Analytical model for transient fluid mixing in upper outlet plenum of an LMFBR
Description
A two-zone mixing model based on the lumped-parameter approach was developed for the analysis of transient thermal response in the outlet plenum of an LMFBR. The maximum penetration of core flow is used as the criterion for dividing the sodium region into two mixing zones. The model considers the transient sodium temperature affected by the thermal expansion of sodium, heat transfer with cover gas, heat capacity of different sections of metal and the addition of by-pass flow into the plenum. The results of numerical calculations indicate that effects of flow stratification, chimney height, metal heat capacity and by-pass flow are important for transient sodium temperature calculation. Thermal expansion of sodium and heat transfer with the cover gas do not play any significant role on sodium temperature
Availability note (English)
MF available from INIS under the Report Number.
Files
Additional details
Publishing Information
- Imprint Pagination
- 9 p.
- Report number
- BNL-NUREG--21782
Conference
- Title
- International meeting on fast reactor safety and related physics.
- Dates
- Oct 1976.
- Place
- Chicago, Illinois, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8296906
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FLUID FLOW; LMFBR TYPE REACTORS; MATHEMATICAL MODELS; MIXING; PRIMARY COOLANT CIRCUITS; SODIUM; TRANSIENTS
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; COOLING SYSTEMS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; METALS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS
Optional Information
- Notes
- Available from NTIS. $3.50.
- Secondary number(s)
- CONF-761001--4.