Published 1999 | Version v1
Computer medium Metadata-only

3D modelling as a support to thermal-hydraulic safety analyses with standard codes

Creators

  • 1. Faculty of Mechanical Engineering, Univ. of Belgrade, Belgrade (Yugoslavia)

Description

A three-dimensional (3D) thermal-hydraulic model and a numerical procedure for the simulation and analysis of a steady-state, as well as transient operation of nuclear power plant components are presented. A two-fluid approach is applied to modelling of two-phase flow. Thermal-hydraulics of a horizontal steam generator in the WWER 1000 nuclear power plant has been simulated at the full load, steady-state operation. A comparison of the numerical results with data measured at the NPP Novovoronjezh shows good agreement. 3D numerical results can be used in plant design or retrofitting, in nuclear power plant operation and safety analysis and as improvement of existing one-dimensional thermal-hydraulics models of the horizontal steam generator which are assessed by system codes used for the nuclear power plant safety analyses. (author)

Part of:
ICONE-7: Proceedings of the 7th international conference on nuclear engineering

Additional details

Publishing Information

Publisher
Japan Society of Mechanical Engineers
Imprint Place
Tokyo (Japan)
Imprint Title
ICONE-7: Proceedings of the 7th international conference on nuclear engineering
Imprint Pagination
4252 p.
Journal Page Range
[10 p.]

Conference

Title
7. international conference on nuclear engineering
Acronym
ICONE-7
Dates
19-23 Apr 1999
Place
Tokyo (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
31009067
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COMPUTERIZED SIMULATION; FUNCTIONAL MODELS; HEAT TRANSFER; HYDRAULICS; NUCLEAR POWER PLANTS; R CODES; SAFETY ANALYSIS; STEAM GENERATORS; THREE-DIMENSIONAL CALCULATIONS; TWO-PHASE FLOW; WWER TYPE REACTORS
Descriptors DEC
BOILERS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL POWER PLANTS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
This CD-ROM can be used for WINDOWS 95/98/NT, MACINTOSH and UNIX; Acrobat Reader 3.0.1 is included; Data in PDF format, Track No. 07, ICONE-7376