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2017 | OriginalPaper | Buchkapitel

4. Reactor Calculation Models

verfasst von : Mihály Makai, János Végh

Erschienen in: Reactor Core Monitoring

Verlag: Springer International Publishing

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Abstract

Operation of a nuclear power plant (NPP) uses an extended knowledge on nuclear data, behavior of the neutron gas, heat transfer processes, fluid flow in various extreme circumstances. In the daily work of an NPP the mentioned expertise remains hidden in computer programs. Understanding what may go wrong and why needs knowledge of the mentioned topics. The present chapter is a brief survey of the nuclear data library, neutron transport and diffusion, and thermal hydraulics. The goal is to provide the reader with basic knowledge and references to look up further info.

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Fußnoten
1
Structural elements serve keeping the fuel fixed, to maintain the coolant flow, to operate the regulation organs, etc.
 
2
This surprising simplification works because the wave length or “size” of the neutron is small compared to the path between two collisions and the neutron–neutron collisions may be neglected.
 
3
The number of atoms per unit volume.
 
4
A fraction of neutrons, the delayed neutrons emerging from fission appears with delay, see Sect. 4.4.
 
5
Actually the boundary condition for the entering directions determine the solution.
 
6
Inhour is actually a reactivity unit. It’s the amount of reactivity that gives a stable period of 1 h. It is a highly nonlinear unit (for example a reactivity of 2 h does not lead to a stable period of 30 min.
 
7
A neutron entering a black absorber is absorbed with unit probability.
 
8
There is no absorption in a transparent material.
 
9
During a fuel cycle the \(c_B\) boron concentration decreases and the neutron spectrum hardens. The accumulating fission products also influence the neutron spectrum.
 
10
The first digit equals the last digit of the atomic number, the second digit equals the last digit of the mass number.
 
Literatur
1.
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2.
Zurück zum Zitat Stamm’ler, R.J.J., Abbate, M.J.: Methods of Steady State Reactor Physics in Nuclear Design. Academic Press, London (1983) Stamm’ler, R.J.J., Abbate, M.J.: Methods of Steady State Reactor Physics in Nuclear Design. Academic Press, London (1983)
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4.
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Zurück zum Zitat Bussac, J., Reuss, P.: Traité de Neutronique. Hermann, Paris (1985) Bussac, J., Reuss, P.: Traité de Neutronique. Hermann, Paris (1985)
6.
Zurück zum Zitat Marchuk, G.I., Lebedev, V.I.: Numerical Methods in Neutron Transport Theory. Atomizdat, Moscow (1971). (in Russian)MATH Marchuk, G.I., Lebedev, V.I.: Numerical Methods in Neutron Transport Theory. Atomizdat, Moscow (1971). (in Russian)MATH
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Zurück zum Zitat Makai, M., Kis, D., Végh, J.: Global Reactor Calculation. Bentham, Sharjah (2015) Makai, M., Kis, D., Végh, J.: Global Reactor Calculation. Bentham, Sharjah (2015)
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Zurück zum Zitat Duderstadt, J.J., Martin, W.R.: Transport Theory. Wiley, New York (1979)MATH Duderstadt, J.J., Martin, W.R.: Transport Theory. Wiley, New York (1979)MATH
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Zurück zum Zitat Williams, M.M.R.: Random Processes in Nuclear Reactors. Pergamon Press, Oxford (1974) Williams, M.M.R.: Random Processes in Nuclear Reactors. Pergamon Press, Oxford (1974)
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Zurück zum Zitat Henry, A.F.: Nuclear-Reactor Analysis. MIT Press, Cambridge (1975) Henry, A.F.: Nuclear-Reactor Analysis. MIT Press, Cambridge (1975)
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Zurück zum Zitat Pázsit, I., Demazier, Ch.: Noise techniques in nuclear systems. In: Cacuci, D.G. (ed.) Handbook of Nuclear Engineering. Springer, Berlin (2010). Chap. 14 Pázsit, I., Demazier, Ch.: Noise techniques in nuclear systems. In: Cacuci, D.G. (ed.) Handbook of Nuclear Engineering. Springer, Berlin (2010). Chap. 14
13.
Zurück zum Zitat Pázsit, I., Glöckler, O.: On the neutron noise diagnostics of PWR control rod vibrations III. Application at a power plant. Nucl. Sci. Eng. 99(4), 313–328 (1988) Pázsit, I., Glöckler, O.: On the neutron noise diagnostics of PWR control rod vibrations III. Application at a power plant. Nucl. Sci. Eng. 99(4), 313–328 (1988)
14.
Zurück zum Zitat Szatmáry, Z.: Introduction to Reactor Physics. Akadémiai Kiadó, Budapest (2000). (in Hungarian) Szatmáry, Z.: Introduction to Reactor Physics. Akadémiai Kiadó, Budapest (2000). (in Hungarian)
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Zurück zum Zitat Babuska, I., Tempone, R., Zouraris, G.E.: Galerkin finite element approximation of stochastic elliptic partial differential equations. SIAM J. Numer. Anal. 42, 800 (2004)MathSciNetCrossRefMATH Babuska, I., Tempone, R., Zouraris, G.E.: Galerkin finite element approximation of stochastic elliptic partial differential equations. SIAM J. Numer. Anal. 42, 800 (2004)MathSciNetCrossRefMATH
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Zurück zum Zitat Hoogenboom, J.E., Ivanov, A., Sanchez, V. Diop, C.: A flexible coupling scheme for Monte Carlo and thermal-hydraulics codes. International conference on mathematics, computational methods and reactor physics, (M & C 2009), Saratoga Springs, New York, May 3–7 (2009) Hoogenboom, J.E., Ivanov, A., Sanchez, V. Diop, C.: A flexible coupling scheme for Monte Carlo and thermal-hydraulics codes. International conference on mathematics, computational methods and reactor physics, (M & C 2009), Saratoga Springs, New York, May 3–7 (2009)
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Zurück zum Zitat Sanchez, V., Al-Hamry, A.: Development of coupling scheme between MCNP and COBRA-TF for the prediction of the pin power of a PWR fuel assembly. International conference on mathematics, computational methods and reactor physics, (M & C 2009), Saratoga Springs, New York, May 3–7 (2009) Sanchez, V., Al-Hamry, A.: Development of coupling scheme between MCNP and COBRA-TF for the prediction of the pin power of a PWR fuel assembly. International conference on mathematics, computational methods and reactor physics, (M & C 2009), Saratoga Springs, New York, May 3–7 (2009)
19.
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Metadaten
Titel
Reactor Calculation Models
verfasst von
Mihály Makai
János Végh
Copyright-Jahr
2017
DOI
https://doi.org/10.1007/978-3-319-54576-9_4