Anticipated transient without scram analysis of the simplified boiling water reactor following main steam isolation valve closure with boron injection
Journal Article
·
· Nuclear Technology
OSTI ID:276534
- Brookhaven National Lab., Upton, NY (United States). Dept. of Advanced Technology
The simplified boiling water reactor (SBWR) operating in natural circulation is designed with many passive safety features. An anticipated transient without scram (ATWS) initiated by inadvertent closure of the main steam isolation valve (MSIV) in an SBWR has been analyzed using the RAMONA-4B code of Brookhaven National Laboratory. This analysis demonstrates the predicted performance of the SBWR during an MSIV closure ATWS, followed by shutdown of the reactor through injection of boron into the reactor core from the standby liquid control system.
- OSTI ID:
- 276534
- Journal Information:
- Nuclear Technology, Journal Name: Nuclear Technology Journal Issue: 1 Vol. 115; ISSN 0029-5450; ISSN NUTYBB
- Country of Publication:
- United States
- Language:
- English
Similar Records
MSIV closure ATWS mitigation of SBWR with the standby liquid control system
Influence of isolation condensers on boiling water reactor performance during an anticipated transient without scram
A long-term MAAP 3. 0B analysis of a severe anticipated transient without scram accident in a boiling water reactor
Conference
·
Thu Sep 01 00:00:00 EDT 1994
·
OSTI ID:10180191
Influence of isolation condensers on boiling water reactor performance during an anticipated transient without scram
Journal Article
·
Tue Jan 31 23:00:00 EST 1995
· Nuclear Technology
·
OSTI ID:109967
A long-term MAAP 3. 0B analysis of a severe anticipated transient without scram accident in a boiling water reactor
Journal Article
·
Thu Oct 01 00:00:00 EDT 1992
· Nuclear Technology; (United States)
·
OSTI ID:6933322