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)
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31031646.pdf
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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