Gressier V, Guerre-Chaley J F, Lacoste V, Lebreton L, Pelcot G, Pochat J L, Bolognese-Milstajn T, Champion D
Institut de Radioprotection et de Sûreté Nucléaire. BP 3, 13115 Saint-Paul-lez-Durance, France.
Radiat Prot Dosimetry. 2004;110(1-4):49-52. doi: 10.1093/rpd/nch185.
The variation of the response of the instruments with the neutron energy has to be determined in well-characterized monoenergetic neutron fields. The AMANDE facility will deliver such neutron fields between 2 keV and 20 MeV in an experimental hall designed with metallic walls for neutron scattering minimisation. The neutrons will be produced by nuclear interaction of accelerated protons or deuterons on thin targets of selected materials. The measuring devices to be characterised will be accurately placed with a fully automated detector transport system. The energy of the neutron field will be validated by time-of-flight experiments and a large set of standard detectors and fluence monitors will be used to determine the neutron fluence references. The scattered neutron fluence and dose equivalent were calculated by the MCNP Monte Carlo code at several measuring points in order to determine their contribution to the neutron field.
必须在特征明确的单能中子场中确定仪器响应随中子能量的变化。AMANDE设施将在一个设计有金属壁以尽量减少中子散射的实验大厅中提供能量在2 keV至20 MeV之间的此类中子场。中子将通过加速质子或氘核与选定材料的薄靶发生核相互作用产生。待表征的测量装置将通过全自动探测器传输系统精确放置。中子场的能量将通过飞行时间实验进行验证,并将使用大量标准探测器和注量监测器来确定中子注量参考值。为了确定散射中子注量和剂量当量对中子场的贡献,使用MCNP蒙特卡罗代码在几个测量点进行了计算。