Abstract
Usually, the one-point core dynamic approximation model can be expressed by the following equation system
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Bibliography
Suda N (1969) Nuclear reactor kinetics and control. Dobunshoin, Tokyo
Ash M (1965) Nuclear reactor kinetics. McGraw-Hill, New York
Yoshikawa T (2004) Classic control theory. Shokodo, Tokyo
Enomoto, Tanabe et al (1985) The boiling water reactor: recent knowledge and forward perspective for stability. J. At. Energy Soc. Jpn 27(10):890–903
Anegawa, Ebata et al (1996) Recent topics relating to the BWR thermal-hydraulic stability. J. At. Energy Soc. Jpn 38(5):348–356
Takigawa Y et al (1987) Caorso limit cycle oscillation analysis with three-dimensional transient code TOSDYN-2. Nucl Technol 79:210–227
Nariai H et al (2001) Atomic Energy Society of Japan: “Present situation and issues for BWR thermal-hydraulic stability assessment”
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Chapter 6 Exercises
Chapter 6 Exercises
- 1.
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2.
Prove that the exact equilibrium of (6.1) does not exist if the neutron source exists and the core is in critical state.
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3.
Derive (6.11).
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4.
Derive approximate (6.13a)–(6.13d) for the critical reactor.
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5.
Draw a block diagram of high-output reactor having the negative feedback output and determine its transfer function. The output coefficient is denoted by α [$/MW].
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6.
Select appropriate terminologies from the bottom list and complete the following sentences for a BWR.
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(1)
The channel stability of BWR plant is based on (<1>). When the channel inlet flow changes, the feedback is made to maintain the (<2>) between the top and bottom plenums to be fixed. Because the channel inlet flow is tried to be returned to the original rate, the oscillation occurs.
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(2)
The core stability is mainly based on (<3>). When the output is changed, the reactivity by the change of (<4>) in the core is fed back. Because the output is tried to return to the original level, the oscillation occurs.
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(3)
The area stability is a combination of effects of (<5>) and (<6>). If a thermal-hydraulically unstable channel exists around the core, the (<7>) which is normally attenuated quickly can thermal-hydraulically excite the oscillation. This oscillation continues and the area becomes unstable.
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(4)
In the BWR, if the (<8>) status occurs, the stability tends to drop. To solve this, the system is provided to drop the output by inserting (<9>) after trip of recirculation pump.
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(1)
nuclear characteristics, high-output and low core flow, voids, subcriticality, selective control rods, pressure loss, thermo-hydraulic characteristics, high-order mode
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7.
Derive (6.33).
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Suzuki, K., Ono, H., Miyake, S. (2013). Reactor Stability Study. In: Oka, Y., Suzuki, K. (eds) Nuclear Reactor Kinetics and Plant Control. An Advanced Course in Nuclear Engineering. Springer, Tokyo. https://doi.org/10.1007/978-4-431-54195-0_6
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