tailieunhanh - Gamma ray transport simulations using SGaRD code

SGaRD (Spectroscopy, Gamma rays, Rapid, Deterministic) code is used for the fast calculation of the gamma-ray spectrum, produced by a spherical shielded source and measured by a detector. The photon source lines originate from the radioactive decay of the unstable isotopes. | Gamma ray transport simulations using SGaRD code EPJ Nuclear Sci. Technol. 3 9 2017 Nuclear Sciences P. Humbert and B. Méchitoua published by EDP Sciences 2017 amp Technologies DOI epjn 2017006 Available online at http REGULAR ARTICLE Gamma ray transport simulations using SGaRD code Philippe Humbert and Boukhmès Méchitoua CEA DAM Ile-de-France Bruyères-le-Châtel 91297 Arpajon cedex France Received 18 November 2016 Received in final form 7 February 2017 Accepted 15 February 2017 Abstract. SGaRD Spectroscopy Gamma rays Rapid Deterministic code is used for the fast calculation of the gamma-ray spectrum produced by a spherical shielded source and measured by a detector. The photon source lines originate from the radioactive decay of the unstable isotopes. The leakage spectrum is separated in two parts the uncollided component is transported by ray tracing and the scattered component is calculated using a multigroup discrete ordinates method. The pulse height spectrum is then simulated by folding the leakage spectrum with the detector response function which is precalculated for each considered detector type. An application to the simulation of the gamma spectrum produced by a natural uranium ball coated with plexiglass and measured using a NaI detector is presented. The SGaRD code is also used to infer the dimensions of a one-dimensional model of a shielded gamma ray source. The method is based on the simulation of the uncollided leakage current of discrete gamma lines that are produced by nuclear decay. The material thicknesses are computed with SGaRD using a fast ray-tracing algorithm embedded in a nonlinear multidimensional iterative optimization procedure that minimizes the error metric between calculated and measured signatures. 1 Introduction In the second part we present the identification of nuclear radiation-source characteristics which is a subject of Real-time applications require fast and accurate calculation interest for .

• Năng lượng
• Gamma ray spectrum
• Gamma ray transport simulations
• Ray tracing algorithm
• Nuclear radiation source characteristics
• MonteCarlo code MCNP5