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1. 发明授权

US4622200A Non-destructive method for determining neutron exposure and constituent concentrations of a body 失效
标题翻译：用于确定中子暴露和身体成分浓度的非破坏性方法
公开(公告)号：US4622200A
公开(公告)日：1986-11-11
申请号：US582510
申请日：1984-02-22
申请人： Raymond Gold , William N. McElroy
发明人： Raymond Gold , William N. McElroy
IPC分类号： G01N23/222 , G21C17/00
CPC分类号： G01N23/222 , G01N2223/01 , G01N2223/0745 , G01N2223/626
摘要： A non-destructive method for determination of neutron exposure and constituent concentrations in an object, such as reactor pressure vessel, is based on the observation of characteristic gamma-rays emitted by activation products in the object by using a unique continuous gamma-ray spectrometer. The spectrometer views the object through appropriate collimators to determine the absolute emission rate of these characteristic gamma-rays, thereby ascertaining the absolute activity of given activation products in the object. These data can then be used to deduce the spatial and angular dependence of neutron exposure or the spatial constituent concentration at regions of interest within the object.
摘要翻译：用于确定物体（例如反应堆压力容器）中的中子暴露和组分浓度的非破坏性方法是基于通过使用独特的连续γ射线光谱仪观察物体中的活化产物发射的特征γ射线。光谱仪通过适当的准直仪观察物体，以确定这些特征性γ射线的绝对排放速率，从而确定物体中给定活化产物的绝对活性。然后可以使用这些数据来推断中子曝光的空间和角度依赖性或物体内感兴趣区域的空间成分浓度。

2. 发明授权

US4744939A Method for correcting for isotope burn-in effects in fission neutron dosimeters 失效
标题翻译：用于校正裂变中子剂量计中同位素燃烧效应的方法
公开(公告)号：US4744939A
公开(公告)日：1988-05-17
申请号：US897555
申请日：1986-08-18
申请人： Raymond Gold , William N. McElroy
发明人： Raymond Gold , William N. McElroy
IPC分类号： G01T3/00 , G01T5/10 , G21G1/08 , G01T5/00
CPC分类号： G01T3/00 , G01T5/10
摘要： A method is described for correcting for effect of isotope burn-in in fission neutron dosimeters. Two quantities are measured in order to quantify the "burn-in" contribution, namely P.sub.Z',A', the amount of (Z', A') isotope that is burned-in, and F.sub.Z', A', the fissions per unit volume produced in the (Z', A') isotope. To measure P.sub.Z', A', two solid state track recorder fission deposits are prepared from the very same material that comprises the fission neutron dosimeter, and the mass and mass density are measured. One of these deposits is exposed along with the fission neutron dosimeter, whereas the second deposit is subsequently used for observation of background. P.sub.Z', A' is then determined by conducting a second irradiation, wherein both the irradiated and unirradiated fission deposits are used in solid state track recorder dosimeters for observation of the absolute number of fissions per unit volume. The difference between the latter determines P.sub.Z', A' since the thermal neutron cross section is known. F.sub.Z', A' is obtained by using a fission neutron dosimeter for this specific isotope, which is exposed along with the original threshold fission neutron dosimeter to experience the same neutron flux-time history at the same location. In order to determine the fissions per unit volume produced in the isotope (Z', A') as it ingrows during the irradiation, B.sub.Z', A', from these observations, the neutron field must generally be either time independent or a separable function of time t and neutron energy E.

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