Published May 2000 | Version v1
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Experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors. Proceedings of a technical committee meeting

Description

Worldwide there is considerable experience in nuclear power technology, especially in water cooled reactor technology. Of the operating plants, in September 1998, 346 were light water reactors (LWRs) totalling 306 GW(e) and 29 were heavy water reactors (HWRs) totalling 15 GW(e). The accumulated experience and lessons learned from these plants are being incorporated into new advanced reactor designs. Utility requirements documents have been formulated to guide these design activities by incorporating this experience, and results from research and development programmes, with the aim of reducing costs and licensing uncertainties by establishing the technical bases for the new designs. Common goals for advanced designs are high availability, user-friendly features, competitive economics and compliance with internationally recognized safety objectives. Large water cooled reactors with power outputs of 1300 MW(e) and above, which possess inherent safety characteristics (e.g. negative Doppler moderator temperature coefficients, and negative moderator void coefficient) and incorporate proven, active engineered systems to accomplish safety functions are being developed. Other designs with power outputs from, for example, 220 MW(e) up to about 1300 MW(e) which also possess inherent safety characteristics and which place more emphasis on utilization of passive safety systems are being developed. Passive systems are based on natural forces and phenomena such as natural convection and gravity, making safety functions less dependent on active systems and components like pumps and diesel generators. In some cases, further experimental tests for the thermohydraulic conditions of interest in advanced designs can provide improved understanding of the phenomena. Further, analytical methods to predict reactor thermohydraulic behaviour can be qualified for use by comparison with the experimental results. These activities should ultimately result in more economical designs. The Technical Committee Meeting on Experimental Tests and Qualification of Analytical Methods to Address Thermohydraulic Phenomena in Advanced Water Cooled Reactors was convened to review the current status and the remaining needs in this field

Availability note (English)

Available from INIS in electronic form

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Additional details

Publishing Information

Imprint Pagination
475 p.
ISSN
1011-4289
Report number
IAEA-TECDOC--1149

Conference

Title
Technical committee meeting on experimental tests and qualification of analytical methods to address thermohydraulic phenomena in advanced water cooled reactors
Dates
14-17 Sep 1998
Place
Villigen (Switzerland)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
31031646
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Is Lead record
Yes
Descriptors DEI
ANALYTICAL SOLUTION; DOPPLER EFFECT; ENGINEERED SAFETY SYSTEMS; HYDRODYNAMICS; LEADING ABSTRACT; NATURAL CONVECTION; REACTOR SAFETY EXPERIMENTS; SAFETY ANALYSIS; TEMPERATURE COEFFICIENT; THERMAL ANALYSIS; VOID COEFFICIENT; WATER COOLED REACTORS
Descriptors DEC
ABSTRACTS; CONVECTION; ENERGY TRANSFER; FLUID MECHANICS; HEAT TRANSFER; MASS TRANSFER; MECHANICS; REACTIVITY COEFFICIENTS; REACTORS

Optional Information

Notes
Refs, figs, tabs