Published April 2002 | Version v1
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Natural convection and natural circulation flow and limits in advanced reactor concepts

Creators

  • 1. Atomic Energy of Canada Ltd (Canada)

Description

Existing reactor designs and new concepts rely to varying degrees on heat removal processes driven by natural convection as a potentially important design feature or ultimate heat removal mechanism. This is independent of whether the nuclear core is cooled by water, gas or liquid metal, since in many shut down or emergency conditions forced cooling is assumed or predicted to be lost. However, using natural convection to advantage is possible, since it can provide significant cost-savings by the elimination of pumps and ancillary equipment and also can result in simplified and hence higher reliability safety systems. It is highly desirable to build on the inherent or existing heat removal processes than to graft design or add them on afterwards. The limits to the heat removal are set by the natural circulation flow and heat removal capability, so these need to be predicted with accuracy. The capability limit is determined by well-known physically linked parameters, including the flow rates, driving heads, heat sinks, fluid thermal expansion, and flow thermal and hydraulic stability. In natural convection plants, there are opportunities for the limits to be set by the absolute power output available from naturally convective flow, and the onset of instability in that flow. We are interested in the ultimate or maximum power output both in order to minimize power generation costs, and to determine how far the natural circulation designs can be developed. This paper reviews some of the fundamental equations and analytical solutions for natural convection flows, and examines their application to determine the limits of heat removal as a means of establishing simple criteria and fundamental design limits. This type of physical analysis can be used to investigate the flow and stability limits for a thermally expandable fluid, which encompasses the extremes of both low and supercritical pressure applications. To illustrate the approach, simple analytical expressions are derived for the ultimate or maximum heat removal. We can then relate the maximum thermal hydraulic limits to hypothetical reactor power output. The relationship between some of the various enhanced design features is then clear when seeking the ultimate or maximum safe power output at least cost. Hypothetical natural circulation designs are discussed as a basis. (author)

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Natural circulation data and methods for advanced water cooled nuclear power plant designs. Proceedings of a technical committee meeting

Additional details

Publishing Information

Imprint Title
Natural circulation data and methods for advanced water cooled nuclear power plant designs. Proceedings of a technical committee meeting
Imprint Pagination
252 p.
Journal Page Range
p. 49-65
ISSN
1011-4289
Report number
IAEA-TECDOC--1281

Conference

Title
Technical committee meeting on natural circulation data and methods for advanced water cooled nuclear power plant designs
Dates
18-21 Jul 2000
Place
Vienna (Austria)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
33018370
Subject category
S42: ENGINEERING; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT; ECONOMICS; FLOW RATE; FLUID FLOW; NATURAL CONVECTION; REACTOR COOLING SYSTEMS; REACTOR SAFETY; STABILITY; THERMAL ANALYSIS; THERMAL EXPANSION
Descriptors DEC
CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; EXPANSION; HEAT TRANSFER; MASS TRANSFER; REACTOR COMPONENTS; SAFETY

Optional Information

Notes
Refs, 4 figs