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)
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)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 33022064
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- B CODES; CHEMICAL REACTIONS; COMBUSTION KINETICS; COMBUSTION PRODUCTS; COMPUTERIZED SIMULATION; DROPLETS; LIQUID METAL COOLED REACTORS; PONDS; SAFETY ANALYSIS; SODIUM; SPRAYS; THERMAL ANALYSIS
- Descriptors DEC
- ALKALI METALS; CHEMICAL REACTION KINETICS; COMPUTER CODES; ELEMENTS; KINETICS; METALS; PARTICLES; REACTION KINETICS; REACTORS; SIMULATION; SURFACE WATERS
Optional Information
- Notes
- Program code FE/SE-1-G2, Data in PDF format No. FE 082; 23 refs., 15 figs.