Abstract
The boiling water reactor (BWR) is divided into two main systems: the nuclear steam supply system (NSSS) that generates steam, and the turbine system (or turbine island) that uses the stream to rotate turbo-generator and generate electric power. The NSSS consists of various subsystems and equipments. They include basically the reactor pressure vessel that houses fuel, control rods, and other nuclear reactor equipments, a reactor auxiliary system that handles circulation of coolant, generated steam, and feed water returned from turbines, the engineered safety features that are required for securing safety, and a reactor auxiliary system that is required for operating the plant. The fuel handling and storage equipment, the instrumentation and control system, and the electrical system, as well as the radioactive waste treatment system that is unique to nuclear power station are also included in the NSSS. The turbine system consists mainly of turbines, generators, the condenser that condenses steam, the feed-water system that resupplies the reactor with the condensate. Figure 7.1 shows the overview configuration of BWR systems.
An erratum to this chapter can be found at http://dx.doi.org/10.1007/978-4-431-54195-0_12
This is a preview of subscription content, log in via an institution to check access.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Bibliography
Atomic Energy Society of Japan (1984) C43 BWR power plant daily power adjusting operation (1). Results of continuous operation in various mode. In: Proceedings of the 1984 conference, Higashi-Osaka, Japan
Atomic Energy Society of Japan (1986) E33 Kinetics of full capacity turbine bypass plant. In: Proceedings of the 1986 conference, Kyoto, Japan
Fukushima Daiichi Nuclear Power Station (1992) License application for nuclear power plant (complete copy of plant no. 5), body and attachment (attachment 8 and attachment 10) (Aug 1992)
Tomisawa T, Tone Y, Fujii M (1997) Electrical, instrumentation and control system of advanced boiling water reactor (ABWR). Toshiba Rev 52(4):20–23
Author information
Authors and Affiliations
Editor information
Editors and Affiliations
Chapter 7 Exercises
Chapter 7 Exercises
-
1.
The critical operation for staring and stopping the plant is to change the reactor power. Name 3 systems used for monitoring or maintaining integrity of the fuel during the operation.
-
2.
Name 2 means for controlling reactivity for maintaining constant power at rated operation of the BWR.
-
3.
Give 3 major moderation functions for preventing the reactor power from rising when an event occurs that the reactor power rises excessively.
-
4.
Give 2 major moderation functions for preventing the reactor pressure from rising when an event occurs that the reactor pressure rises excessively.
-
5.
The central control panel of the first generation had been improved and the third-generation central control panel is currently being used. Give 2 purposes of the control panel what is improved for the operators.
-
6.
Give 2 display functions equipped with the large-size display panel of the third-generation central control panel for sharing information among operators.
Rights and permissions
Copyright information
© 2013 Springer Japan
About this chapter
Cite this chapter
Kondo, K., Ota, Y., Ono, H., Kuroki, M., Koshi, Y., Tahira, M. (2013). Actual Operation Control of Boiling Water Reactor. 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_7
Download citation
DOI: https://doi.org/10.1007/978-4-431-54195-0_7
Published:
Publisher Name: Springer, Tokyo
Print ISBN: 978-4-431-54194-3
Online ISBN: 978-4-431-54195-0
eBook Packages: EnergyEnergy (R0)