Method and apparatus for measurement of concentration of thermal neutron absorber contained in nuclear fuel专利检索-核燃料棒燃料组件堆芯核反应堆核能电厂发电厂分销网络和设备专利检索查询-专利查询网

Method and apparatus for measurement of concentration of thermal neutron absorber contained in nuclear fuel

阅读：134发布：2022-01-29

专利汇可以提供Method and apparatus for measurement of concentration of thermal neutron absorber contained in nuclear fuel专利检索，专利查询，专利分析的服务。并且Nuclear fuel samples containing burnable poisons are irradiated with epithermal neutrons and the neutron emission rate is counted to provide a measurement of fissile content through comparisons with the results of like steps performed on reference fuels. Where the fissile content is known, poison content is determined through irradiation of the sample with thermal neutrons. The presence of the poisons depresses the thermal neutron flux within the fuel and reduces the number of fission neutrons emitted. This emission rate is compared with the results of like steps performed on reference rods to indicate poison content. In another embodiment gamma emission by the fissile species is used in conjunction with thermal neutron interrogation to measure both fissile and absorber content.，下面是Method and apparatus for measurement of concentration of thermal neutron absorber contained in nuclear fuel专利的具体信息内容。

权利要求

1. A method for determining the concentration of non-fissionable thermal neutron absorbers in sample nuclear fuel of known fissile content by comparison with the fast fission neutron emission rate of a reference fuel irradiated with thermal neutrons, said reference fuel containing a fissile content substantially equal to said known fissile content, and a known non-fissionable thermal neutron absorber content, the method comprising the steps of irradiating said sample fuel with thermal neutrons, measuring the emission rate of fast fission neutrons from said sample fuel, and comparing said emission rate of the sample fuel with said emission rate of the reference fuel to provide an indication of said non-fissionable neutron absorber content of the sample fuel.

2. The method of claim 1 in which the reference fuels include a plurality of fuel elements comprising varying known fissile content and known non-fissionable thermal neutron absorber content from which there has been established a parametric relationship of said reference fuel emission rates as a function of fissile content and non-fissionable neutron absorber content, wherein said comparison step comprises comparing the emission rate of the sample fuel with a like emission rate and fissile content of said parametric relationship to provide said indication of the non-fissionable neutron absorber content.

3. A method of determining the unknown fissile content of sample nuclear fuel in the presence of non-fissionable thermal neutron absorbers comprising the steps of irradiating a plurality of reference fuels with epithermal neutrons, said reference fuels comprising varying known fissile contents, measuring the emission rate of fast fission neutrons frOm each of the reference fuels and establishing therefrom a parametric relationship of emission rate as a function of fissile content, irradiating said sample fuel with epithermal neutrons, measuring the emission rate of fast fission neutrons from said sample fuel, and comparing said emission rate of the sample fuel with a like emission rate of said parametric relationship to provide an indication of said unknown fissile content, irradiating said sample fuel with thermal neutrons, measuring the emission rate of fast fission neutrons generated by said thermal neutrons, and correcting said last mentioned measurement for said indicated fissile content of the sample fuel to provide a measurement of the non-fissionable thermal neutron absorber content of the sample.

4. A method for determining the concentration of non-fissionable neutron absorbers and fissile content in sample nuclear fuel comprising the steps of irradiating a plurality of reference fuels with thermal neutrons, said reference fuels comprising varying known fissile and known non-fissionable thermal neutron absorber contents, measuring the emission rates of gamma rays and fast fission neutrons from each of the reference fuels and establishing therefrom a parametric relationship of gamma ray emission rate as a function of non-fissionable neutron absorber content and a parametric relationship of fast fission neutron emission rate as a function of fissile content, irradiating said sample fuel with thermal neutrons, measuring the emission rate of gamma rays from said sample fuel, comparing said gamma emission rate of the sample with said first mentioned parametric relationship to indicate the non-fissionable neutron absorber content of the sample fuel, measuring the emission rate of fast fission neutrons from said sample fuel, and comparing the said neutron emission rate of the sample with said last mentioned parametric relationship to indicate the fissile content of the sample fuel.

5. Apparatus for determining the concentration of non-fissionable thermal neutron absorption and fissile content in sample nuclear fuel including the combination of a source of neutrons, means to moderate the source neutrons to within the thermal energy range for irradiation thereof into said fuel, means to measure fast fission neutrons radiating from the fuel as an indication of said absorber concentration, means to measure gamma ray radiation from the fuel as an indication of said fissile content, and means to shield the gamma ray measuring means from gamma rays emitted from the neutron source.

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Method and apparatus for measurement of concentration of thermal neutron absorber contained in nuclear fuel

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