Measurement of Neutron Spectrum Parameters of Miniature Neutron Source Reactor
Fu Hongyu
Abstract
Fu Hongyu
Abstract
The neutron spectrum parameters of the miniature neutron source reactor(MNSR) in China Institute of Atomic Energy were measured by bare monitor method using Au,Zr and Fe as monitors.The measured values of α(a parameter accounting for the non-ideality of the 1/E epithermal neutron fluence rate distribution),f(thermal / epithermal neutron fluence rate) and fF(thermal / fast neutron fluence rate) in the inner irradiation site are-0.007±0.003,20.8±0.4,and 5.5±0.2,respectively.The value of φth measured by this method is agreed with that measured by 4πβ-γ method within 2%.Compared with SLOWPOKE,MNSR had higher values of α and fF.The com-parison with the previous measurements indicates that MNSR has a quite constant neutron spectrum.The fluence rate monitors are not needed when k0-NAA is performed by using MNSR as neutron source,and with occasional check,the comparator data from one measurement may be used as a standard for subsequent analyses over a period of time.
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The neutron spectrum parameters of the miniature neutron source reactor(MNSR) in China Institute of Atomic Energy were measured by bare monitor method using Au,Zr and Fe as monitors.The measured values of α(a parameter accounting for the non-ideality of the 1/E epithermal neutron fluence rate distribution),f(thermal / epithermal neutron fluence rate) and fF(thermal / fast neutron fluence rate) in the inner irradiation site are-0.007±0.003,20.8±0.4,and 5.5±0.2,respectively.The value of φth measured by this method is agreed with that measured by 4πβ-γ method within 2%.Compared with SLOWPOKE,MNSR had higher values of α and fF.The com-parison with the previous measurements indicates that MNSR has a quite constant neutron spectrum.The fluence rate monitors are not needed when k0-NAA is performed by using MNSR as neutron source,and with occasional check,the comparator data from one measurement may be used as a standard for subsequent analyses over a period of time.
Key concepts: Neutron source, Neutron temperature, Neutron flux, Neutron, Neutron cross section, Fluence, Irradiation, Materials science