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Major Outcomes through Recent ROSA/LSTF Experiments and Future Plans

World Journal of Nuclear Science and Technology 2021年第1期11卷 17-42页

作者： Takeshi Takeda Yuki Wada yasuteru sibamoto Nuclear Safety Research Center Japan Atomic Energy Agency Ibaraki Japan

Many experiments have been conducted on accidents and transients of pressurized water reactor (PWR) employing the rig of safety assessment/large-scale test facility (ROSA/LSTF). Recent research activities concerned with the OECD/NEA international joint projects included experimental investigation via the ROSA and ROSA-2 Projects, and counterpart testing with thermal-hydraulic integral test facilities under collaboration of the PKL-2, PKL-3, ATLAS, and ATLAS-2 Projects. Major results of the related integral effect tests (IETs) with the LSTF were reviewed to experimentally identify thermal-hydraulic phenomena involved, regarding the PWR accident sequences in accordance with the new regulatory requirements for the Japanese light-water nuclear power plants. Future separate effect test using the LSTF is planned to simulate loss of emergency core cooling system (ECCS) recirculation functions in a large-break loss-of-coolant accident (LOCA). Key results of the recent IETs utilizing the LSTF and future plans were presented relevant to multiple steam generator tube rupture accident with recovery operation, small-break LOCA with accident management measure on core exit temperature reliability, and small-break LOCA with thermal stratification under cold water injection from ECCS into cold legs. Also, main outcomes of the LSTF IETs were indicated for wide spectrum LOCA with core uncovery and anticipated transient without scram following small-break LOCA under totally failed high-pressure injection system.

关键词： PWR ROSA/LSTF LOCA ECCS Integral Effect Test

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A Study on Improvement of RANS Analysis for Erosion of Density Stratified Layer of Multicomponent Gas by Buoyant Jet in a Containment Vessel

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Journal of Energy and Power Engineering 2015年第7期9卷 599-607页

作者： Satoshi Abe Masahiro Ishigaki yasuteru sibamoto Taisuke Yonomoto Thermalhydraulic Safety Research Group Nuclear Safety Research Center Japan Atomic Energy Agency Ibaraki 319-1195 Japan

The analysis on a density stratification layer consisting of multiple gases in the reactor containment vessel is important for the safety assessment of sever accidents. The JAEA (Japan Atomic Energy Agency) has started the project on the containment thermal hydraulics. We carried out CFD (computational fluid dynamics) analyses in order to investigate the erosion of the density stratification layer by a vertical buoyant jet under this project. We used the RANS (Reynolds averaged numerical simulation) and LES (large eddy simulation) models to analyze the erosion of a density stratification layer by a vertical buoyant jet in a small vessel which represents a containment vessel. This numerical study calculates the turbulent mixing of a two-component (air and helium) gas mixture. The turbulence models used for the RANS analyses are two types of k-ε models. The first model is the low Reynolds number k-ε model developed by Launder and Sharma. The second model is modified from the first model in order to accurately consider the turbulent production and damping in a stratification layer. The results indicated while the erosion rate calculated by the low-Re k-ε model was much faster than that of the LES model, the modified k-ε model could calculate the erosion rate similar to the LES result.

关键词： RANS 气体密度浮力射流侵蚀率分析改进容器计算流体动力学多组分

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