A novel method was developed to separate the 238 U fission contribution measured in quasi-differential time-of-flight scattering experiments order isolate elastic and inelastic events. Pulse height distributions from in-beam measurements were used generate response functions, which reconstruct prompt neutron spectra. This validated by reconstructing 252 Cf spontaneous pulse distribution. Monte ...

In this paper we propound a non­destructive and non­invasive technique for measuring the thickness of water penetration in a homogeneous slab. The proposed device consists of a 252 Cf spontaneous fission source and a set of 3 He detectors located on the same side of a concrete slab subject to water infiltration. The effectiveness of this technique has been investigated by Monte Carlo simulation...

This paper presents the validation of the Monte Carlo code MCNP-PoliMi for the simulation of nuclear safeguards experiments with plutonium and uranium metal based on fast time-correlation measurements. A comparison is presented between experimental data acquired with the Nuclear Materials Identification System and the Monte Carlo simulations. The measurements and simulations were performed for ...

یکی از پارامترهای مهم محیط­های پخش نوترون، طول نوترون حرارتی است. روش مرسوم محاسباتی استفاده کد MCNP برمبنای توزیع شار در محیط و برازش تابع ریاضی مربوطه بر آن این پژوهش، روشی نوین که مبنای کارت PTRAC است، ارایه شده پارامتر برای آب­سبک اساس روش­های فوق محاسبه با مقادیر گزارش مراجع مقایسه گردیده تطابق خوبی نیز مشاهده حسن فوق، عدم نیاز به علاوه فرض می­شود تا محل چشمه، فاصله­ی کافی وجود دارد. مسأله...