Published 1982 | Version v1
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Scaling criteria for LWR's under single-phase and two-phase natural circulation

Description

Scaling criteria for a natural circulation loop under single-phase and two-phase flow conditions have been derived. For a single-phase case the continuity, integral momentum, and energy equations in one-dimensional area average forms have been used. From this, the geometrical similarity groups, friction number, Richardson number, characteristic time constant ratio, Biot number, and heat source number are obtained. The Biot number involves the heat-transfer coefficient which may cause some difficulties in simulating the turbulent-flow regime. For a two-phase-flow case, the similarity groups obtained from a perturbation analysis based on the one-dimensional drift-flux model have been used. The physical significance of the phase-change number, subcooling number, drift-flux number, friction number are discussed and conditions imposed by these groups are evaluated. In the two-phase-flow case, the critical heat flux is one of the most-important transients which should be simulated in a scale model. The above results are applied to the LOFT facility in case of a natural-circulation simulation

Availability note (English)

MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01 as DE83007721.

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Additional details

Publishing Information

Imprint Pagination
39 p.
Report number
CONF-820962--4

Conference

Title
NRC/ANS meeting on basic thermal hydraulic mechanisms in LWR analysis.
Dates
14-15 Sep 1982.
Place
Bethesda, MD (USA).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
14775899
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
HEAT TRANSFER; HYDRAULICS; LOSS OF FLOW; MATHEMATICAL MODELS; NATURAL CONVECTION; PWR TYPE REACTORS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; CONVECTION; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTORS; SAFETY; WATER COOLED REACTORS; WATER MODERATED REACTORS