DocumentCode :
304354
Title :
Reactor coolant pump startup under degraded conditions in a scaled OTSG lowered loop PWR
Author :
Tafreshi, A.M. ; Marzo, M. Di
Author_Institution :
Dept. of Mater. & Nucl. Eng., Maryland Univ., College Park, MD, USA
Volume :
2
fYear :
1996
fDate :
11-16 Aug 1996
Firstpage :
1512
Abstract :
After a small break-loss of coolant accident or improper maintenance activities, the potential exists for a nonuniform distribution of boric acid in a PWR coolant system. This in turn presents the possibility of a reactivity excursion if sufficient volumes of boron-dilute water an transported into the core region without having first undergone substantial mixing. A research program is being conducted at the University of Maryland College Park (USA) 2×4 thermal-hydraulic test facility to assess the generation, transport and mixing of boron-dilute volumes. The start up of a pump and the flow of a boron free slug of water in the cold leg and subsequent transport to the core downcorner in the facility is investigated
Keywords :
boron compounds; fission reactor accidents; fission reactor coolants; fission reactor cooling; fission reactor safety; fission research reactors; nuclear power stations; nuclear reactor steam generators; pumps; starting; PWR coolant system; boron-dilute volumes; core downcorner; core region; degraded conditions; generation; mixing; once-through steam generators; reactivity excursion; reactor coolant pump startup; research program; thermal-hydraulic test facility; transport; Accidents; Boron; Coolants; Cooling; Degradation; Inductors; Leg; Nuclear power generation; Prototypes; Seals;
fLanguage :
English
Publisher :
ieee
Conference_Titel :
Energy Conversion Engineering Conference, 1996. IECEC 96., Proceedings of the 31st Intersociety
Conference_Location :
Washington, DC
ISSN :
1089-3547
Print_ISBN :
0-7803-3547-3
Type :
conf
DOI :
10.1109/IECEC.1996.553952
Filename :
553952
Link To Document :
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