Published June 2000 | Version v1
Report Metadata-only

Modelling the ISB-WWER experimental stand

Creators

Description

ISB-WWER is an experimental facility built at the Research and Engineering Centre for Nuclear Power Plants in Elektrogorsk, Russia. The facility serves to simulate the primary coolant circuit of VVER 1000 type reactors and to model thermal hydraulic processes in it. The report presents the results of calculations of small break LOCA with and without high-pressure feed performed by using the ATHLET code and comparison of the results with observed data. The effect of granulation of reactor core distribution on the fuel simulator cladding temperature was also studied. (P.A.)

Availability note (English)

Available from Nuclear Research Institute Rez, 250 68 Rez, Czech Republic; e-mail contact: ret@nri.cz

Additional details

Additional titles

Original title (Czech)
Modelovani experimentalniho stendu ISB-WWER

Publishing Information

Imprint Pagination
[134 p.]
Report number
UJV--11428-T

INIS

Country of Publication
Czech Republic
Country of Input or Organization
Czech Republic
INIS RN
36101211
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Non-conventional Literature
Descriptors DEI
A CODES; COMPUTER CALCULATIONS; DESIGN BASIS ACCIDENTS; FEEDWATER; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; TEST FACILITIES; WWER TYPE REACTORS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
6 tabs., 119 figs., 6 refs.