Published October 2003 | Version v1
Miscellaneous Metadata-only

Steady state and transient core analysis of the VVER-1000 nuclear reactor

Creators

  • 1. Bulgarian Academy of Sciences, Institute for Nuclear Research and Nuclear Energy, Sofia (Bulgaria)

Description

Detailed thermal hydraulic calculation of the reactor core have been carried out at steady state conditions and during loss of power of the main pumps using modified digital computer program COBRA-3C [1]. The purpose was to estimate the safe margins of the reactor operation and to get the temperature fields in the coolant and the reactor fuel elements, distribution of the flow, void fraction, etc., in the maximal powered fuel rod bundle of VVER-1000 reactor core. The deviation of the operation parameters from the nominal values and technical factors have been taken into account. This work summarises our experience in using the computer code COBSIM for subchannel analysis of the nuclear reactor VVER-1000 in steady state conditions and during coast down of the main pumps. The most significant modifications and extension of the computer code COBRA-3C are discussed and some computational result are shown. (author)

Part of:
Calculation of gamma-ray dose rate from storage cask with radioactive sludge

Additional details

Identifiers

URL
http://www.vin.bg.ac.yu/YUNS/YUNSC2K2/Contents.htm;

Publishing Information

Publisher
Institute of Nuclear Sciences VINCA
Imprint Place
Belgrade (Yugoslavia)
ISBN
86-7306-062-1
Imprint Title
Proceedings of the Yugoslav Nuclear Society Conference (YUNSC-2002)
Imprint Pagination
706 p.
Journal Page Range
p. 191-194

Conference

Title
4. International Yugoslav Nuclear Society Conference
Acronym
YUNSC-2002
Dates
30 Sep - 4 Oct 2002
Place
Belgrade (Yugoslavia)

INIS

Country of Publication
Yugoslavia
Country of Input or Organization
Serbia
INIS RN
41123039
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature, Numerical Data
Descriptors DEI
C CODES; COMPUTER CALCULATIONS; COOLANTS; DATA ANALYSIS; EVALUATED DATA; EXPERIMENTAL DATA; FLOW MODELS; FUEL ELEMENTS; FUEL RODS; MONITORING; REACTOR CHANNELS; REACTOR CORES; REACTOR SAFETY; STEADY-STATE CONDITIONS; THERMAL HYDRAULICS; WWER TYPE REACTORS
Descriptors DEC
COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; FLUID MECHANICS; FUEL ELEMENTS; HYDRAULICS; INFORMATION; MATHEMATICAL MODELS; MECHANICS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
3 refs., 6 figs.; This record replaces 35104450; This record replaces 36000071