s2
), pp.
173
175
.
14.
Si
,
S.
,
2010
, “
3D Coarse Mesh NEM Embedded With 2D Fine Mesh NDOM for PWR Core Analysis
,”
Advances in Reactor Physics to Power the Nuclear Renaissance
(
PHYSOR
),
Pittsburgh, PA
,
May 9–14
.https://inis.iaea.org/search/search.aspx?orig_q=RN:42004135
15.
Benes
,
O.
,
Cabet
,
C.
, and
Delpech
,
S.
,
2009
, “
Review Report on Liquid Salts for Various Applications, Assessment of Liquid Salts for Innovative Applications
,” Institute for Transuranium Elements, Joint Research Centre, European Commission.
16.
Su
,
B.
,
2016
,
Research on Preparation and Property of SiC Ceramic in Nuclear Energy System
,
University of Chinese Academy of Sciences
, Beijing, China.
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