Published February 2021 | Version v1
Journal article

2D and 3D numerical investigations of sodium boiling in sodium cooled fast reactor with MOX fuel and low sodium void reactivity effect during unprotected loss of flow accidents

  • 1. State Scientific Center "Institute for Physiscs and Power Engineering", 1 Bondarenko Square, Obninsk (Russian Federation)
  • 2. Electricite De France (EDF), EDF Lab Paris-Saclay, Palaiseau (France)
  • 3. National Research Center "Kurchatov Institute", 1 Akademika Kurchatova Square, Moscow (Russian Federation)

Description

Highlights: • Behavior of SFR under ULOF simulated for Low Sodium Void Worth design. • No core melting simulated and stable boiling behavior predicted by both codes. • Different frequencies and amplitudes of boiling regimes with SIMMER and COREMELT. • 3D modeling performed with COREMELT confirms oscillating behavior and absence of core melting. • If confirmed by enough experimental evidence, could make safety demonstration of SFR more robust.

Availability note (English)

Available from http://dx.doi.org/10.1016/j.nucengdes.2020.110961

Additional details

Identifiers

DOI
10.1016/j.nucengdes.2020.110961;
PII
S0029549320304556;

Publishing Information

Journal Title
Nuclear Engineering and Design
Journal Volume
372
Journal Page Range
vp.
ISSN
0029-5493
CODEN
NEDEAU

Optional Information

Copyright
Copyright (c) 2020 Elsevier B.V. All rights reserved.