Abstract
| Original language | English |
|---|---|
| Title of host publication | BALTICA VII - Life Management and Maintenance for Power Plants. Vol. 1 |
| Place of Publication | Espoo |
| Publisher | VTT Technical Research Centre of Finland |
| Pages | 235-235 |
| Number of pages | 1 |
| ISBN (Electronic) | 978-951-38-6316-6 |
| ISBN (Print) | 978-951-38-6315-9 |
| Publication status | Published - 2007 |
| Event | BALTICA VII - International Conference on Life Management and Main-tenance for Power Plants - Helsinki-Stockholm, Finland Duration: 12 Jun 2007 → 14 Jun 2007 |
Publication series
| Series | VTT Symposium |
|---|---|
| Number | 246 |
| ISSN | 0357-9387 |
Conference
| Conference | BALTICA VII - International Conference on Life Management and Main-tenance for Power Plants |
|---|---|
| Country | Finland |
| City | Helsinki-Stockholm |
| Period | 12/06/07 → 14/06/07 |
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Modelling of supercritical conditions in the safety analysis codes. / Vanttola, Timo; Hänninen, Markku; Daavittila, Antti.
BALTICA VII - Life Management and Maintenance for Power Plants. Vol. 1. Espoo : VTT Technical Research Centre of Finland, 2007. p. 235-235 (VTT Symposium; No. 246).Research output: Chapter in Book/Report/Conference proceeding › Conference abstract in proceedings › Scientific
TY - CHAP
T1 - Modelling of supercritical conditions in the safety analysis codes
AU - Vanttola, Timo
AU - Hänninen, Markku
AU - Daavittila, Antti
PY - 2007
Y1 - 2007
N2 - Thermal hydraulic modelling is needed for describing processes that use water for cooling. Simulator codes solve conservation equations of coolant mass, momentum and energy using numerical methods. Additionally, correlation based models are needed for describing, among others, heat transfer and friction between the structures and the coolant. In two-phase flow the correlations for interfacial heat transfer and friction are used for exchanging of mass, momentum and energy between liquid and gas phases. Typical applications are various boiler processes and nuclear reactors. Some modern boilers operate in supercritical water conditions as well as a new nuclear reactor concept SCWR (Super Critical Water Cooled Reactor). Water properties change fast around the critical point (220.64 bar, 374.15 C) and heat transfer in supercritical state is not fully understood, which makes modelling challenging and is typically beyond normal operation regime of the analysis codes. At the moment VTT is modifying two of its code packages, APROS and TRAB-SMABRE to adapt for supercritical conditions. APROS is a general purpose simulation code both for nuclear and non-nuclear applications, while TRAB-SMABRE is used solely for nuclear reactor analysis. The models for water properties, such as density, specific heat capacity and heat conductivity, have already been developed. The homogeneous water model of APROS (3 conservation equations) has already been tested in supercritical boiler conditions and operates in principle. The more sophisticated operation mode of APROS (6 conservation equations) operates in supercritical state but the transition from supercritical to subcritical two-phase state has not yet been tested. The correlation package of heat transfer and friction has to be tested and possibly modified in supercritical conditions. The testing of the TRAB-SMABRE code (5 conservation equations) is to be started soon. TRAB-SMABRE and possibly also APROS are to be applied for reactivity transient analysis of the European development version of the supercritical water reactor in the Euratom 6th Framework Programme project High Performance Light Water Reactor, HPLWR Phase 2.
AB - Thermal hydraulic modelling is needed for describing processes that use water for cooling. Simulator codes solve conservation equations of coolant mass, momentum and energy using numerical methods. Additionally, correlation based models are needed for describing, among others, heat transfer and friction between the structures and the coolant. In two-phase flow the correlations for interfacial heat transfer and friction are used for exchanging of mass, momentum and energy between liquid and gas phases. Typical applications are various boiler processes and nuclear reactors. Some modern boilers operate in supercritical water conditions as well as a new nuclear reactor concept SCWR (Super Critical Water Cooled Reactor). Water properties change fast around the critical point (220.64 bar, 374.15 C) and heat transfer in supercritical state is not fully understood, which makes modelling challenging and is typically beyond normal operation regime of the analysis codes. At the moment VTT is modifying two of its code packages, APROS and TRAB-SMABRE to adapt for supercritical conditions. APROS is a general purpose simulation code both for nuclear and non-nuclear applications, while TRAB-SMABRE is used solely for nuclear reactor analysis. The models for water properties, such as density, specific heat capacity and heat conductivity, have already been developed. The homogeneous water model of APROS (3 conservation equations) has already been tested in supercritical boiler conditions and operates in principle. The more sophisticated operation mode of APROS (6 conservation equations) operates in supercritical state but the transition from supercritical to subcritical two-phase state has not yet been tested. The correlation package of heat transfer and friction has to be tested and possibly modified in supercritical conditions. The testing of the TRAB-SMABRE code (5 conservation equations) is to be started soon. TRAB-SMABRE and possibly also APROS are to be applied for reactivity transient analysis of the European development version of the supercritical water reactor in the Euratom 6th Framework Programme project High Performance Light Water Reactor, HPLWR Phase 2.
M3 - Conference abstract in proceedings
SN - 978-951-38-6315-9
T3 - VTT Symposium
SP - 235
EP - 235
BT - BALTICA VII - Life Management and Maintenance for Power Plants. Vol. 1
PB - VTT Technical Research Centre of Finland
CY - Espoo
ER -