Abstract

Molten salt reactors (MSRs) are a family of advanced, generation-IV, nuclear reactors that use a circulating molten alkali fluoride fuel salt as both a primary working fluid and a fuel matrix. Since the fuel salt is liquid, gases become entrained in the fuel salt flow, and these entrained gases are called circulating voids. This paper reviews some aspects of circulating voids on reactor behavior. A formal definition of the circulating void fraction is given. A time-line of Oak Ridge reports on circulating void behavior is presented. Methods to measure the circulating void fraction are described. Foam induced by gas entrained in the fuel salt is discussed. The discovery of circulating voids in the molten salt reactor experiment (MSRE) is detailed. Aspects related to bubble size and interfacial area are reviewed. The Laplace pressure is examined. The void and pressure coefficients of reactivity are examined. Some requirements for a bubble model for xenon behavior analysis are proposed. The effects of bubble surface mobility are examined. Finally, sources of gas production in the fuel salt are investigated.

References

1.
Sorensen
,
K.
,
2019
, “
Energy From Thorium
,” accessed May 11, 2019, http://energyfromthorium.com
2.
Kohn
,
H.
,
1968
, “
Bubbles, Drops, and Entertainment in Molten Salts
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-2373
.http://moltensalt.org/references/static/downloads/pdf/ORNL-TM-2373.pdf
3.
Prince
,
B.
,
Ball
,
S.
,
Engel
,
J.
,
Haubenreich
,
P.
, and
Kerlin
,
T.
,
1968
, “
Zero-Power Physics Experiments on the Molten-Salt Reactor Experiment (MSRE)
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-4233
.http://moltensalt.org/references/static/downloads/pdf/ORNL-4233.pdf
4.
Fry
,
D.
,
Kryter
,
R.
, and
Robinson
,
R.
,
1968
, “
Measurement of Helium Void Fraction in the MSRE Fuel Salt Using Neutron-Noise Analysis
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNLTM-2315
.http://moltensalt.org/references/static/downloads/pdf/ORNL-TM-2315.pdf
5.
Rosenthal
,
M.
,
Briggs
,
R.
, and
Haubenreich
,
P.
,
1973
, “
Molten-Salt Reactor Program Semiannual Progress Report—Period Ending August 31, 1972
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-4832
.https://www.osti.gov/servlets/purl/4466863
6.
Briggs
,
R.
,
1963
, “
Molten Salt Reactor Program Semi-Annual Progress Report For Period Ending July 31, 1963
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-3529
.
7.
Briggs
,
R.
,
1967
, “
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1966
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-4037
.
8.
Robinson
,
J.
, and
Fry
,
D.
,
1969
, “
Determination of the Void Fraction in the MSRE Using Small Induced Pressure Perturbations
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-2318
.
9.
Smith
,
P.
,
1970
, “
Development of Fuel and Coolant Salt Centrifugal Pumps for the Molten Salt Reactor Experiment
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-2987
.
10.
Engel
,
J.
,
Haubenreich
,
P.
, and
Houtzeel
,
A.
,
1970
, “
Spray, Mist, Bubbles, and Foam in the Molten Salt Reactor Experiment
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-3027
.http://moltensalt.org/references/static/downloads/pdf/ORNL-TM-3027.pdf
11.
Engel
,
J.
, and
Steffy
,
R.
,
1971
, “
Xenon Behavior in the Molten Salt Reactor Experiment
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-3464
.https://www.osti.gov/servlets/purl/4731186
12.
Smith
,
P.
,
1962
, “
Water Test Development of the Fuel Pump for the MSRE
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-79
.
13.
Briggs
,
R.
,
1965
, “
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1965
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-3872
.
14.
Kedl
,
R.
, and
Houtzeel
,
A.
,
1967
, “
Development of a Model for Computing Xe-135 Migration in the MSRE
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-4069
.http://moltensalt.org/references/static/downloads/pdf/ORNL-4069.pdf
15.
Gabbard
,
C.
,
1972
, “
Development of a Venturi Type Bubble Generator for Use in the Molten Salt Reactor Xenon Removal System
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-4122
.http://thmfgrcs.homestead.com/ORNL-TM-4122.pdf
16.
Hinze
,
J.
,
1955
, “
Fundamentals of the Hydrodynamic Mechanism of Splitting in Dispersion Processes
,”
Am. Inst. Chem. Eng. J.
,
1
(
3
), pp.
289
295
.10.1002/aic.690010303
17.
Jain
,
S.
,
2017
, “
Flow-Induced Breakup of Drops and Bubbles
,” preprint arXiv:1701.06157.
18.
Quigley
,
C.
,
Johnson
,
A.
, and
Harris
,
B.
,
1955
, “
Size and Mass Transfer Studies of Gas Bubbles
,”
Chemical Engineering Progress Symposium Series
, Vol.
1
,
American Institute of Chemical Engineers
, p.
31
.
19.
Butt
,
H.
,
Graf
,
K.
, and
Kappl
,
M.
,
2006
,
Physics and Chemistry of Interfaces
,
Wiley
,
Hoboken, NJ
, p.
495
.
20.
Sohal
,
M.
,
Ebner
,
M.
,
Sabharwall
,
P.
, and
Sharpe
,
P.
,
2010
, “
Engineering Database of Liquid Salt Thermophysical and Thermochemical Properties
,”
daho National Laboratory
,
Idaho Falls, ID
,
Report No. INL/EXT-10-18297
.
21.
Cantor
,
S.
,
Cooke
,
W.
,
Dworkin
,
S.
,
Robbins
,
D.
,
Thoma
,
E.
, and
Watson
,
M.
,
1968
, “
Physical Properties of Molten-Salt Reactor Fuel, Coolant and Flush Salts
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM2316
.http://moltensalt.org/references/static/downloads/pdf/ORNL-TM-2316.pdf
22.
Elsheikh
,
B.
,
2013
, “
Safety Assessment of Molten Salt Reactors in Comparison With Light Water Reactors
,”
J. Radiat. Res. Appl. Sci.
,
6
(
2
), pp.
63
70
.10.1016/j.jrras.2013.10.008
23.
Furukawa
,
K.
,
Simonenko
,
V.
,
Mitachi
,
K.
,
Furuhashi
,
A.
,
Yoshioka
,
R.
,
Chigrinov
,
S.
,
Lecocq
,
A.
, and
Kato
,
Y.
,
2002
, “
Thorium Cycle Implementation Through Plutonium Incineration by Thorium Molten-Salt Nuclear Energy Synergetics
,”
Thorium Fuel Utilization: Options and Trends (IAEATECDOC-1319)
, International Atomic Energy Agency,
Vienna, AT
, pp.
123
138
.https://www-pub.iaea.org/MTCD/publications/PDF/te_1319_web.pdf
24.
Rosenthan
,
M.
,
Haubenreich
,
P.
, and
Briggs
,
R.
,
1972
, “
The Development Status of Molten-Salt Breeder Reactors
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-4812
.
25.
Engel
,
J.
,
Baurman
,
H.
,
Dearing
,
J.
,
Grimes
,
W.
,
McCoy
,
E.
, and
Rhoades
,
W.
,
1980
, “
Conceptual Design Characteristics of a Denatured Molten-Salt Reactor With Oonce-Through Fueling
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL/TM7207
.
26.
Suzuki
,
N.
, and
Shimazu
,
Y.
,
2006
, “
Preliminary Safety Analysis on Depressurization Accident Without Scram of a Molten Salt Reactor
,”
J. Nucl. Sci. Technol.
,
43
(
7
), pp.
720
730
.10.1080/18811248.2006.9711154
27.
Suzuki
,
N.
, and
Shimazu
,
Y.
,
2008
, “
Reactivity-Initiated Accident Analysis Without Scram of a Molten Salt Reactor
,”
J. Nucl. Sci. Technol.
,
45
(
6
), pp.
575
581
.10.1080/18811248.2008.9711881
28.
Rosenthal
,
M.
,
Briggs
,
P.
, and
Kasten
,
P.
,
1967
, “
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending February 28, 1967
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-4119
.http://moltensalt.org/references/static/downloads/pdf/ORNL-4119.pdf
29.
Rosenthal
,
M.
,
Briggs
,
R.
, and
Kasten
,
P.
,
1967
, “
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1967
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-4191
.http://moltensalt.org/references/static/downloads/pdf/ORNL-4191.pdf
30.
Haubenreich
,
P.
, and
Engel
,
J.
,
1970
, “
Experience With the Molten-Salt Reactor Experiment
,”
Nucl. Appl. Technol.
,
8
(
2
), pp.
118
136
.10.13182/NT8-2-118
31.
Wang
,
W.
,
Zhou
,
Z.
,
Nandakumar
,
K.
,
Xu
,
Z.
, and
Masliyah
,
J.
,
2003
, “
Effect of Surface Mobility on the Particle Sliding Along a Bubble or a Solid Sphere
,”
J. Colloid Interface Sci.
,
259
(
1
), pp.
81
88
.10.1016/S0021-9797(02)00140-6
32.
Peebles
,
F.
,
1968
, “
Removal of Xenon-135 From Circulating Fuel Salt of the MSBR by Mass Transfer to Helium Bubbles
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-2245
.http://moltensalt.org/references/static/downloads/pdf/ORNL-TM-2245.pdf
33.
Lyu
,
X.
,
Xia
,
X.
,
Zhang
,
Z.
,
Cai
,
J.
, and
Chen
,
C.
,
2016
, “
Analysis of Tritium Production in a 2 MW Liquid-Fueled Molten Salt Experimental Reactor and Its Environmental Impact
,”
Nucl. Sci. Tech.
,
27
(
4
), p.
78
.https://link.springer.com/article/10.1007/s41365-016-0100-z
34.
Haubenreich
,
P.
,
Engel
,
J.
,
Prince
,
B.
, and
Claiborne
,
H.
,
1964
, “
MSRE Design and Operations Report—Part III: Nuclear Analysis
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-730
.https://www.osti.gov/servlets/purl/4114686
35.
Albenesius
,
E.
,
1959
, “
Tritium as a Product of Fission
,”
Phys. Rev. Lett.
,
3
(
6
), pp.
274
275
.10.1103/PhysRevLett.3.274
36.
Forsberg
,
C. W.
,
Peterson
,
P. F.
,
Sridharan
,
K.
,
Hu
,
L.
,
Fratoni
,
M.
, and
Prinja
,
A. K.
,
2018
, “
Integrated FHR Technology Development: Tritium Management, Materials Testing, Salt Chemistry Control, Thermal Hydraulics and Neutronics, Associated Benchmarking and Commercial Basis
,”
Massachusetts Institute of Technology
,
Cambridge, MA
,
Report No. MITANP-TR-180
.
37.
Qin
,
H.
,
Wang
,
C.
,
Qiu
,
S.
,
Zhang
,
D.
,
Tian
,
W.
, and
Su
,
G. H.
,
2018
, “
Study of Tritium Transport Characteristics in a Transportable Fluoride-Salt-Cooled High Temperature Reactor
,”
Int. J. Energy Res.
,
42
(
4
), pp.
1536
1550
.10.1002/er.3944
38.
Singh
,
B.
,
Rodionov
,
A.
, and
Khazov
,
Y.
,
2008
, “
Nuclear Data Sheets for a = 135
,”
Nucl. Data Sheets
,
109
(
3
), pp.
517
698
.10.1016/j.nds.2008.02.001
39.
Lamarsh
,
J.
, and
Baratta
,
A.
,
2001
,
Introduction to Nuclear Engineering
, 3rd ed.,
Prentice Hall
,
Upper Saddle River, NJ
, p.
626
.
40.
IAEA
, 2019, “
Research Reactor Database
,” International Atomic Energy Agency, accessed Mar. 27, 2019, https://www.iaea.org/resources/databases/research-reactor-database-rrdb
41.
Briggs
,
R.
,
1964
, “
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending July 31, 1964
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-3708
.https://technicalreports.ornl.gov/1964/3445600500358.pdf
42.
Haubenreich
,
P.
,
1970
, “
Fluorine Production and Recombination in Frozen MSR Salts After Reactor Operation
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-3144
.http://moltensalt.org/references/static/downloads/pdf/ORNL-TM-3144.pdf
43.
Grimes
,
W.
,
1963
, “
Radiation Chemistry of MSR System
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
.
44.
Price
,
T.
,
Chvala
,
O.
, and
Taylor
,
R.
,
2019
, “
Molten Salt Reactor Xenon Analysis: Review and Decomposition
,”
ASME J. Nucl. Eng. Radiat. Sci.
,
5
(
4
), p.
041210
.10.1115/1.4043813
45.
Shimazu
,
Y.
,
1977
, “
Transient Xenon Analysis in a Molten Salt Breeder Reactor
,”
J. Nucl. Sci. Technol.
,
14
(
11
), pp.
805
810
.10.1080/18811248.1977.9730841
46.
Kress
,
T.
,
1972
, “
Mass Transfer Between Small Bubbles and Liquids in Cocurrent Turbulent Pipeline Flow
,”
Oak Ridge National Laboratory
,
Oak Ridge, TN
,
Report No. ORNL-TM-3718
.
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