Pressurized-water-reactor station blackout
Conference
·
OSTI ID:5624652
The purpose of the Severe Accident Sequence Analysis (SASA) Program was to investigate accident scenarios beyond the design basis. The primary objective of SASA was to analyze nuclear plant transients that could lead to partial or total core melt and evaluate potential mitigating actions. The following summarizes the pressurized water reactor (PWR) SASA effort at the Idaho National Engineering Laboratory (INEL). The INEL is presently evaluating Unresolved Safety Issue A-44 - Station Blackout from initiation of the transient to core uncovery. The balance of the analysis from core uncovery until fission product release is being performed at Sandia National Laboratory (SNL). The current analyses involve the Bellefonte Nuclear Steam Supply System (NSSS), a Babcock and Wilcox (B and W) 205 Fuel Assembly (205-FA) raised loop design to be operated by the Tennessee Valley Authority (TVA).
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5624652
- Report Number(s):
- EGG-M-20083; CONF-8310143-39; ON: DE84002205
- Country of Publication:
- United States
- Language:
- English
Similar Records
Thermal-hydraulic and core damage analysis of the station blackout transient in pressurized water reactors
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Applications of the RELAP5 code to the station blackout transients at the Browns Ferry Unit One Plant
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:6315107
SCDAP severe core-damage studies: BWR ATWS and PWR station blackout
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:5624615
Applications of the RELAP5 code to the station blackout transients at the Browns Ferry Unit One Plant
Conference
·
Fri Dec 31 23:00:00 EST 1982
·
OSTI ID:6635154
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