Validation study of sodium pool fire modeling efforts in $$\mathrm{MELCOR}$$ and $$\mathrm{SPHINCS}$$ codes
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
- Japan Atomic Energy Agency (JAEA), Oarai (Japan)
Discharge of sodium coolant into containment from a sodium-cooled fast reactor vessel can occur in the event of a pipe leak or break. In this situation, some of the liquid sodium droplets discharged from the coolant system will react with oxygen in the air before reaching the containment. This phase of the event is normally termed the sodium spray fire phase. Unreacted sodium droplets pool on the containment floor where continued reaction with containment atmospheric oxygen occurs. This phase of the event is normally termed the sodium pool fire phase. Both phases of these sodium-oxygen reactions (or fires) are important to model because of the heat addition and aerosol generation that occur. Any fission products trapped in the sodium coolant may also be released during this progression of events, which if released from containment could pose a health risk to workers and the public. The paper describes progress of an international collaborative research in the area of the sodium fire modeling in the sodium-cooled fast reactors between the United States and Japan under the framework of the Civil Nuclear Energy Research and Development Working Group. In this collaboration between Sandia National Laboratories and Japan Atomic Energy Agency, the validation basis for and modeling capabilities of sodium spray and pool fires in MELCOR of Sandia National Laboratories and SPHINCS of Japan Atomic Energy Agency are being enhanced. Here this study documents MELCOR and SPHINCS sodium pool fire model validation exercises against the JAEA’s sodium pool fire experiments, F7-1 and F7-2. The proposed enhancement of the sodium pool fire models in MELCOR through addition of thermal hydraulic and sodium spreading models that enable a better representation of experimental results is also described.
- Research Organization:
- Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA)
- Grant/Contract Number:
- NA0003525
- OSTI ID:
- 2311672
- Alternate ID(s):
- OSTI ID: 2004737
OSTI ID: 1968966
- Report Number(s):
- SAND--2023-02594J
- Journal Information:
- Nuclear Engineering and Design, Journal Name: Nuclear Engineering and Design Journal Issue: NED IAEA Vol. 407; ISSN 0029-5493
- Publisher:
- ElsevierCopyright Statement
- Country of Publication:
- United States
- Language:
- English
Non-LWR Model Development for the MELCOR Code
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conference | July 2018 |
Numerical Methodology to Evaluate Fast Reactor Sodium Combustion
|
journal | December 2001 |
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