Thermal Response of the Hybrid Loop-Pool Design for Sodium Cooled Faster Reactors

Conference · Mon Sep 01 04:00:00 EDT 2008

OSTI ID:941748

Zhang, Hongbin; Zhao, Haihua; Davis, Cliff

An innovative hybrid loop-pool design for the sodium cooled fast reactor (SFR) has been recently proposed with the primary objective of achieving cost reduction and safety enhancement. With the hybrid loop-pool design, closed primary loops are immersed in a secondary buffer tank. This design takes advantage of features from conventional both pool and loop designs to further improve economics and safety. This paper will briefly introduce the hybrid loop-pool design concept and present the calculated thermal responses for unproctected (without reactor scram) loss of forced circulation (ULOF) transients using RELAP5-3D. The analyses examine both the inherent reactivity shutdown capability and decay heat removal performance by passive safety systems.

• Research Organization: Idaho National Laboratory (INL)
• Sponsoring Organization: DOE - NE
• DOE Contract Number: AC07-99ID13727
• OSTI ID: 941748
• Report Number(s): INL/CON-07-13296
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
AFTER-HEAT REMOVAL
BUFFERS
DESIGN
ECONOMICS
FAST REACTORS
PERFORMANCE
SAFETY
SCRAM
SFR
RELAP5-3D
Thermal Response
SHUTDOWN
SODIUM
TRANSIENTS