Simple evaluation model for long term debris transport velocity in the torus of a mark I containment
Description
After the Barsebaeck 2 strainer clogging incident from 28 July 1992, a first review of the design features of a Mark I containment and the thermal insulation typically employed revealed a potential for the transportation of larger amounts of insulation into the wet-well (torus) of the containment during a LOCA. Although Switzerland took a quick decision to increase the strainers of all BWRs till the end of 1993 (as it was performed by the Swiss Utilities) for the meantime it was necessary to develop tools for assessing the effectiveness of accident management actions proposed by the utilities for the existing (old strainer) design. Among others tools a simple evaluation model for assessing the transport velocity of insulation debris caused by the suction of operating strainers was developed, which was applied for a BWR with a Mark I containment and can as well be applied for sump pool conditions of a PWR (submerged sump strainers). (author)
Additional details
Publishing Information
- Publisher
- Organisation for Economic Co-Operation and Development - Nuclear Energy Agency
- Imprint Place
- Paris (France)
- ISBN
- 92-64-00666-4
- Imprint Title
- Debris impact on emergency coolant recirculation
- Imprint Pagination
- 418 p.
- Journal Page Range
- p. 263-269
Conference
- Title
- Workshop on debris impact on emergency coolant recirculation
- Dates
- 25-27 Feb 2004
- Place
- Albuquerque, NM (United States)
INIS
- Country of Publication
- France
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 36010668
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CONTAINMENT SPRAY SYSTEMS; CONTAINMENT SYSTEMS EXPERIMENT; ECCS; EVALUATION; FLUID FLOW; REACTOR SAFETY; THERMAL INSULATION; VELOCITY
- Descriptors DEC
- CONTAINMENT; CONTAINMENT SYSTEMS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR PROTECTION SYSTEMS; REACTOR SAFETY EXPERIMENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS