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Determination of neutron temperature in irradiation channels of reactor

机译:反应堆辐照通道中子温度的测定

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摘要

The neutron temperature is a characteristic parameter in irradiation channels of reactor. For nuclides which have resonances in the thermal neutron energy range, their Westcott g-factors are different from unity. The values of g-factors and cross-sections of (n, γ) reaction of these nuclides are temperature dependence. The standard energy for tabulation of thermal neutron cross-section (σ0) is that of room temperature (293.59 K or 20.43 °C), corresponding to a neutron energy 0.0253 eV or to a neutron velocity of 2200 m/s. However, in the irradiation channels of reactor, the temperature is not exact at 20.43 °C. Thus, the temperature at the irradiation position must be known to convert σ0 to σ(T). A method for determination of the neutron temperature in irradiation channels of Dalat reactor is presented by fitting the thermal neutron spectrum obtained from the calculation using MCNP code.
机译:中子温度是反应堆辐照通道中的特征参数。对于在热中子能量范围内具有共振的核素,它们的Westcott g因子不同于一。这些核素的g因子和(n,γ)反应截面的值与温度有关。制表热中子截面(σ0)的标准能量是室温(293.59 K或20.43°C)的能量,对应于中子能量0.0253 eV或中子速度2200 m / s。但是,在反应器的辐照通道中,温度不精确到20.43°C。因此,必须知道照射位置的温度才能将σ0转换为σ(T)。通过使用MCNP代码拟合从计算中获得的热中子谱,提出了一种确定大叻反应堆辐照通道中子温度的方法。

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