The functionality of thermal-hydraulics system code, SMABRE, which has been developed at VTT Technical Research Centre of Finland, was extended to supercritical pressures. The modification was performed by means of introducing a pseudo-two-phase region, which is located along the pseudo-critical line in the supercritical pressure region. SMABRE has been coupled with three dimensional core dynamics code, TRAB-3D, also developed at VTT, for more detailed transient analysis of supercritical water-cooled reactors (SCWR). Using the internal coupling scheme, TRAB-3D performs the 3D neutronics calculation and SMABRE handles ID thermal-hydraulics modelling also in the core. High Performance Light Water Reactor (HPLWR) is a European SCWR concept that has been designed in two projects funded by the European Commission between years 2000 and 2010. Special features of the current work-in-progress design of the HPLWR include the detailed "three-pass-core" coolant flow path. Due to the use of supercritical water as coolant, HPLWR achieves a very high efficiency of 44 % and a simpler plant design since steam generators and steam dryers are omitted and coolant is driven directly to the turbines. Simulation model for HPWLR was created for TRAB-3D/SMABRE. In this paper, several transient analysis cases with neutronics feedback for HPLWR are presented. Loss of feed water transients with different assumptions were analysed with point kinetics feedback using SMABRE. Due to the effects on the 3D power profile, control rod ejection transient was analysed with the coupled TRAB-3D/SMABRE. The results show the capabilities of the tools developed for the safety analyses of present-day light water reactors in the field of SCWR analysis. With relatively speaking minor modifications the TRAB-3D and SMABRE codes can calculate transients in the supercritical pressure regime. Also, similar safety analysis procedures are possible for the SCWRs as has been routinely utilized in existing LWR safety analysis.
|Title of host publication||Proceedings of the International Congress on Advances in Nuclear Power Plants (ICAPP 2010), June 13-17, 2010, San Diego, California, USA|
|Subtitle of host publication||Embedded International Topical Meeting at the 2010 ANS Annual Meeting|
|Publisher||American Nuclear Society (ANS)|
|Publication status||Published - 2010|
|MoE publication type||A4 Article in a conference publication|