The SET matrix of experiments is suitable for the developmental assessment of thermal-hydraulics transient system computer codes by selecting individual tests from selected facilities, relevant to each phenomena. Test facilities differ from one another in geometrical dimensions, geometrical configuration and operating capabilities or conditions. Correlation between SET facility and phenomena were calculated on the basis of suitability for model validation (which means that a facility is designed in such a way as to stimulate the phenomena assumed to occur in a plant and is sufficiently instrumented); limited suitability for model variation (which means that a facility is designed in such a way as to stimulate the phenomena assumed to occur in a plant but has problems associated with imperfect scaling, different test fluids or insufficient instrumentation); and unsuitability for model validation.
Whereas integral experiments are usually designed to follow the behaviour of a reactor system in various off-normal or accident transients, separate effects tests focus on the behaviour of a single component, or on the characteristics of one thermal-hydraulic phenomenon. The construction of a separate effects test matrix is attempt to collect together the best sets of openly available test data for code validation, assessment and improvement, from the wide range of experiments that have been carried out world-wide in the field of thermal hydraulics. In all, 2094 tests are included in the SET matrix.
The SET matrix, as it stands, is representative of the major part of the experimental work which has been carried out in the LWR-safety thermal hydraulics field, covering a large number of phenomena within a large range of useful parameters. The SET matrix also provides a basis for evaluating the existing data base and defining the main axes for further research in LWR-safety thermal hydraulics in relation to separate effects testing.
An identification of phenomena for SET is given in OECD/GD(94)82, including basic phenomena, critical flow, phase separation/vertical flow with and without mixture level, stratification in horizontal flow, phase separation at branches, entrainment/de-entrainment, liquid-vapour mixing with condensation, condensation in stratified conditions, spray effects, countercurrent flow, heat transfer and global multidimensional fluid temperature void and flow distribution. In all, 67 hydraulic phenomena were used to relate to information provided from 187 test facilities used as potential sources of separate effects data.
- Committee on the Safety of Nuclear Installations (CSNI) Principal Working Group No.2 on Coolant System Behaviour (PWG2) Separate Effects Test Matrix for Thermal-Hydraulic Code Validation Volume I, Phenomena Characterisation and Selection of Facilities and Tests; OECD/GD(94)82 (July 1994)
- Committee on the Safety of Nuclear Installations (CSNI) Principal Working Group No.2 on Coolant System Behaviour (PWG2) Separate Effects Test Matrix for Thermal-Hydraulic Code Validation Volume II, Facilities and Experiment Characteristics; OECD/GD(94)83 (July 1994)
Last reviewed: 11 July 2011