National Technical Reports Library

The National Technical Information Service acquires, indexes, abstracts, and archives the largest collection of U.S. government-sponsored technical reports in existence. The NTRL offers online, free and open access to these authenticated government technical reports. Technical reports and documents in its repository may be available online for free either from the issuing federal agency, the U.S. Government Publishing Office’s Federal Digital System website, or through search engines.

Details

Thermal Response of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors. International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource.

DE2008941748

Publication Date	2008
Personal Author	Zhang, H.; Zhao, H.; Davis, C. B.
Page Count	9
Abstract	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.
Keywords	Nuclear reactors Meetings Fast reactors Shutdown Sodium Transients Buffers Design Economics Performance Safety Scram Sodium cooled fast reactor (SFR) After-heat removal Hybrid loop-pool design
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Laboratory, Idaho Falls, ID.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200910

Thermal Response of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors. International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource.

Thermal Response of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors. International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource.
DE2008941748

Publication Date	2008
Personal Author	Zhang, H.; Zhao, H.; Davis, C. B.
Page Count	9
Abstract	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.
Keywords	Nuclear reactors Meetings Fast reactors Shutdown Sodium Transients Buffers Design Economics Performance Safety Scram Sodium cooled fast reactor (SFR) After-heat removal Hybrid loop-pool design
Source Agency	Technical Information Center Oak Ridge Tennessee
Corporate Authors	Idaho National Laboratory, Idaho Falls, ID.; Department of Energy, Washington, DC.
Supplemental Notes	Sponsored by Department of Energy, Washington, DC.
Document Type	Technical Report
NTIS Issue Number	200910