Published 1976 | Version v1
Report Restricted

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.

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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.