Point reactor neutron kinetics equations describe the time-dependent neutron density variation in a nuclear reactor core. These equations are widely applied to nuclear system numerical simulation and nuclear power plant operational control. This paper analyzes the characteristics of ten different basic or normal methods to solve the point reactor neutron kinetics equations. The accuracy after introducing different kinds of reactivity, stiffness of methods, and computational efficiency are analyzed. The calculation results show that: considering both the accuracy and stiffness, implicit Runge–Kutta method and Hermite method are more suitable for solution on these given conditions. The explicit Euler method is the fastest, while the power series method spends the most computational time.

References

1.
Ray
,
S. S.
,
2012
, “
An Explicit Finite Difference Scheme for Numerical Solution of Fractional Neutron Point Kinetic Equation
,”
Ann. Nucl. Energy
,
41
(
41
), pp.
61
66
.
2.
Chen
,
C.
,
1998
, “
A New Numerical Method of Solving the Point Reactor Neutron Kinetics Equations
,”
Chin. J. Nucl. Sci. Eng.
,
18
(4), pp. 364–370.http://en.cnki.com.cn/Article_en/CJFDTOTAL-HKXY804.012.htm
3.
Basken
,
J.
, and
Lewins
,
J. D.
,
1996
, “
Power Series Solutions of the Reactor Kinetics Equations
,”
Nucl. Sci. Eng.
,
122
(
3
), pp.
407
416
.
4.
Aboanber
,
A. E.
, and
Hamada
,
Y. M.
,
2003
, “
Power Series Solution (PWS) of Nuclear Reactor Dynamics With Newtonian Temperature Feedback
,”
Ann. Nucl. Energy
,
30
(
10
), pp.
1111
1122
.
5.
Sathiyasheela
,
T.
,
2009
, “
Power Series Solution Method for Solving Point Kinetics Equations With Lumped Model Temperature and Feedback
,”
Ann. Nucl. Energy
,
36
(
2
), pp.
246
250
.
6.
Cai
,
Z. S.
,
Cai
,
Z. M.
, and
Cheng
,
L. S.
,
2001
, “
Solution of Point-Reactor Neutron-Kinetics Equation With Temperature Feedback by Decoupling Method
,”
Nucl. Power Eng.
,
22
(
5
), pp.
390
391
.http://en.cnki.com.cn/Article_en/CJFDTOTAL-HDLG200105001.htm
7.
Yuan
,
H.
, and
Hu
,
D.
,
1995
, “
High-Order End Floating Method—for Solving Point Reactor Neutron Kinetics Equations
,”
Nucl. Power Eng.
,
16
(
2
), pp.
124
128
. http://en.cnki.com.cn/Article_en/CJFDTOTAL-HDLG502.005.htm
8.
Kueng
,
Y.
,
1978
, “
Polynomial Approach to Reactor Kinetics Equations
,”
Nucl. Sci. Eng.
,
66
(
2
), pp.
235
242
.
9.
Tian
,
H.
,
1989
, “
Interpolation Polynomial Approach to Reactor Kinetics Equations
,”
Nucl. Power Eng.
,
10
(
8
), pp.
39
46
.http://en.cnki.com.cn/Article_en/CJFDTOTAL-HDLG198906009.htm
10.
Li
,
L. K.
,
Yu
,
C. H.
, and
Zhu
,
Z. H.
,
1999
,
Numerical Solutions for Differential Equations
,
Fudan University Press
,
Shanghai, China
.
You do not currently have access to this content.