Inter-subassembly heat transfer of sodium cooled fast reactors: Validation of the NETFLOW code

Author:

Mochizuki Hiroyasu

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference9 articles.

1. Inter-Subassembly Heat Transfer Model of FBR System Dynamics Code for Natural Circulation Simulation, Proceedings of Eighth International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-8), vol. 1;Enuma,1997

2. Guppy, J.G., 1983. Super System Code [ssc Rev.2] an Advanced Thermohydraulic Simulation Code for Transients in LMFBRs, NUREG/CR-3169.

3. Kondo, H., et al., 2003. Design and Manufacture of JOYO Mk-III Heat Transport System—Main Intermediate Heat Exchanger, JNC TN9410 2003-004 (in Japanese).

4. Development of Transient Analysis Code for Primary Cooling System Coupled with Reactor Auxiliary Cooling Systems, Proceedings of NUPTHO-3;Mochizuki,1988

5. Mochizuki, H., Kishida, M., 1998. Network Calculation of System Integration Experiment with a Sodium Loop under Natural Circulation Condition, ICONE-6, ICONE-6127, San Diego, USA.

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