Iris steam generator design overview
Creators
- 1. Mistubishi Heavy Industries, Kobe (Japan)
- 2. Polytechnic of Milan, Nuclear Engineering Dept (Italy)
- 3. Japan Atomic Power Co. Tokyo (Japan)
- 4. Westinghouse Electric Company, Pittsburgh, PA (United States)
Description
The IRIS (International Reactor Innovative and Secure) is a 300 MWt pressurized water reactor being developed by an international consortium, led by Westinghouse, and which includes universities (Polytechnic of Milan, Univ. of California at Berkeley, MIT, Tokyo Inst. Of Technology, and the Univ. of Pisa); laboratories (CEA, Cadarache); commercial companies (BNFL, Bechtel, MHI); and utilities (JAPC). The US Department of Energy is supporting the development of IRIS as part of the NERI Program. IRIS has an ''integral'' reactor vessel, i.e.; the reactor vessel contains the reactor core, the pressurizer, the steam generator and the reactor coolant pumps. This integral reactor coolant system eliminates all loop piping, eliminates the separate pressure vessels and supports, and permits a very compact containment layout. A key component in the IRIS integral design is the unique steam generator. This paper will summarize the design evaluations and the selection process used to evaluate the IRIS steam generator design options, and the selected steam generator design will be presented. The presentation will include discussions of the calculations for heat transfer and fluid pressure drop, methods of inspection and maintenance for the generators, and discussion on steam generator replacement and refurbishment. (author)
Availability note (English)
Available from INIS in electronic formFiles
33015269.pdf
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Additional details
Publishing Information
- Imprint Pagination
- [1 p.]
- Report number
- INIS-FR--959
Conference
- Title
- 9. international conference on nuclear engineering
- Dates
- 8-12 Apr 2001
- Place
- Nice, Acropolis (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 33015269
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COORDINATED RESEARCH PROGRAMS; DESIGN; FLUID FLOW; HEAT TRANSFER; PRESSURE DROP; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR MAINTENANCE; STEAM GENERATORS; WATER SUPPLY
- Descriptors DEC
- BOILERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MAINTENANCE; POWER REACTORS; REACTORS; RESEARCH PROGRAMS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS