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Published September 2000 | Version v1
Conference paper

Numerical methodology for sodium combustion evaluation of fast reactor

  • 1. Japan Nuclear Cycle Research Inst., O-arai Engineering Center, Oarai, Ibaraki (Japan)

Description

In the present study, sodium combustion analysis codes have been developed for the safety evaluation of a liquid metal cooled fast reactor. It includes zone model code for fast-running safety evaluation, field model code for multi-dimensional thermalhydraulics, chemical reaction analysis code based on chemical equilibrium, and so forth. Recently performed two experiments have been analyzed using the computer codes and the numerical results are in good agreement with the experiment. Although the sodium combustion is a complex phenomenon, use of these computer codes gives better understanding of the coupled thermalhydraulics and chemical reaction. (author)

Part of:
SNA 2000. The fourth international conference on supercomputing in nuclear applications

Additional details

Publishing Information

Publisher
Atomic Energy Society of Japan
Imprint Place
Tokyo (Japan)
ISBN
4-9900652-0-4
Imprint Title
SNA 2000. The fourth international conference on supercomputing in nuclear applications
Imprint Pagination
19 p.

Conference

Title
4th International Conference on Supercomputing in Nuclear Applications
Acronym
SNA 2000
Dates
4-7 Sep 2000
Place
Tokyo (Japan)

Optional Information

Notes
Program code FE/SE-1-G2, Data in PDF format No. FE 082; 23 refs., 15 figs.