Station blackout analysis for AHWR using CATHARE
- 1. Reactor Design and Development Group, Bhabha Atomic Research Centre, Mumbai (India)
Description
The strong earthquake followed by Tsunami, a low frequency and high-consequence natural disaster, at Fukushima has shaken the world's faith in nuclear energy. The new reactor design around the world has started looking ways to mitigate this scenario with innovative design features whereas every nuclear country has started reviewing their existing reactor response to this scenario and minimize the consequences or limit the damage progression. India has designed an advanced reactor concept i.e. Advanced Heavy Water Reactor (AHWR). This reactor has many passive design features to mitigate the consequences for not only the postulated design basis events but also for beyond design basis events. During station blackout scenario leading to hot shutdown, the Isolation Condensers (ICs) are intended to remove decay heat with the help of overhead large pool of water ie. Gravity Driven Water Pool (GDWP). This paper outlines the assessment of station blackout scenario for AHWR using last version of French best estimate computer code CATHARE2. First, it explains the modeling of main heat transport system of AHWR and isolation Condenser loop along with GDWP in CATHARE followed by thermal hydraulic safety assessment of station blackout scenario. (author)
Additional details
Publishing Information
- Publisher
- Bhabha Atomic Research Centre
- Imprint Place
- Mumbai (India)
- Imprint Title
- Proceedings of the international workshop on new horizons in nuclear reactor thermal hydraulics and safety
- Imprint Pagination
- 91 p.
- Journal Page Range
- [14 p.]
Conference
- Title
- international workshop on new horizons in nuclear reactor thermal hydraulics and safety
- Acronym
- IW-NRTHS 2014
- Dates
- 13-15 Jan 2014
- Place
- Mumbai (India)
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 45080300
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; C CODES; DESIGN; HWLWR TYPE REACTORS; NATURAL CONVECTION; OUTAGES; PRESSURE TUBES; REACTOR COOLING SYSTEMS; THERMAL HYDRAULICS
- Descriptors DEC
- COMPUTER CODES; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; HEAVY WATER MODERATED REACTORS; HYDRAULICS; MASS TRANSFER; MECHANICS; REACTOR COMPONENTS; REACTORS; REMOVAL; TUBES; WATER COOLED REACTORS
Optional Information
- Notes
- 20 refs., 22 figs.