Abstract
The behavior of the nuclear reactor in response to any sudden change in reactivity is very important for reactor control. Positive reactivity insertions causes power excursion and could have a destructive impact on the reactor core. The aim of the study is to investigate the safety features of a material test reactor (MTR) during reactivity transient with emphasis on the capability of the mathematical modeling using programming language. Therefore a mathematical model using Python3.6; high-level programming language is developed to solve the point kinetic equations taking into account Doppler and moderator feedback effects. The model is validated with AIREKMOD_RR; point kinetic computer code for reactivity transient analysis in nuclear research reactors. The results of the Python model demonstrate the inherent safety features of the MTR reactor. Also, there is good agreement between the results of the Python model and AIREKMOD_RR code, illustrating the efficiency of the Python model in simulating the behavior of the reactor core under reactivity transient.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: None declared.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
The differential equations in our model are implemented as system differential equations that are solved simultaneously in Python with the “Scipy. Integrate” package using function odeint
y = odeint(model, y0, t)
The function odeint requires the following three inputs:
model: Function name that returns derivative values at requested y and t values as dydt = model(y, t)
y0: Initial conditions of the differential states
t: Time points at which the solution should be reported.
The system equations are represented as follow:
References
Caia, X., Langtangen, H.P., and Moe, H. (2005). On the performance of the python programming language for serial and parallel scientific computations. Sci. Program. 13: 619804, https://doi.org/10.1155/2005/619804.Search in Google Scholar
Heinold, B. (2012). A practical introduction to Python programming. Department of Mathematics and Computer Science Mount St. Mary’s University, Los Angeles.Search in Google Scholar
Hetrick, D. (1971). Dynamics of nuclear reactors. University of Chicago Press, Chicago and London.Search in Google Scholar
International Atomic Energy Agency (2008). Safety analysis for research reactors, safety reports series no. 55. IAEA Publication, Vienna.Search in Google Scholar
International Atomic Energy Agency (2016). Safety of research reactors, safety standards series no. SSR-3. IAEA Publication, Vienna.Search in Google Scholar
Kinard, M. and Allen, E.J. (2004). Efficient numerical solution of the point kinetics equations in nuclear reactor dynamics. Ann. Nucl. Energy 31: 1039–1051, https://doi.org/10.1016/j.anucene.2003.12.008.Search in Google Scholar
Lewis, E. (1977). Nuclear power reactor safety. John Wiley & Sons, New York.Search in Google Scholar
Mohamed, F. (2011). Analysis of reactivity accidents in MTR for various protection system parameters and core conditions, Ph.D. thesis. Alexandria University Press, Alexandria.Search in Google Scholar
Nuclear Energy Agency Data Bank (1993). AIREKMOD_RR - a point kinetic computer code for reactivity transient analysis in nuclear research reactors. User guide & validation/benchmarking. Organization for Economic Co-operation and Development, Paris.Search in Google Scholar
Petersen, C., Dulla, S., Vilhena, M., and Ravetto, P. (2011). An analytical solution of the point kinetics equations with time-variable reactivity by the decomposition method. Prog. Nucl. Energy 53: 1091–1094, https://doi.org/10.1016/j.pnucene.2011.01.001.Search in Google Scholar
Upadhyay, R., Dutta, G., Singh, M., Bera, D., and Srivastava, N. (2014). A numerical solution of the point kinetics equations and its validation. Math. Sci. Int. Res. J. 3: 993–1005.Search in Google Scholar
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Articles in the same Issue
- Frontmatter
- Single-phase flow heat transfer characteristics in helically coiled tube heat exchangers
- Design and optimization of an integrated gamma ray scanning system for the uranium sample
- Numerical simulation of the effect of rod bowing on critical heat flux
- Flow and heat transfer characteristics of a nanofluid as the coolant in a typical MTR core
- Mathematical modeling of point kinetic equations with temperature feedback for reactivity transient analysis in MTR
- An enhanced formalism for the inverse reactor kinetics problem
- The establishment of analysis methodology of NRCDose3 for Kuosheng nuclear power plant decommissioning
- Analysis of SMART reactor core with uranium mononitride for prolonged fuel cycle using OpenMC
- Conceptual design of an innovative I&XC fuel assembly for a SMR based on neutronic/thermal-hydraulic calculations at the BOC
- Optimized fractional-order PID controller based on nonlinear point kinetic model for VVER-1000 reactor
- High rate X-ray radiation shielding ability of cement-based composites incorporating strontium sulfate (SrSO4) minerals
- Vibration analysis for predictive maintenance and improved reliability of rotating machines in ETRR-2 research reactor
- Calendar of events