Simulation of typical accidents in fuel test loop of CMRR
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摘要: 基于中国绵阳研究堆(CMRR)高温高压辐照考验回路初步设计方案，就回路失水事故(LOCA)及失流事故(LOFA)两类典型事故进行分析。结果表明：回路在冷管段及热管段失水事故下包壳热点温度最高为880.6 ℃及367.6 ℃，均远低于1204 ℃；全部失流事故下最小偏离泡核沸腾比(MDNBR)大于1.5，不会发生偏离泡核沸腾；卡轴事故中包壳最高温度为734.1 ℃，低于1482 ℃。上述结果均满足验收准则，符合安全法规要求。
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关键词:
- 高温高压辐照考验回路 /
- 失水事故 /
- 失流事故 /
- 中国绵阳研究堆
Abstract: In order to reflect the behavior of the nuclear materials in the operating reactor veritably and roundly, and to supply reliable data for the safety review of the nuclear materials, the most effective solution is building a fuel test loop (FTL) based on the real pressurized water reactor in the research reactor. To ensure the safety of the fuel test loop and the research reactor, it is necessary to analyze the safety of the fuel test loop during accident transient. This article simulates and analyzes two typical kinds of accidents—small break loss-of-coolant accidents (LOCA) and loss-of-flow accidents (LOFA)—based on the origin design of the fuel test loop in China's Mianyang Research Reactor (CMRR). The peak cladding temperature in cold leg SBLOCA and hot leg small break LOCA is 880.6 ℃ and 367.6 ℃ respectively, which is under the critical value (1204 ℃). During the total LOFA, the MDNBR is greater than 1.5, which means there is no departure from nucleate boiling. In the clamp shaft accident, the cladding temperature is 734.1 ℃, which is less than 1482 ℃. The results obtained are consistent with the safety criteria. -
图 6 失水事故辐照装置水位
Figure 6. Coolant level in the irradiation facility during loss-of-coolant accident
图 9 失水事故CMRR冷却水温
Figure 9. Temperature of China's Mianyang Research Reactor coolant during loss-of-coolant accident
图 10 卡轴事故与失流事故主回路冷却剂流量
Figure 10. Flow rate through the irradiation facility during loss-of-flow accidents (LOFAs)
图 11 卡轴事故与失流事故回路功率
Figure 11. Power during clamp shaft accident and loss-of-flow accidents
图 12 卡轴事故与失流事故主回路压力
Figure 12. Pressure in the main loop during clamp shaft accident and loss-of-flow accidents
表 1 主回路主要设计参数
Table 1. Designed value of key parameters of primary loop
power/kW primary loop pressure/MPa argon gap pressure/MPa coolant flow rate/(kg·s-1) inlet coolant temperature/K outlet coolant temperature/K 60 15.5 0.165 3.5 553 583 
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表 2 系统稳态参数
Table 2. Key parameters in steady-state
power/ kW pressure/ MPa inlet coolant temperature/℃ outlet coolant temperature/℃ main loop coolant flow rate/(kg·s-1) argon gap pressure/ MPa cladding temperature/ K design value 600 15.500 280.00 310.00 3.500 0.165 630.00 RELAP5 calculation value 600 15.556 278.89 310.41 3.476 0.175 640.63
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