Published October 2010 | Version v1
Miscellaneous Open

Comparison of In-Core Thermocouple and SPND Measured Data with the ATHLET-BIPR-VVER Predictions

Creators

  • 1. RRC Kurchatov Institute (Russian Federation)
  • 2. GRS mbH (Germany)

Description

The aim of this study is to compare the available in-core measured thermal-hydraulic and neutron-physical local (point) core data of the OECD/NEA Kalinin-3 Benchmark with the ATHLET-BIPR-VVER (A-BV) simulation results. In order to decrease the uncertainties coming from modelling of the primary and secondary NPP sides a boundary condition problem is defined on the base of the measure data. (Authors)

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Part of:
Proceedings of the twentieth symposium of atomic energy research

Additional details

Publishing Information

Publisher
Kiadja and KFKI Atomenergia Kutatointezet
Imprint Place
Budapest (Hungary)
ISBN
978-963-372-643-3 (OE)
Imprint Title
Proceedings of the twentieth symposium of atomic energy research
Imprint Pagination
790 p.
Journal Page Range
p. 1-15
Report number
INIS-SK--2010-097

Conference

Title
20. Atomic Energy Research Symposium on WWER Physics and Reactor Safety
Dates
20-24 Sep 2010
Place
Hanasaari, Espoo (Finland)

INIS

Country of Publication
Hungary
Country of Input or Organization
Slovakia
INIS RN
41131444
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Numerical Data
Descriptors DEI
BENCHMARKS; CONTROL ELEMENTS; COOLANT LOOPS; COUPLED REACTOR CORES; DATA COVARIANCES; EXPERIMENTAL DATA; FUEL ASSEMBLIES; FUEL ELEMENT CLUSTERS; KALININ-3 REACTOR; MULTIPHASE FLOW; NUMERICAL DATA; REACTOR CHANNELS; REACTOR COMMISSIONING; REACTOR COMPONENTS; SELF-POWERED NEUTRON DETECTORS; TEMPERATURE DISTRIBUTION; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; TRANSIENTS; VALIDATION
Descriptors DEC
COMMISSIONING; COOLING SYSTEMS; DATA; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; FLUID FLOW; FLUID MECHANICS; FUEL ASSEMBLIES; HYDRAULICS; INFORMATION; MEASURING INSTRUMENTS; MECHANICS; NEUTRON DETECTORS; NUMERICAL DATA; POWER REACTORS; PWR TYPE REACTORS; RADIATION DETECTORS; REACTOR COMPONENTS; REACTOR CORES; REACTORS; SELF-POWERED DETECTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; WWER TYPE REACTORS

Optional Information

Contract/Grant/Project number
The work was partly performed within projects supporting the scientific and technological co-operation with Russia of the German Federal Ministry of Economics and Technology (Russian Federation; Germany)
Notes
11 figs.; 7 refs.