Abstract

Due to the circulating nature of the fuel, there is a qualitative difference between xenon behavior in a molten salt reactor (MSR) compared to a solid fuel reactor. Therefore, the equations that describe 135Xe behavior in a molten salt reactor must be formulated differently. Prior molten salt reactor xenon models have focused on behavior below a solubility limit in which the 135Xe is partially dissolved in the fuel salt. It is foreseeable that a molten salt reactor may operate with a concentration of gas dissolved in the salt sufficiently high such that no further gas may dissolve in the fuel salt. This paper introduces a theory of molten salt reactor xenon behavior for a reactor operating above the solubility limit. A model was developed based on this theory and analyses performed are discussed. Results indicate: (1) steady-state xenon poisoning is not monotonic with respect to gas egress rate, (2) a increase in gas ingress rate leads to a characteristic increase which is followed by a new steady-state in xenon poisoning, and (3) given a sufficient rate of gas egress, it is possible to remove the iodine pit behavior.

References

1.
Dolan
,
T.
,
2017
,
Molten Salt Reactors and Thorium Energy
,
Woodhead Publishing
,
Kidlington, UK
, p.
841
.
2.
Serp
,
J.
,
Allibert
,
M.
,
Beneš
,
O.
,
Delpech
,
S.
,
Feynberg
,
O.
,
Ghetta
,
V.
,
Heuer
,
D.
,
Holcomb
,
D.
,
Ignatiev
,
V.
,
Kloosterman
,
J. L.
,
Luzzi
,
L.
,
Merle-Lucotte
,
E.
,
Uhlíř
,
J.
,
Yoshioka
,
R.
, and
Zhimin
,
D.
,
2014
, “
The Molten Salt Reactor (MSR) in Generation IV: Overview and Perspectives
,”
Prog. Nucl. Energy
,
77
, pp.
308
319
.10.1016/j.pnucene.2014.02.014
3.
Hoglund
,
B.
,
2012
, “Molten Salt Energy Technologies Web Site,” accessed May 5, 2020, MoltenSalt.org.
4.
Ergen
,
W.
,
Callihan
,
A.
,
Mills
,
C.
, and
Scott
,
D.
,
1957
, “
The Aircraft Reactor Experiment—Physics
,”
Nucl. Sci. Eng.
,
2
(
6
), pp.
826
840
.10.13182/NSE57-A35496
5.
Scott
,
D.
,
Alwang
,
G.
,
Demski
,
E.
,
Fader
,
W.
,
Sandin
,
E.
, and
Malenfant
,
R.
,
1958
, “
A Zero Power Reflector-Moderated Reactor Experiment at Elevated Temperature
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
93
, Report No. ORNL-2536.
6.
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
7.
Robertson
,
R.
,
1965
, “
MSRE Design and Operations Report
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
536
, Report No. ORNL-TM-0728.
8.
Price
,
T. J.
,
Chvala
,
O.
, and
Taylor
,
Z.
,
2019
, “
Molten Salt Reactor Xenon Analysis: Review and Decomposition
,”
ASME J. Nucl. Eng. Radiat. Sci.
,
5
(
4
), p.
041210
.10.1115/1.4043813
9.
Grimes
,
W.
,
Smith
,
N.
, and
Watson
,
G.
,
1958
, “
Solubility of Noble Gases in Molten Fluorides—I: In Mixtures of NaF–ZrF4 (53-47 Mole %) and NaF–ZrF4–UF4 (50–46–4 Mole%)
,”
J. Phys. Chem.
,
62
(
7
), pp.
862
866
.10.1021/j150565a024
10.
Watson
,
G.
,
Evans
, III
R.
,
Grimes
,
W.
, and
Smith
,
N.
,
1962
, “
Solubility of Noble Gases in Molten Fluorides. In LiF-BeF2
,”
J. Chem. Eng. Data
,
7
(
2
), pp.
285
287
.10.1021/je60013a038
11.
Cottrell
,
W.
,
Hungerford
,
H.
,
Leslie
,
J.
, and
Meerv
,
J.
,
1955
, “
Operation of the Aircraft Reactor Experiment
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
238
, Report No. ORNL-1845.
12.
Miller
,
J.
,
1961
, “
Xenon Poisoning in Molten Salt Reactors
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
18
, Report No. ORNL-CF-61-5-62.
13.
Engel
,
J.
,
1962
, “
Preliminary Equations to Describe Iodine and Xenon Behavior in the MSRE
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
17
, Report No. ORNL-CF-62-11-69.
14.
Salzano
,
F.
, and
Eshaya
,
A.
,
1962
, “
Sorption of Xenon in High Density Graphite at High Temperatures
,”
Nucl. Sci. Eng.
,
12
(
1
), pp.
1
3
.10.13182/NSE62-A25361
15.
Eshaya
,
A. M.
, and
Wiswall
,
R. H.
,
1959
, “
The Chemistry of Fission Products in a Molten Metal Nuclear Fuel
,”
Trans. New York Acad. Sci.
,
21
(
8 Series II
), pp.
668
681
.10.1111/j.2164-0947.1959.tb01713.x
16.
Blander
,
M.
,
Grimes
,
W.
,
Smith
,
N.
, and
Watson
,
G.
,
1959
, “
Solubility of Noble Gases in Molten Fluorides—II: In the Lif-NaF-LF Eutectic Mixtures
,”
J. Phys. Chem.
,
63
(
7
), pp.
1164
1167
.10.1021/j150577a033
17.
Watson
,
G.
, and
Evans
,
R.
,
1962
, “
Xenon Diffusion in Graphite: Effects of Xenon Absorption in Molten Salt Reactors Containing Graphite
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
26
, Report No. ORNL-TM-262.
18.
Alexander
,
L.
,
Carter
,
W.
,
Craven
,
C.
,
Janney
,
D.
,
Kerlin
,
T.
, and
Van Winkle
,
R.
,
1965
, “
Molten Salt Converter Reactor. Design Study and Power Cost Estimates for a 1000 MWe Station
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
347
, Report No. ORNL-TM1060.
19.
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, p.
77
, Report No. ORNL-4069.
20.
Robertson
,
R.
,
1971
, “
Conceptual Design Study of a Single-Fluid Molten-Salt Breeder Reactor
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
189
, Report No. ORNL-TM-4541.
21.
Engel
,
J.
, and
Steffy
,
R.
,
1971
, “
Xenon Behavior in the Molten Salt Reactor Experiment
,” Oak Ridge National Laboratory, Oak Ridge, TN, p.
112
, Report No. ORNL-TM-3464.
22.
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
23.
Wu
,
J.
,
Li
,
X.
,
Hu
,
J.
,
Chen
,
J.
,
Yu
,
C.
,
Zou
,
C.
, and
Cai
,
X.
,
2018
, “
Influence of Xe-135 Dynamic Behavior on Core Operation Safety for a Molten Salt Reactor
,”
Proceedings of the 26th International Conference on Nuclear Engineering, ICONE26
, London, Jul. 22–28, Paper No. ICONE26-82352.
24.
MathWorks,
2019
, “
Mathworks Simulink
,” MathWorks, accessed Apr. 20, 2020, www.mathworks.com/products/simulink.html
25.
Post_Sol_Xe_Model, “
Post Solubility Xenon Model Repository Github
,” accessed Apr. 20,
2020
, https://github.com/TPrice2244/Post_Sol_Xe_Model
26.
Qin
,
H.
,
Wang
,
C.
,
Qiu
,
S.
,
Zhang
,
D.
,
Tian
,
W.
, and
Su
,
G.
,
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
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