Two tests initiated by unscrammed control rod withdrawal were performed on the High Temperature GasCooled Reactor-Test Module(HTR-10) in November 2003 after the reactor achieved its full power, and the test conditions...Two tests initiated by unscrammed control rod withdrawal were performed on the High Temperature GasCooled Reactor-Test Module(HTR-10) in November 2003 after the reactor achieved its full power, and the test conditions represented a typical transient scenario of modular high-temperature reactors(HTRs), called pressurized loss of forced cooling, and anticipated transient without scram.Based on the test parameters, the HTR-10 thermal behaviors under the test conditions were studied with the help of the system analysis code THERMIX. The combination of the test results and the investigation results makes the HTR-10 safety potential better understood. Key phenomena, such as the helium natural circulation and the temperature redistribution in the reactor, were revealed. As the safety feature of most significance, there is a large margin between the maximum fuel temperature and its safety limit in each test. Temperatures of thermocouples in different components were calculated by THERMIX and compared with the test values. The applicability of the code was verified by good agreement obtained from the comparison.展开更多
The HTR-10 is a small modular high-temperature reactor located in Tsinghua University,in China.After the reactor ran continuously for 72 h at full power in the commissioning stage,a full load rejection test was conduc...The HTR-10 is a small modular high-temperature reactor located in Tsinghua University,in China.After the reactor ran continuously for 72 h at full power in the commissioning stage,a full load rejection test was conducted by manually disconnecting the generator from the grid.In this study,reactor transients were analyzed using the THERMIX model.Some of the important thermal–fluid phenomena that occurred after the test initiation are discussed here,including the natural convection of helium in the core and the temperature redistribution in the reactor.Temperatures reproduced for the measuring points arranged in the internals were in agreement with the test data.This demonstrated that the code and calculation model are suitable for posttest analysis applications.Regarding the safety features of the reactor,there was a large margin between the predicted maximum fuel temperature of 997℃and the safety limit of 1620℃.展开更多
基金supported by the Chinese National S&T Major Project(No.ZX069)
文摘Two tests initiated by unscrammed control rod withdrawal were performed on the High Temperature GasCooled Reactor-Test Module(HTR-10) in November 2003 after the reactor achieved its full power, and the test conditions represented a typical transient scenario of modular high-temperature reactors(HTRs), called pressurized loss of forced cooling, and anticipated transient without scram.Based on the test parameters, the HTR-10 thermal behaviors under the test conditions were studied with the help of the system analysis code THERMIX. The combination of the test results and the investigation results makes the HTR-10 safety potential better understood. Key phenomena, such as the helium natural circulation and the temperature redistribution in the reactor, were revealed. As the safety feature of most significance, there is a large margin between the maximum fuel temperature and its safety limit in each test. Temperatures of thermocouples in different components were calculated by THERMIX and compared with the test values. The applicability of the code was verified by good agreement obtained from the comparison.
基金supported by the Chinese National S&T Major Project(No.ZX069)
文摘The HTR-10 is a small modular high-temperature reactor located in Tsinghua University,in China.After the reactor ran continuously for 72 h at full power in the commissioning stage,a full load rejection test was conducted by manually disconnecting the generator from the grid.In this study,reactor transients were analyzed using the THERMIX model.Some of the important thermal–fluid phenomena that occurred after the test initiation are discussed here,including the natural convection of helium in the core and the temperature redistribution in the reactor.Temperatures reproduced for the measuring points arranged in the internals were in agreement with the test data.This demonstrated that the code and calculation model are suitable for posttest analysis applications.Regarding the safety features of the reactor,there was a large margin between the predicted maximum fuel temperature of 997℃and the safety limit of 1620℃.
