An Assessment of Corewide Coherency Effects in the Multichannel Modeling of the Initiating Phase of a Severe Accident in a Sodium Fast Reactor
Author:
Affiliation:
1. Commissariat à l’É nergie Atomique, DEN/DTN/STRI/LMA, CE de Cadarache, 13115 St. Paul-lez-Durance, France
2. Commissariat à l’É nergie Atomique, DEN/DER/SESI/LSMR, CE de Cadarache, 13115 St. Paul-lez-Durance, France
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT12-123
Reference4 articles.
1. Physics of liquid metal fast breeder reactor safety
2. H. H. Hummel, P. A. Pizzica, and Kalimullah, “Studies of Unprotected Loss-of-Flow Accidents for the Clinch River Breeder Reactor,” ANL-76-51, Argonne National Laboratory (Apr. 1976).
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1. Modeling of sodium-cooled fast reactor core – A sensitivity study on number of core channels and axial meshes;Nuclear Engineering and Design;2023-03
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