Due to the advantages of small volume, light weight, and long-time running, nuclear reactor can provide an ideal energy source for space crafts. In this paper, two small compact prismatic nuclear reactors with different core block materials are presented, which have a thermal power of 5 MW for 10 years of equivalent full power operation. These two reactors use Mo-14%Re alloy or nuclear grade graphite IG110 as core block material, loaded with 50% and 39.5% enriched uranium nitride (UN) fuel and cooled by helium, whose inlet/outlet temperature of the reactor and operational pressure are 850/1300 K and 2 MPa, respectively. High temperature helium flowing out of the reactor can be used as the working medium for closed Brayton cycle power conversion with high efficiency (more than 20%). Neutronics analyses of reactors for the preliminary design in this paper are performed using reactor Monte Carlo (RMC) code developed by Tsinghua University. Both the reactors have enough initial excess reactivity to ensure 10 years of full power operation without refueling, have safety margin for reactor shutdown with one control drum failed, and remain subcritical in the submersion accident. Finally, the two reactors are compared in aspect of the 235U mass and the total reactor mass.

References

References
1.
Hai
,
H.
, and
Ming
,
X.
,
1995
, “
Research on Application of Small Movable Reactor Power Systems Aboard
,”
Nucl. Power Eng.
,
16
(
5
), pp.
401
406
.
2.
Kiryushin
,
A. I.
,
Kodochigov
,
N. G.
,
Kouzavkov
,
N. G.
,
Ponomarev-Stepnoi
,
N. N.
,
Gloushkov
,
E. S.
, and
Grebennik
,
V. N.
,
1997
, “
Project of the GT-MHR High-Temperature Helium Reactor With Gas Turbine
,”
Nucl. Eng. Des.
,
173
(
1
), pp.
119
129
.
3.
Shiozawa
,
S.
,
Fujikawa
,
S.
,
Iyoku
,
T.
,
Kunitomi
,
K.
, and
Tachibana
,
Y.
,
2004
, “
Overview of HTTR Design Features
,”
Nucl. Eng. Des.
,
233
(
1
), pp.
11
21
.
4.
Methnani
,
M.
,
2005
, “
Evaluation of High Temperature Gas Cooled Reactor Performance
,” International Atomic Energy Agency, Vienna, Austria, Report No.
1694
.http://www-pub.iaea.org/MTCD/Publications/PDF/TE-1694_web.pdf
5.
King
,
J. C.
, and
El-Genk
,
M. S.
,
2006
, “
Solid-Core, Gas-Cooled Reactor for Space and Surface Power
,”
AIP Publ.
,
813
(
1
), pp.
298
307
.
6.
King
,
J. C.
, and
El-Genk
,
M. S.
,
2009
, “
Thermal-Hydraulic and Neutronic Analyses of the Submersion-Subcritical, Safe Space (S4) Reactor
,”
Nucl. Eng. Des.
,
239
(
12
), pp.
2809
2819
.
7.
King
,
J. C.
, and
El-Genk
,
M. S.
, “
Submersion-Subcritical Safe Space (S4) Reactor
,”
Nucl. Eng. Des.
,
236
(
17
), pp.
1759
1777
.
8.
Wang
,
K.
,
Li
,
Z. G.
,
She
,
D.
,
Liang
,
J. G.
,
Xu
,
Q.
,
Qiu
,
Y. S.
,
Yu
,
J. K.
,
Sun
,
J. L.
,
Fan
,
X.
, and
Yu
,
G. L.
,
2015
, “
RMC-a Monte Carlo Code for Reactor Core Analysis
,”
Ann. Nucl. Energy
,
82
(
SI
), pp.
121
129
.
9.
She
,
D.
,
Liang
,
J. G.
,
Wang
,
K.
, and
Forget
,
B.
,
2014
, “
2D Full-Core Monte Carlo Pin-by-Pin Burnup Calculations With the RMC Code
,”
Ann. Nucl. Energy
,
64
, pp.
201
205
.
10.
King
,
J. C.
, and
El-Genk
,
M. S.
,
2006
, “
Submersion Criticality Safety of Fast Spectrum Space Reactors: Potential Spectral Shift Absorbers
,”
Nucl. Eng. Des.
,
236
(
3
), pp.
238
254
.
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