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RELAP5 Analysis of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors (Preprint). ICAPP 2008.


DE2008935457

Publication Date 2008
Personal Author Zhang, H.; Zhao, H.; Davis, C.; Memmott, M.
Page Count 14
Abstract An innovative hybrid loop-pool design for sodium cooled fast reactors (SFR-Hybrid) has been recently proposed. This design takes advantage of the inherent safety of a pool design and the compactness of a loop design to improve economics and safety of SFRs. In the hybrid loop-pool design, primary loops are formed by connecting the reactor outlet plenum (hot pool), intermediate heat exchangers (IHX), primary pumps and the reactor inlet plenum with pipes. The primary loops are immersed in the cold pool (buffer pool). Passive safety systems--modular Pool Reactor Auxiliary Cooling Systems (PRACS)--are added to transfer decay heat from the primary system to the buffer pool during loss of forced circulation (LOFC) transients. The primary systems and the buffer pool are thermally coupled by the PRACS, which is composed of PRACS heat exchangers (PHX), fluidic diodes and connecting pipes. Fluidic diodes are simple, passive devices that provide large flow resistance in one direction and small flow resistance in reverse direction. Direct reactor auxiliary cooling system (DRACS) heat exchangers (DHX) are immersed in the cold pool to transfer decay heat to the environment by natural circulation. To prove the design concepts, especially how the passive safety systems behave during transients such as LOFC with scram, a RELAP5-3D model for the hybrid loop-pool design was developed.
Keywords
  • Fast reactors
  • Design
  • After heat removal
  • Buffers
  • Burners
  • Cooling systems
  • Economics
  • Heat exchangers
  • Natural convection
  • Removal
  • Safety
  • Sodium
  • Test reactors
  • Transients
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 200901
RELAP5 Analysis of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors (Preprint). ICAPP 2008.
RELAP5 Analysis of the Hybrid Loop-Pool Design for Sodium Cooled Fast Reactors (Preprint). ICAPP 2008.
DE2008935457

  • Fast reactors
  • Design
  • After heat removal
  • Buffers
  • Burners
  • Cooling systems
  • Economics
  • Heat exchangers
  • Natural convection
  • Removal
  • Safety
  • Sodium
  • Test reactors
  • Transients
  • Technical Information Center Oak Ridge Tennessee
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