Top page > Learn(History/Science) > Toshiba Firsts of Their Kind > Completion of the first Advanced Boiling Water Reactor

Completion of the first Advanced Boiling Water Reactor

Development and construction of ABWR facilities brings together the essence of the latest technologies.
ABWRs will be the mainstay light water reactors in the 21st century.

Tokyo Electric Power Company’s as Kashiwazaki-Kariwa Nuclear Power Plants Unit 6 and 7
Tokyo Electric Power Company’s as Kashiwazaki-Kariwa Nuclear
Power Plants Unit 6 and 7

In 1975, an industry-wide framework was established for an advanced boiling water reactor (ABWR). Under this framework, Toshiba cooperated with power companies to investigate the feasibility of a Reactor Internal Pump (RIP), a major component of the ABWR, contributing to the successful start of an ABWR development project.

In 1978, an international collaborative team, which consisted of the world BWR manufactures including General Electric (GE), Hitachi and Toshiba, began conceptual designs of the ABWR. Additionally, Toshiba participated in government-sponsored studies and a number of joint research projects with power companies to complete development testing and baseline design.

Consequently, the first ABWRs were adopted in Tokyo Electric Power Company's as Kashiwazaki-Kariwa Nuclear Power Plants Unit 6 and 7.

Toshiba represented the international joint venture, which consisted of GE, Hitachi and Toshiba, to put together the construction project for Unit 6, the first ABWR plant.

Unit 6 and 7 entered commercial operation in November 1996 and July 1997, respectively.

Since then, Toshiba has constructed several ABWR plants in Japan and is highly acclaimed by power companies around the world. In the United States, the ABWR plant design has obtained a standard design certification (SDC) from the U.S. Nuclear Regulatory Commission (NRC).

Toshiba's major technological contributions to the development of ABWR include the following;

To simplify piping interfaces for improved safety, reactor internal pumps (RIP) for control of core flow are directly mounted inside the reactor pressure vessel. The RIPs make it possible to do away with the external recirculation loop and jet pumps in former BWR plants. This eliminates the possibility of external pipe ruptures, enhancing the safety of a nuclear reactor and thus making it possible to reduce the capacity required for the emergency core cooling system (ECCS).

To reduce the per-kWh electricity cost, the ABWR is designed to provide larger power capacity and improved thermal efficiency. Therefore the ABWR has a rated output of about 1,350MW. To produce a large amount of power with higher efficiency, the ABWR uses a highefficiency turbine with 52-inch blades and a reheating cycle.

The fine motion control rod drive (FMCRD) is used to control the output of a nuclear power reactor. It slowly adjusts the positions of control rods using electric motors under normal conditions, while allowing for fast control rod adjustment using a hydraulic-driven system in the event of emergencies. The FMCRD controls the positions of multiple control rods simultaneously to shorten start-up time and is equipped with diverse drive source to improve reliability.

The ABWR uses a reinforced-concrete containment vessel (RCCV) integrated with a reactor building. This enhances economic efficiency by reducing the amount of steel materials and improving their structural utilization. It also helps to shorten the construction period because it allows simultaneous construction of the reactor building and RCCV. Additionally, the ABWR ensures higher seismic resistance by lowering the centers of gravity of the pressure vessel, RCCV and reactor building.

The ABWR fully utilizes state-of-the-art digital control systems such as digital instrumentation and control systems and optical multiplexing communication systems. The comprehensive digital control systems interconnected the main control panels and on-site equipment through an optical network to provide enhanced capabilities for efficient and safe operation of the plant.

Toshiba will continue to employ leading-edge technologies to further improve ABWRs so as to realize nuclear power plants with excellent safety, reliability, economic efficiency, operability, and maintainability.

Internal pump high-temperature, high-pressure testing device

Internal pump high-temperature, high-pressure testing device

RCCV seismic resistance verification test

RCCV seismic resistance verification test

Related Links

Learn (History/Science) Top Page

Toshiba Science Museum
2F Lazona Kawasaki Toshiba Bldg., 72-34, Horikawa-Cho, Saiwai-Ku, Kawasaki 212-8585, Japan
TEL. 044-549-2200

To Top