Benchmarking Monte Carlo Simulations of Thermal Neutron Kinetics and Differential Die-away Analysis
نویسندگان
چکیده
Differential Die-Away Analysis (DDAA) is a very effective technique for detection of special nuclear material (SNM). It is based on fission neutrons that are detected with a time constant characteristic of the thermal neutron that created them. The presence of fast neutrons with this slow die-away time is a positive indication of the presence of SNM in the inspected cargo. Results are presented from MCNPX simulations of pulsed neutron interrogation of hydrogenous cargo. MCNPX is first used to simulate the thermal neutron die-away times of the cargo. Next, it is used to simulate the fast-neutron die-away times of the cargo with SNM present, and the gross signal of a full DDAA measurement modeled against a set of experiments. These results are benchmarked against these experimental measurements. MCNPX is in good agreement with measurement of thermal die-away times. The differential die-away signature, which appears on the order of tens to hundreds of microseconds after a neutron pulse, can be modeled accurately for hydrogenous cargoes.
منابع مشابه
Monte Carlo characterization of photoneutrons in the radiation therapy with high energy photons: a Comparison between simplified and full Monte Carlo models
Background: The characteristics of secondary neutrons in a high energy radiation therapy room were studied using the MCNPX Monte Carlo (MC) code. Materials and Methods: Two MC models including a model with full description of head components and a simplified model used in previous studies were implemented for MC simulations. Results: Results showed 4-53% difference between full and wit...
متن کاملA Monte Carlo Study on the Effect of Various Neutron Capturers on Dose Distribution in Brachytherapy with 252Cf Source
Background: In neutron interaction with matter and reduction of neutron energy due to multiple scatterings to the thermal energy range, increasing the probability of thermal neutron capture by neutron captures makes dose enhancement in the tumors loaded with these materials. Objective: The purpose of this study is to evaluate dose distribution in the presence of 10B, 157Gd and 33S neutron...
متن کاملExperimental and Monte Carlo studies on the response of CR-39 detectors to Am-Be neutron spectrum
Background: The Poly-Allyl Diglycol Carbonate (PADC) detector is of particular interest for development of a fast neutron dosimeter. Fast neutrons interact with the constituents of the CR-39 detector and produce H, C and O recoils, as well as (n, α) reaction. These neutron- induced charged particles contribute towards the response of CR-39 detectors. Material and Methods: Electrochemical...
متن کاملOptimised BNCT facility based on a compact D-D neutron generator
Background: Boron Neutron Capture Therapy (BNCT) is a very promising treatment for patients suffering gliobastoma multiforme, an aggressive type of brain cancer, where conventional radiation therapies fail. Thermal neutrons are suitable for the direct treatment of cancers which are located at near-tissue-surface deep-seated tumors need harder, epithermal neutron energy spectra. Materials and Me...
متن کاملBenchmarking of Monte Carlo model of 6 Mv photon beam produced by Siemens Oncor® linear accelerator: determination of initial electron beam parameters in comparison with measurement
Introduction: The aim of this study was to investigate the initial electron beam parameters for Monte Carlo model of 6MV photon beam produced by Siemens Oncor® linear accelerator. Materials and Methods: In this study, the EGSnrc Monte Carlo user codes BEAMnrc and DOSXYZnrc were used. The beamnrc code were used for modelling of a 6 MV photon beam produced by...
متن کامل