Abstract
The continuous indication of the neutron density and its rate of change are important for the safe startup and operation of reactors. The best way to achieve this is to obtain analytical solutions of the neutron kinetics equations because none of the developed numerical methods can well satisfy the need for real-time or even super-time computation for the safe startup and operation of reactors in practice. In this paper, an accurate analytical solution of point kinetics equations with one-group delayed neutrons and an extraneous neutron source is proposed to calculate the change in neutron density, where the whole process from the subcritical stage to critical and supercritical stages is considered for step reactivity insertions. The accurate analytical solution can also be used as a benchmark of all numerical methods employed to solve stiff neutron kinetics equations.
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Li H F, Chen W Z, Zhang F, et al. Approximate solutions of point kinetics equations with one delayed neutron group and temperature feedback during delayed supercritical process. Ann Nucl Energy, 2007, 34: 521–526
Chen W Z, Kuang B, Guo L F, et al. New analysis of prompt supercritical process with temperature feedback. Nucl Eng Design, 2006, 236: 1326–1329
Chen W Z, Guo L F, Zhu B, et al. Accuracy of analytical methods for obtaining supercritical transients with temperature feedback. Prog Nucl Energy, 2007, 49: 290–302
Nahla A A. An analytical solution for the point reactor kinetics equations with one group of delayed neutrons and the adiabatic feedback model. Prog Nucl Energy, 2009, 51: 124–128
Brown H D. A general treatment of flux transients. Nucl Sci Eng, 1957, 2: 687–693
Kang C M, Hansen K F. Finite element methods for reactor analysis. Nucl Sci Eng, 1973, 51: 456–495
Sánchez J. On the numerical solution of the point reactor kinetics equations by generalized Runge-Kutta methods. Nucl Sci Eng, 1989, 103: 94–99
Ott K O, Meneley D A. Accuracy of the quasistatic treatment of spatial reactor kinetics. Nucl Sci Eng, 1969, 36: 402–411
Koclas J, Sissaoui M T, Hébert A. Solution of the improved and generalized quasistatic methods using an analytic calculation or a semi-implicit scheme to compute the precursor equations. Ann Nucl Energy, 1996, 23: 1127–1142
Hennart J P. Piecewise polynomial approximations for nuclear reactor point and space kinetics. Nucl Sci Eng, 1977, 64: 875–901
Goldstein R, Shotkin L M. Use of the prompt-jump approximation in fast-reactor kinetics. Nucl Sci Eng, 1969, 38: 94–103
Chao Y, Attard A. A resolution of the stiffness problem of reactor kinetics. Nucl Sci Eng, 1985, 90: 40–46
Aboanber A E, Hamada Y M. PWS: An efficient code system for solving space-independent nuclear reactor dynamics. Ann Nucl Energy, 2002, 29: 2159–2172
Aboanber A E, Hamada Y M. Power series solution (PWS) of nuclear reactor dynamics with Newtonian temperature feedback. Ann Nucl Energy, 2003, 30: 1111–1122
Sathiyasheela T. Power series solution method for solving point kinetics equations with lumped model temperature and feedback. Ann Nucl Energy, 2009, 36: 246–250
Lawrence R D, Doring J J. A smoothing and extrapolation method for point kinetics. Trans Am Nucl Soc, 1976, 24: 199–201
Aboanber A E. On Padé approximations to the exponential function and application to the point kinetics equations. Prog Nucl Energy, 2004, 44: 347–368
Aboanber A E, Nahla A A. Solution of the point kinetics equations in the presence of Newtonian temperature feedback by Padé approximations via analytical inversion method. J Phys A: Math Gen, 2002, 35: 9609–9627
Li H F, Chen W Z, Luo L, et al. A new integral method for solving the point reactor neutron kinetics equations. Ann Nucl Energy, 2009, 36: 427–432
Zhong S Q, Ren X M, Huang Y Q, et al. Numerical studies on flow and thermal fields in MOCVD reactor. Chinese Sci Bull, 2010, 55: 560–566
Ni J Y, Hao Y, Zhang J C, et al. Effect of reactor pressure on the growth rate and structural properties of GaN films. Chinese Sci Bull, 2009, 54: 2595–2598
Zhao C Z, Xiu X Q, Zhang R, et al. Simulation of growing GaN in vertical HVPE reactor. Sci China Phys Mech Astron, 2010, 53: 72–75
Liu S H, Jiang X B, Zhong Y H, et al. Parameters measurement for the thermal neutron beam in the thermal column hole of Xi’an pulse reactor. Sci China Tech Sci, 2010, 53: 1220–1224
Wu Y L, Hu H S, Zang B P, et al. Penumbral imaging and numerical evaluation of large area source neutron imaging system. Sci China Ser E-Tech Sci, 2009, 52: 2567–2575
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Li, H., Shang, X. & Chen, W. An accurate solution of point kinetics equations of one-group delayed neutrons and an extraneous neutron source for step reactivity insertion. Chin. Sci. Bull. 55, 4116–4119 (2010). https://doi.org/10.1007/s11434-010-4220-2
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DOI: https://doi.org/10.1007/s11434-010-4220-2
