Control rod hydraulic drive system (CRHDS), which is invented by INET, Tsinghua University, is a new type of internal control rod drive technology. Control rod hydraulic deceleration device (CRHDD), which consists of the plug, the hydraulic deceleration cylinder, etc., is one of the main components of the CRHDS. The CRHDD performs the rod dropping deceleration function through the interworking of the plug and the deceleration cylinder, which is filled with water, and reduces the rod dropping peak acceleration and the impact force acting upon the control rod to prevent the control rod cruciform blade from being deformed or damaged. The working mechanism of the CRHDD is presented and analyzed. The theoretical model of the control rod dropping process, which is based upon force analysis of the control rod during scram process, three-dimensional flow field analysis, and flow resistance calculation of the hydraulic deceleration cylinder, the kinematics and dynamics analysis of the control rod, is built whose results are compared and validated by the CRHDS scram test results. Then the model is used to analyze the influence of the key parameters, including the fuel case gap, the plug design clearance, the working temperature, etc. on the CRHDD working performance. The research results can give guidance for the design and optimization of the CRHDD.

References

1.
Rabiee, A., and Atf, A.,
2016
, “
Control Rod Drop Hydrodynamic Analysis for a Pressurized Water Reactor
,”
Prog. Nucl. Energy
,
88
, pp.
191
197
.
2.
Wu
,
Y. Q.
,
Hu
,
Y. D.
,
Cheng
,
Y. S.
, and
Yang
,
N. Z.
,
1990
, “
The Hydraulic Driving System for Control Rods on 5 MW District Heating Reactor (DHR
),”
J. Tsinghua Univ.: Sci. Technol.
,
30
(
6
), pp.
53
59
.
3.
Qiu
,
S. Z.
,
Guo
,
Y. J.
, and
Su
,
G. H.
,
1998
,
Nuclear Reactor Structures and Power Equipments
,
Xi'an Jiaotong University Press
,
Xi'an, China
, pp.
49
52
.
4.
Bo
,
H. L.
,
Zheng
,
W. X.
,
Wang
,
D. Z.
,
Jiang
,
S. Y.
, and
Yang
,
J. N.
,
2005
, “
Hydraulic Control Rod Drive Technology for Nuclear Reactors
,”
J. Tsinghua Univ.: Sci. Technol.
,
45
(
3
), pp.
424
427
.
5.
Wu
,
Y. Q.
,
Diao
,
X. Z.
,
Zhou
,
H. Z.
, and
Huang
,
Z. Y.
,
2002
, “
Design and Tests for the HTR-10 Control Rod System
,”
Nucl. Eng. Des.
,
218
, pp.
147
154
.
6.
Yoon
,
K. H.
,
Kim
,
J. Y.
,
Lee
,
K. H.
,
Lee
,
Y. H.
, and
Kim
,
H. K.
,
2009
, “
Control Rod Drop Analysis by Finite Element Method Using Fluid–Structure Interaction for a Pressurized Water Reactor Power Plant
,”
Nucl. Eng. Des.
,
239
(
10
), pp.
1857
1861
.
7.
Lahey
,
R. T.
, Jr.
, and
Moody
,
F. J.
,
1993
,
The Thermal-Hydraulics of a Boling Water Nuclear Reactor
, 2nd ed.,
American Nuclear Society
,
La Grange Park, IL
.
8.
Babu
,
V. R.
,
Veerasamy
,
R.
,
Patri
,
S.
, and
Raj
,
S. I. S.
,
2010
, “
Testing and Qualification of Control & Safety Rod and Its Drive Mechanism of Fast Breeder Reactor
,”
Nucl. Eng. Des.
,
240
, pp.
1728
1738
.
9.
Qin
,
B. K.
,
Bo
,
H. L.
,
Zheng
,
W. X.
, and
Wang
,
D. Z.
,
2008
, “
Pressure Transients in Hydraulic Cylinder Step-Up Motion of Control Rod Hydraulic Drive Mechanism
,”
J. Tsinghua Univ.: Sci. Technol.
,
48
(
12
), pp.
2118
2121
.
10.
Lv
,
C. D.
,
2001
,
Thermal Parameter Measurement and Treatment
,
Tsinghua University Press
,
Beijing, China
.
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