An Innovative Hybrid Loop-Pool Design for Sodium Cooled Fast Reactor

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The existing sodium cooled fast reactors (SFR) have two types of designs – loop type and pool type. In the loop type design, such as JOYO (Japan) [1] and MONJU (Japan), the primary coolant is circulated through intermediate heat exchangers (IHX) external to the reactor tank. The major advantages of loop design include compactness and easy maintenance. The disadvantage is higher possibility of sodium leakage. In the pool type design such as EBR-II (USA), BN-600M(Russia), Superphénix (France) and European Fast Reactor [2], the reactor core, primary pumps, IHXs and direct reactor auxiliary cooling system (DRACS) heat exchangers (DHX) all are ... continued below

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Zhao, Haihua & Zhang, Hongbin November 1, 2007.

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The existing sodium cooled fast reactors (SFR) have two types of designs – loop type and pool type. In the loop type design, such as JOYO (Japan) [1] and MONJU (Japan), the primary coolant is circulated through intermediate heat exchangers (IHX) external to the reactor tank. The major advantages of loop design include compactness and easy maintenance. The disadvantage is higher possibility of sodium leakage. In the pool type design such as EBR-II (USA), BN-600M(Russia), Superphénix (France) and European Fast Reactor [2], the reactor core, primary pumps, IHXs and direct reactor auxiliary cooling system (DRACS) heat exchangers (DHX) all are immersed in a pool of sodium coolant within the reactor vessel, making a loss of primary coolant extremely unlikely. However, the pool type design makes primary system large. In the latest ANL’s Advanced Burner Test Reactor (ABTR) design [3], the primary system is configured in a pool-type arrangement. The hot sodium at core outlet temperature in hot pool is separated from the cold sodium at core inlet temperature in cold pool by a single integrated structure called Redan. Redan provides the exchange of the hot sodium from hot pool to cold pool through IHXs. The IHXs were chosen as the traditional tube-shell design. This type of IHXs is large in size and hence large reactor vessel is needed.

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  • 2007 ANS/ENS International Meeting,Washington D.C.,11/11/2007,11/15/2007

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  • Report No.: INL/CON-07-12657
  • Grant Number: DE-AC07-99ID-13727
  • Office of Scientific & Technical Information Report Number: 923496
  • Archival Resource Key: ark:/67531/metadc897459

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  • November 1, 2007

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  • Sept. 27, 2016, 1:39 a.m.

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  • Nov. 7, 2016, 4:21 p.m.

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Zhao, Haihua & Zhang, Hongbin. An Innovative Hybrid Loop-Pool Design for Sodium Cooled Fast Reactor, article, November 1, 2007; [Idaho Falls, Idaho]. (digital.library.unt.edu/ark:/67531/metadc897459/: accessed August 18, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.