Mitigation of BWR MARK 1 containment loads due to safety relief valve actuations by a low low set relief logic

Conference · Fri Jan 01 00:00:00 EST 1982 · Trans. Am. Nucl. Soc.; (United States)

OSTI ID:5871735

Chi, L L; Stoll, C H

• Research Organization: General Electric Company, Nuclear Energy Division, 175 Curtner Avenue, San Jose, CA 95125
• OSTI ID: 5871735
• Report Number(s): CONF-821103-
• Journal Information: Trans. Am. Nucl. Soc.; (United States), Vol. 43; Conference: American Nuclear Society winter meeting, Washington, DC, USA, 14 Nov 1982
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BWR TYPE REACTORS
CONTAINMENT
RELIEF VALVES
TRANSIENT OVERPOWER ACCIDENTS
COMPUTER CODES
M CODES
LOAD MANAGEMENT
LOSS OF COOLANT
PRESSURE RELEASE
REACTOR SAFETY
REACTOR TECHNOLOGY
ACCIDENTS
CONTROL EQUIPMENT
EQUIPMENT
FLOW REGULATORS
MANAGEMENT
REACTOR ACCIDENTS
REACTORS
SAFETY
VALVES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100* - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled