iB1350 stands for an innovative, intelligent and inexpensive BWR 1350. The iB1350 uses innovative passive containment cooling system (iPCCS). The iPCCS is a part of the in-containment filtered venting system (IFVS). The vent pipe is submerged in the IFVS tank in the outer well (OW) of the Mark W containment. The conventional PCCS has a suction pipe only from the dry well (DW). On the contrary, the iPCCS has two suction pipes. One is normally opened to the wet well (WW) and another normally closed to the DW. The suction pipe in the conventional design cannot be connected to the WW because the PCCS vent pipe is connected to the WW. A PCCS functions using differential pressure between two nodes to discharge noncondensable gases in a PCCS heat exchanger (Hx). A suction pipe and a vent pipe must be connected to different nodes to use differential pressure. Therefore, the conventional PCCS never can cool the S/P. Although the S/P is the in-containment heat sink, heat up of the S/P is the most unfavorable for the conventional PCCS. In order to use the PCCS the conventional design must discharge steam directly into the DW instead of the S/P. Therefore, the conventional PCCS must open depressurization valves (DPV) at a SBO if the isolation condenser (IC) fails. On the contrary, the iPCCS can cool the S/P directly using the suction pipe connected to the WW and without DPV. Instead of DPV the iB1350 has modulating valves (MV) of which discharge lines are submerged in the S/P. Even if the IC fails during a SBO, the iB1350 can cool the core using the severe accident feedwater system (SAFWS), the SRV or the MV, and the iPCCS. The SAFWS makes up the core. The decay heat is carried by steam to the S/P through the SRV or the MV. The S/P works as in-containment heat sink. Once the S/P starts boiling the iPCCS automatically initiates cooling of the steam from the S/P. In the case of a core melt accident, a certain amount of FP is released into the S/P and heats up the S/P. Once the S/P starts boiling, the noncondensable gases in the WW is purged by the steam into the DW and then into the PCCS Hx. In order to purge the stagnant gases, the conventional PCCS needs an active fan in the long term. On the contrary, the iPCCS can easily purge noncondensable gases in the heat exchanger using differential pressure to the OW and need not any active fan even in the long term.
Skip Nav Destination
2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5002-2
PROCEEDINGS PAPER
iB1350: Innovative Passive Containment Cooling System for the iB1350 Available to Purchase
Takashi Sato,
Takashi Sato
Toshiba Corporation, Yokohama, Japan
Search for other works by this author on:
Keiji Matsumoto,
Keiji Matsumoto
Toshiba Corporation, Yokohama, Japan
Search for other works by this author on:
Nobuhiro Hara
Nobuhiro Hara
Toshiba Corporation, Yokohama, Japan
Search for other works by this author on:
Takashi Sato
Toshiba Corporation, Yokohama, Japan
Keiji Matsumoto
Toshiba Corporation, Yokohama, Japan
Nobuhiro Hara
Toshiba Corporation, Yokohama, Japan
Paper No:
ICONE24-60919, V002T06A039; 9 pages
Published Online:
October 25, 2016
Citation
Sato, T, Matsumoto, K, & Hara, N. "iB1350: Innovative Passive Containment Cooling System for the iB1350." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues. Charlotte, North Carolina, USA. June 26–30, 2016. V002T06A039. ASME. https://doi.org/10.1115/ICONE24-60919
Download citation file:
10
Views
Related Proceedings Papers
Safety Assurance for Boiling Water Reactors (BWRs) Beyond Design Basis
ICONE20-POWER2012
Related Articles
Analyses of Feedwater Trip With SBO Sequence of VVER1000 Reactor
ASME J of Nuclear Rad Sci (October,2016)
Computational Fluid Dynamics Analysis and Structural Safety Assessment of a Mitigation Device to Minimize Consequence of a Containment Bypass Nuclear Accident
J. Pressure Vessel Technol (April,2021)
The Separation of Dissolved Gases From Water
Trans. ASME (January,1920)
Related Chapters
Engineering and Physical Modeling of Power Plant Cooling Systems
Thermal Power Plant Cooling: Context and Engineering
Lay-Up and Start-Up Practices
Consensus on Operating Practices for Control of Water and Steam Chemistry in Combined Cycle and Cogeneration
Outlook
Closed-Cycle Gas Turbines: Operating Experience and Future Potential