Thermal-hydraulic analysis of Ignalina NPP compartments response to group distribution header rupture using RALOC4 code
Creators
- 1. Laboratory of Nuclear Installation Safety, Lithuanian Energy Institute, Breslaujos 3, LT-3035 Kaunas (Lithuania)
Description
The Accident Localisation System of Ignalina NPP is a containment of pressure suppression type designed to protect the environment from the dangerous impact of the radiation. In this paper the analysis of guillotine Group Distribution Header break in the Lower Water Piping compartment of ALS of Ignalina NPP is presented. The purpose of this analysis is to perform the long-term thermal-hydraulic analysis of compartments response to Group Distribution Header rupture and to verify if design pressure values in the compartments are not exceeded. The operation of CTCS, sprays, drainages and the make-up of hot condensate chamber are considered in the model. According to the calculation results all the pressures in ALS compartments are below the maximum allowed design values. (authors)
Files
33011251.pdf
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Additional details
Identifiers
- URL
- http://www.iync.org/;
Publishing Information
- Publisher
- YDRNS Information Technology Services, Ltd.
- Imprint Place
- Obninsk (Russian Federation)
- Imprint Title
- International Youth Nuclear Congress 2000: Youth, Future, Nuclear. Proceedings and Multimedia Presentation
- Imprint Pagination
- [1000 p.]
- Journal Page Range
- [4 p.]
- Report number
- INIS-SK--2002-01
Conference
- Title
- International Youth Nuclear Congress 2000
- Acronym
- IYNC 2000
- Dates
- 9-14 Apr 2000
- Place
- Bratislava (Slovakia)
INIS
- Country of Publication
- Russian Federation
- Country of Input or Organization
- Slovakia
- INIS RN
- 33011251
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- COMPUTER CALCULATIONS; COMPUTER CODES; COMPUTER-AIDED DESIGN; DESIGN BASIS ACCIDENTS; EXPERIMENTAL DATA; HYDRAULICS; IGNALINA-1 REACTOR; MATHEMATICAL MODELS; PRESSURE GRADIENTS; PRESSURIZATION; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RUPTURES; WATER SUPPLY
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; DATA; DESIGN; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FAILURES; FLUID MECHANICS; GRAPHITE MODERATED REACTORS; INFORMATION; LWGR TYPE REACTORS; MECHANICS; NUMERICAL DATA; POWER REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS
Optional Information
- Notes
- 3 Refs, 4 figs. E-mail: egis@isag.lei.lt Data on the publication on CD-ROM in PDF and HTML format; Acrobat Reader for Windows 3.x, 95, 98, NT3.5.1, NT 4.0, 2000, MacIntosh and UNIX (SUN, HP, IRIX (SGI) and Digital UNIX) included