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Published in:
Reactor Safety Goals Read chapter Read first chapter

2017 | OriginalPaper | Chapter

3. Description of Core Power Distribution

Authors : Mihály Makai, János Végh

Published in: Reactor Core Monitoring

Publisher: Springer International Publishing

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Abstract

In Chap. 2, we have seen that reactor operation should keep the reactor state within given limits. Such limits have been formulated in (2.​104), (2.​105) and (2.​106). The present Chapter endeavors coining methods to determine the quantities limited by the mentioned equations. To this end we may use elaborated measurements and the attached calculations. A goal of limitations is to check local heat generation or the local power release. By means of measurements and calculations we have to derive an estimated value for each quantity subjected to limitation. We also estimate the uncertainty of the safety parameters. We investigate the main models forming the basis of reactor operation. The mentioned models are discussed in more details in Chap. 4.

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previous chapter Core Monitoring
next chapter Reactor Calculation Models
Footnotes
1
A nucleus containing more than 200 neutrons and protons.
 
2
Stationary solution is constant in time thus the left-hand side of (3.14) is identically zero.
 
3
This is the case with the upper boundary of the core. There cables, motors, and other technical utensils are in an irregular arrangement. Nobody will give the isotope composition of such a volume.
 
4
In the sixties “multigroup” meant 6–16 energy groups, see [2].
 
5
We present calculations with space points above 200.
 
6
f is the ratio thermal neutrons absorbed by the fuel divided by the total number of neutrons absorbed.
 
7
In the laboratory coordinate system.
 
8
In thermal hydraulics the term control element is also used.
 
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Nikolaev, M.N., Ryazanov, B.G., Savoskin, M.M., Tzibulya, A.M.: Multigroup Approach in the Theory of Neutron Transport. Energoatomizdat, Moscow (1984). (in Russian)
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IAEA Safety Standard Series No. GS-G-2.2, IEAE, Vienna, Chapter 6. Limits and conditions for normal operation; Chapter 7. Surveillance requirements and chapter 10. Compliance with operational limits and conditions and operating procedures (2000)
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Ronen, Y. (ed.): CRC Handbook of Nuclear Reactors Calculations, vol. I. CRC, Boca Raton (1986)
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Becker, R., Gadó, J., Kereszturi, A., Pshenin, V.: Asymptotic approximations and their place in WWER core analysis. In: Theoretical Investigations of the Physical Properties of WWER-Type Uranium-Water Lattices, vol. 2. Akadémiai Kiadó, Budepst (1994)
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Habetler, G.J., Martino, M.A.: Existence theorems and spectral theory for the multigroup diffusion model. In: Nuclear Theory, pp. 127–139. AMS (1961)
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Deniz, V.V.: The theory of neutron leakage in reactor lattices. In: CRC Handbook of Nuclear Reactors Calculations, vol. II, pp. 409–508. CRC (1986)
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Metadata
Title
Description of Core Power Distribution
Authors
Mihály Makai
János Végh
Copyright Year
2017
Book
Reactor Core Monitoring

Print ISBN: 978-3-319-54575-2

Electronic ISBN: 978-3-319-54576-9

Copyright Year: 2017

DOI
https://doi.org/10.1007/978-3-319-54576-9_3