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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Notes
- 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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Makai, M., Végh, J. (2017). Description of Core Power Distribution. In: Reactor Core Monitoring. Lecture Notes in Energy, vol 58. Springer, Cham. https://doi.org/10.1007/978-3-319-54576-9_3
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