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钍基熔盐堆石墨材料辐照考验目标为:中子注量为5×10~(20)cm~(-2)(±15%)(E>0.1 Me V),堆内辐照试验温度650℃(允许偏差±50℃)。为了满足辐照考验要求,在高通量工程试验反应堆(HFETR)第92-I炉的K07孔道进行辐照验证试验。该验证试验辐照装置采用分段构成的型式,主要由辅助密封段、辐照试验段、气管组件3部分构成,辐照罐外围为去离子水,辐照罐内为惰性气体用于控制辐照试验温度。使用MCNP程序对各样品中子注量进行预示计算,同时在辐照装置阳面和阴面都布置了探测器进行中子注量测量。试验表明:在辐照试验过程中,在辐照装置调气系统最佳导热模式下辐照温度略高于上限700℃;利用MCNP程序预示计算中子注量结果为5.7×10~(20)cm~(-2)(E>0.1 Me V),而中子注量测量结果为4.83×10~(20)cm~(-2)(E>0.1 Me V),基本满足石墨材料辐照考验中子注量要求。
Thorium-based fused salt reactor graphite material irradiation test objectives: neutron fluence of 5 × 10 ~ (20) cm ~ (-2) (± 15%) (E> 0.1MeV), the reactor radiation test temperature 650 ℃ (allowable deviation ± 50 ℃). In order to meet the requirements of the irradiation test, a radiation verification test was conducted on the K07 tunnel of a 92-I furnace of a high-throughput engineering test reactor (HFETR). The verification test irradiating device adopts a segmented structure type, which is mainly composed of an auxiliary sealing section, an irradiation test section and a trachea assembly. The periphery of the irradiation tank is deionized water, and the irradiation tank is an inert gas for controlling the radiation According to the test temperature. The MCNP program was used to predict the neutron flux in each sample. At the same time, detectors were placed on both the sun and the cathode of the irradiation device for neutron fluence measurement. The experimental results show that the irradiation temperature is slightly higher than the upper limit of 700 ℃ during the irradiation experiment, and the predicted neutron flux of MCNP program is 5.7 × 10 ~ (20) cm -2 (E> 0.1 Me V), while the neutron fluence measurement was 4.83 × 10-20 cm -2 (E> 0.1 Me V), which basically satisfied the test of irradiation of graphite material Neutron fluence requirements.