Investigation of natural circulation phenomena in WWER-1000 reactors
- 1. Sharif Univ. of Technology, Tehran (Iran, Islamic Republic of). Dept. of Mechanical Engineering
- 2. DIMNP, Univ. of Pisa (Italy)
Description
Natural circulation cooling is very important phenomena from the viewpoint of a passive safety concept. Natural circulation phenomena plays an important role in energy extraction from hot zones and rejection to the cold zones without using a mechanical pump in several engineering systems, such as solar water heaters, geothermal heat extraction, electrical machine motor cooling, nuclear reactor core cooling. In this paper we are using the RELAP5 system code model for the analysis of natural circulation transient in WWER-1000 reactors. The WWER-1000 reactor type is a PWR with a thermal power of about 3000 MW. We have considered the following systems of WWER-1000 into the model: Pressure vessel of WWER-1000; Main circulation pipelines; Reactor coolant pump; Steam generators; Pressurizer; Main steam lines; Main and auxiliary feed water; The results, which are obtained from the model by using the RELAP5 code, can be compared with experimental results. (author)
Additional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- ICONE-11: Proceedings of the 11th international conference on nuclear engineering
- Imprint Pagination
- [3610 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 11. international conference on nuclear engineering
- Acronym
- ICONE-11
- Dates
- 20-23 Apr 2003
- Place
- Tokyo (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 35045207
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COOLING; HEAT FLUX; NATURAL CONVECTION; NOVOVORONEZH-5 REACTOR; PRIMARY COOLANT CIRCUITS; STEAM GENERATORS; TWO-PHASE FLOW; VAPOR CONDENSATION
- Descriptors DEC
- BOILERS; CONVECTION; COOLING SYSTEMS; ENERGY SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Track No. 07, Session 7-28, ICONE-36229