Considering the delay of the fast breeding reactor (FBR) development, it is expected that the light water reactor will still play the main role of the electric power generation in the 2030’s. Accordingly, Toshiba has been developing a new conceptual ABWR as the near-term BWR. We tentatively call it AB1600. The AB1600 has introduced the hybrid active/passive safety system in order to improve countermeasure against severe accident (SA). At the same time, we have made the simplification of the overall plant systems in order to improve economy. The simplification of the AB1600 is based on the proven technologies. To retain the safety performance superior or equivalent to the current ABWR and to strengthen the countermeasure against SA, the AB1600 has introduced the passive systems such as the passive containment cooling system (PCCS), the gravity driven core cooling system (GDCS) and the isolation condenser (IC). While we retain the safety performance superior or equivalent to the current ABWR, we have made the simplification of the safety systems. We could eliminate the high pressure core flooder system (HPCF) and the reactor core isolation system (RCIC) by extending the height of reactor pressure vessel (RPV) two meters. To achieve simplification of reactor systems, we have reduced the number of fuel bundles and the number of control rods by adopting large bundle that has a bundle pitch 1.2 times wider than that of the current ABWR. In the 1600MWe class, the number of fuel bundles could be reduced to 600 from 872 of the current ABWR, and the number of control rods could be reduced to 137 from 205 of the current ABWR. Because the reactor internal pump (RIP) of the current ABWR has sufficient performance capacity and the improvement of fuel characteristics from the current fuel enables the operation at lower core flow, the number of RIPs could be decreased from ten to eight. Furthermore, we have reduced the number of divisions of emergency core cooling system (ECCS)/heat removal system to two from three of the current ABWR. This configuration change contributes to reduce the amount of resources of not only reactor systems but also auxiliary systems. In the previous paper, the AB1600 had four low pressure flooder systems (LPFLs). We have studied about the possibility of reduction of LPFLs to two from four by providing the LPFL with alternative injection lines. This change is expected to contribute to reduce the total number of ECCS pumps and the capacity of emergency AC power.
Skip Nav Destination
14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4244-4
PROCEEDINGS PAPER
The Development of the Evolutionary BWR
M. Nakamaru,
M. Nakamaru
Toshiba Corporation, Yokohama, Japan
Search for other works by this author on:
S. Yokoyama
S. Yokoyama
Toshiba Corporation, Yokohama, Japan
Search for other works by this author on:
A. Murase
Toshiba Corporation, Yokohama, Japan
M. Nakamaru
Toshiba Corporation, Yokohama, Japan
M. Kuroki
Toshiba Corporation, Yokohama, Japan
Y. Kojima
Toshiba Corporation, Yokohama, Japan
S. Yokoyama
Toshiba Corporation, Yokohama, Japan
Paper No:
ICONE14-89441, pp. 835-841; 7 pages
Published Online:
September 17, 2008
Citation
Murase, A, Nakamaru, M, Kuroki, M, Kojima, Y, & Yokoyama, S. "The Development of the Evolutionary BWR." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. Miami, Florida, USA. July 17–20, 2006. pp. 835-841. ASME. https://doi.org/10.1115/ICONE14-89441
Download citation file:
3
Views
Related Proceedings Papers
Related Articles
The Plant Feature and Performance of Double MS (Modular Simplified and Medium Small Reactor)
J. Eng. Gas Turbines Power (January,2010)
Quantitative and Qualitative Comparison of Light Water and Advanced Small Modular Reactors
ASME J of Nuclear Rad Sci (October,2015)
Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design
ASME J of Nuclear Rad Sci (July,2022)
Related Chapters
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Lessons Learned: NRC Experience
Continuing and Changing Priorities of the ASME Boiler & Pressure Vessel Codes and Standards
Source Term Assessments in PSA Level 2 for the Outage Period (PSAM-0168)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)