Two types of a passive safety containment for a near future BWR with active and passive safety systems
- 1. Toshiba Corporation, IEC, Gen-SS, 8, Shinsugita-ho, Isogo-ku, Yokohama (Japan)
Description
The paper presents two types of a passive safety containment for a near future BWR. They are named Mark S and Mark X containment. One of their common merits is very low peak pressure at severe accidents without venting the containment atmosphere to the environment. The PCV pressure can be moderated within the design pressure. Another merit is the capability to submerge the PCV and the RPV above the core level. The third merit is robustness against external events such as a large commercial airplane crash. Both the containments have a passive cooling core catcher that has radial cooling channels. The Mark S containment is made of reinforced concrete and applicable to a large power BWR up to 1830 MWe. The Mark X containment has the steel secondary containment and can be cooled by natural circulation of outside air. It can accommodate a medium power BWR up to 1380 MWe. In both cases the plants have active and passive safety systems constituting in-depth hybrid safety (IDHS). The IDHS provides not only hardware diversity between active and passive safety systems but also more importantly diversity of the ultimate heat sinks between the atmosphere and the sea water. Although the plant concept discussed in the paper uses well-established technology, plant performance including economy is innovatively and evolutionally improved. Nothing is new in the hardware but everything is new in the performance.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2009.03.004Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2009.03.004;
- PII
- S0029-5493(09)00139-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 239
- Journal Issue
- 9
- Journal Page Range
- p. 1682-1692
- ISSN
- 0029-5493
- CODEN
- NEDEAU
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE 15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya (Japan)
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 41010337
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONTAINMENT; CONTROL ELEMENTS; DESIGN BASIS ACCIDENTS; ECCS; FISSION PRODUCTS; HEAT SINKS; LOSS OF COOLANT; PRESSURE RANGE MEGA PA 10-100; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; RCIC SYSTEMS; REACTOR SAFETY; REINFORCED CONCRETE; RHR SYSTEMS; SEAWATER; STEELS; VALVES
- Descriptors DEC
- ACCIDENTS; ALLOYS; BUILDING MATERIALS; CALCULATION METHODS; CARBON ADDITIONS; COMPOSITE MATERIALS; CONCRETES; CONTAINERS; CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; HYDROGEN COMPOUNDS; IRON ALLOYS; IRON BASE ALLOYS; ISOTOPES; MATERIALS; OXYGEN COMPOUNDS; POWER REACTORS; PRESSURE RANGE; PRESSURE RANGE MEGA PA; RADIOACTIVE MATERIALS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; REINFORCED MATERIALS; REMOVAL; SAFETY; SINKS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2009 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.