Simulation of the OSU inherently safe reactor design using RELAP5

Journal Article · Sat Dec 31 04:00:00 EST 1994 · Transactions of the American Nuclear Society

OSTI ID:76000

Aybar, H S

The Ohio State University inherently safe reactor (OSU-ISR) is a 340-MW(electric [1000-MW(thermal)]), natural-circulation, indirect-cycle small boiling water reactor. The design features a multicavity prestressed concrete reactor vessel (PCRV), which contains all primary loop components (i.e., reactor, steam separator, subcooler/preheater, condenser/evaporator). Under normal operation, the naturally circulated primary fluid rises vertically in the chimney after exiting from the core and enters the steam separator. The separated steam in the steam separator rises through the chimney cavity and then goes through the steam bypass orifice to the upper section of the downcomer cavity where the condenser/evaporator (C/E) is located. The saturated water goes through the water bypass orifice to the lower section of the downcomer cavity where the subcooler/preheater (S/P) is located. The secondary-loop coolant flows in the S/P tubes, is heated up, and then goes to the C/E tubes and is evaporated. The OSU-ISR is inherently safe against any primary breaks. However, any kind of secondary fault (e.g., feedwater pump trip or rupture of one of the S/P or C/E tubes) may lead to loss of heat sink. In that case, the steam-driven jet injector uses the decay heat steam to pump water from the suppression pool to cool the reactor core.

• OSTI ID: 76000
• Report Number(s): CONF-940602--
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 70; ISSN TANSAO; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
DESIGN
HEAT EXCHANGERS
PRESSURE VESSELS
R CODES
REACTOR OPERATION
RESEARCH REACTORS