iB1350 no2. Level 1 PRA for optimization of safety systems of the iB1350
- 1. Toshiba Corp., Isogo Nuclear Engineering Center (IEC), Yokohama, Kanagawa (Japan)
Description
Crediting the iB1350 (innovative, intelligent, and inexpensive BWR 1350) reactor's passive safety systems in DBA analyses allows optimization of its overall safety system configuration. This paper compares the 2 new optimized configurations described in the series paper no.1 for the iB1350 in ICAPP2017 and they are expected to enhance safety and reliability while reducing cost from the original design. Safety system configuration can be further optimized since the iB1350's innovative passive containment cooling system (iPCSS) has greater decay heat removal capability than the conventional PCCS. While the conventional PCCS cannot cool the suppression pool, the iPCCS can. This makes it possible to cool the core and the containment using only core injection systems and the iPCCS without the conventional active RHR systems. The iPCCS can replace some of the conventional active RHR systems. Additionally, divisions without RHR systems can use a dedicated air-cooled component cooling system and a gas turbine generator rather than a reactor sea water cooling system and a diesel generator. This optimization enhances system and power diversity. To analytically compare these safety system configurations, a Level 1 Internal Events Probabilistic Risk Assessment (PRA) has been performed for each configuration. While the two optimized configurations each remove two RHR systems, crediting iPCCS and enhanced power diversity result in excellent performance for the overall CDF. (author)
Additional details
Publishing Information
- Imprint Title
- Proceedings of 2017 international congress on advances in nuclear power plants (ICAPP2017)
- Imprint Pagination
- 2573 p.
- Journal Page Range
- 12 p.
Conference
- Title
- 2017 international congress on advances in nuclear power plants
- Acronym
- ICAPP2017
- Dates
- 24-25 Apr 2017; 26-28 Apr 2017
- Place
- Fukui (Japan); Kyoto (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 49024740
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- AFTER-HEAT REMOVAL; BWR TYPE REACTORS; CONTAINMENT BUILDINGS; CONTAINMENT SPRAY SYSTEMS; ISOLATION CONDENSERS; POWER SUPPLIES; PRESSURE VESSELS; PROBABILISTIC ESTIMATION; REACTOR DESIGN; REACTOR SAFETY; REACTOR VESSELS; RISK ASSESSMENT; SEVERE ACCIDENTS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BUILDINGS; CALCULATION METHODS; CONTAINERS; CONTAINMENT; CONTAINMENT SYSTEMS; DESIGN; ELECTRONIC EQUIPMENT; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; EQUIPMENT; POWER REACTORS; REACTOR LIFE CYCLE; REACTORS; REMOVAL; SAFETY; STEAM CONDENSERS; THERMAL REACTORS; VAPOR CONDENSERS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Available as CD-ROM Data in PDF format. Folder Name: pdf; Paper ID: 17253.pdf; 21 refs., 6 figs., 4 tabs.