MSIV closure ATWS mitigation of SBWR with the standby liquid control system
Conference
·
OSTI ID:10180191
An Anticipated Transient Without Scram (ATWS) initiated by inadvertent closure of the Main Stream Isolation Valve has been analyzed using the RAMONA-4B code of Brookhaven Laboratory (1994). The Simplified Boiling Water Reactor (SBWR) operating in natural circulation is designed with many passive safety features. This analysis demonstrates the effectiveness of the heat-removal system during an ATWS, followed by shut down of the reactor through injection of boron into the reactor core from the Standby Liquid Control System (SLCS).
- Research Organization:
- Brookhaven National Lab., Upton, NY (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 10180191
- Report Number(s):
- BNL-NUREG--60751; CONF-941142--19; ON: DE94018433
- Country of Publication:
- United States
- Language:
- English
Similar Records
Anticipated transient without scram analysis of the simplified boiling water reactor following main steam isolation valve closure with boron injection
Analysis of a typical BWR/4 MSIV closure ATWS using RAMONA-3B and TRAC-BD1 codes
RAMONA-4B development for SBWR safety studies
Journal Article
·
Mon Jul 01 00:00:00 EDT 1996
· Nuclear Technology
·
OSTI ID:276534
Analysis of a typical BWR/4 MSIV closure ATWS using RAMONA-3B and TRAC-BD1 codes
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6715018
RAMONA-4B development for SBWR safety studies
Conference
·
Thu Dec 30 23:00:00 EST 1993
·
OSTI ID:10136624