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Challenges Associated with the Mitigation of Unprotected Loss of Flow in Sodium-Cooled Fast Reactor Cores

Gerald Rimpault, Sandra Poumerouly, Johann Lecerf

Nuclear Technology / Volume 181 / Number 1 / January 2013 / Pages 56-67

Technical Paper / Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Thermal Hydraulics; Fission Reactors; Reactor Safety

Reactivity effects associated with the mitigation of unprotected loss of flow in sodium fast reactors are being studied to find ways to reduce the potential release of mechanical energy.

The studies performed with ERANOS illustrate the importance of cladding removal as well as radial leakage changes during the core slumpdown. Possible arrangements and dispositions are envisioned that would avoid recriticality and hence the possibility of going into severe power excursions.

Challenges to be faced by safety studies that would ascertain that no cliff-edge effects occur are then listed.

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