GaN Radiation Detection Research Based on Monte Carlo Method

2014 ◽  
Vol 668-669 ◽  
pp. 1011-1014
Author(s):  
Yang Liu ◽  
Guo Zheng Zhu ◽  
Zhen Ni Xing
Keyword(s):  
Monte Carlo ◽  
Energy Deposition ◽  
Detection Efficiency ◽  
Hadron Collider ◽  
Radiation Detection ◽  
Radiation Energy ◽  
Radiation Detectors ◽  
Detection Mechanism ◽  
Radiation Beam ◽  
The Impact

Gallium nitride (GaN) is the third generation of semiconductor material; it has a large band gap, high thermal conductivity, low dielectric constant, high drift speed, etc. Radiation detectors based on GaN material have small volume, high radiation resistance, and fast response, can be used to replace the existing Large Hadron Collider vertex detector and track detector. Energy deposition characteristic of GaN detectors to radiation beam is an important factor for detection efficiency, and there are many factors that affect the energy deposition characteristics of the detector, like the detection mechanism, the impact of material properties, the type of incident ray, radiation energy, and many other factors. This paper studies the physical properties of GaN detector by calculation based on Monte Carlo simulation. Energy deposition characteristics are discussed respectively for incident γ-ray with different energy, in the front-end and back-end add PTFE material. The results of our study present the theoretical properties of GaN radiation detectors.

Low-Flux Neutron Radiation Detection Technology with High Sensitivity

2014 ◽  
Vol 668-669 ◽  
pp. 924-927
Author(s):  
Yang Liu ◽  
Zhen Ni Xing ◽  
Guo Zheng Zhu
Keyword(s):  
Energy Deposition ◽  
Plastic Scintillator ◽  
Detection Efficiency ◽  
Radiation Detection ◽  
High Sensitivity ◽  
Neutron Radiation ◽  
Fission Neutron ◽  
Deposition Flux ◽  
Low Intensity ◽  
Detection Technology

Boron-containing plastic scintillator detectors have a high detection efficiency for low-intensity thermal neutrons and fast neutrons which is currently the preferred types of neutron detector. This article is based on Monte Carlo method, studied boron-containing plastic scintillator for neutron detection performance, and analysis the energy deposition flux characteristics and detection efficiency when low intensity fission neutron incident to the boron plastic scintillator. We obtain the low-flux neutron detector performance in a variety of neutron source energy, boron-containing plastic scintillator diameter and length. Results showed that, when the boron-containing plastic scintillator lengths increase, the energy deposition flux will increase. When the length and diameter is constant, increasing source strength can increase the energy deposition flux brought by the recoil proton to a certain extent. When the source intensity over after thermal neutrons, due to the decrease of the cross section, the energy deposition fluxes brought by the react of neutrons and will decrease. The results provide help for low intensity fission neutron radiation detection technology with high sensitivity.

scholarly journals A Novel Portable Gamma Radiation Sensor Based on a Monolithic Lutetium-Yttrium Oxyorthosilicate Ring

Sensors ◽  
2021 ◽  
Vol 21 (10) ◽  
pp. 3376
Author(s):  
Xi Zhang ◽  
Qiangqiang Xie ◽  
Siwei Xie ◽  
Xin Yu ◽  
Jianfeng Xu ◽  
...  
Keyword(s):  
Gamma Radiation ◽  
Gamma Rays ◽  
Detection Efficiency ◽  
Radiation Detection ◽  
Radiation Detectors ◽  
Large Field ◽  
Average Error ◽  
Detection Accuracy ◽  
Environmental Radiation ◽  
Radiation Sensor

Portable radiation detectors are widely used in environmental radiation detection and medical imaging due to their portability feature, high detection efficiency, and large field of view. Lutetium-yttrium oxyorthosilicate (LYSO) is a widely used scintillator in gamma radiation detection. However, the structure and the arrangement of scintillators limit the sensitivity and detection accuracy of these radiation detectors. In this study, a novel portable sensor based on a monolithic LYSO ring was developed for the detection of environmental radiation through simulation, followed by construction and assessments. Monte Carlo simulations were utilized to prove the detection of gamma rays at 511 keV by the developed sensor. The simulations data, including energy resolutions, decoding errors, and sensitivity, showed good potential for the detection of gamma rays by the as-obtained sensor. The experimental results using the VA method revealed decoding errors in the energy window width of 50 keV less than 2°. The average error was estimated at 0.67°, a sufficient value for the detection of gamma radiation. In sum, the proposed radiation sensor appears promising for the construction of high-performance radiation detectors and systems.

scholarly journals Influence of tube volume on measurement uncertainty of GM counters

2010 ◽  
Vol 25 (1) ◽  
pp. 46-50 ◽  
Author(s):  
Koviljka Stankovic ◽  
Milos Vujisic ◽  
Ljubinko Delic
Keyword(s):  
Measurement Uncertainty ◽  
Current Pulse ◽  
Electrical Breakdown ◽  
Radiation Detection ◽  
Random Variable ◽  
Radiation Energy ◽  
Radiation Detectors ◽  
Free Electrons ◽  
Elementary Processes ◽  
Reading System

GM counters are often used in radiation detection since they generate a strong signal which can be easily detected. The working principal of a GM counter is based on the interaction of ionizing radiation with the atoms and molecules of the gas present in the counter's tube. Free electrons created as a result of this interaction become initial electrons, i. e. start an avalanche process which is detected as a pulse of current. This current pulse is independent of the energy imparted on the gas, that being the main difference between a GM counter and the majority of other radiation detectors. In literature, the dependence on the incidence of radiation energy, tube's orientation and characteristics of the reading system are quoted as the main sources of measurement uncertainty of GM counters. The aim of this paper is to determine the dependence of measurement uncertainty of a GM counter on the volume of its counter's tube. The dependence of the pulse current on the size of the counter's tube has, therefore, been considered here, both in radial and parallel geometry. The initiation and expansion of the current pulse have been examined by means of elementary processes of electrical discharge such as the Markov processes, while the changes in the counter's tube volume were put to test by the space - time enlargement law. The random variable known as the 'current pulse in the counter's tube' (i. e. electrical breakdown of the electrode configuration) has also been taken into account and an appropriate theoretical distribution statistically determined. Thus obtained theoretical results were then compared to corresponding experimental results established in controlled laboratory conditions.

scholarly journals Influence of radiation energy and angle of incidence on the uncertainty in measurements by GM counters

2008 ◽  
Vol 23 (1) ◽  
pp. 41-42 ◽  
Author(s):  
Koviljka Stankovic ◽  
Milos Vujisic
Keyword(s):  
Gamma Radiation ◽  
Detection Efficiency ◽  
Radiation Detection ◽  
Radiation Energy ◽  
Incident Radiation ◽  
Angle Of Incidence ◽  
Geometrical Probability

This paper discusses the influence of radiation energy and angle of incidence as possible sources of uncertainties in measurements performed by GM counters. Based on the detection efficiency of GM counters, it has been concluded that the energy of incident radiation does not contribute to the overall uncertainty. The angle of incident radiation does contribute to overall uncertainty, but only in the case of gamma radiation detection. In that case, the uncertainty should be determined by using geometrical probability.

scholarly journals SIMULATION OF PHOTON AND ELECTRON TRANSPORT BY MONTE CARLO METHOD

2010 ◽  
Vol 13 (2) ◽  
pp. 5-14
Author(s):  
Tan Thanh Nguyen ◽  
Phuong Nguyen Dang ◽  
Loan Thi Hong Truong
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Detection Efficiency ◽  
Radiation Transport ◽  
Radiation Detection ◽  
Dose Calculation ◽  
Radiation Shielding ◽  
Fast Calculation ◽  
Transport Simulation ◽  
Program Show

There are many radiation transport simulation codes using Monte Carlo method in the world nowaday. These codes have many applications such as: dose calculation, investigating radiation detection efficiency, designing radiation shielding, . . . However, these codes are too expensive or too difficult to be applied in many different specific purposes. In this work, we built a radiation transport simulation program based on Monte Carlo method using C++ programing language with the purpose of fast calculation and easy to use. The simulation results of this program show a good agreement in compared to MCNP results.

scholarly journals Some Considerations on the Energy Deposition During a RIA Transient Based On Monte Carlo Simulations

2021 ◽  
Vol 253 ◽  
pp. 04005
Author(s):  
Julia Bartos ◽  
Adrien Gruel ◽  
Claire Vaglio-Gaudard ◽  
Christine Coquelet-Pascal
Keyword(s):  
Monte Carlo ◽  
Energy Distribution ◽  
Energy Deposition ◽  
Relative Energy ◽  
Helium Pressure ◽  
Neutron Absorber ◽  
The Core ◽  
Test Loop ◽  
Transient Energy ◽  
The Impact

Specific research reactors are capable of reproducing reactivity injection accidents in order to study the behavior of the nuclear fuel pins in accidental situations. In the CABRI research reactor, the fuel pin to be examined (test pin) is placed in the center of the core in a dedicated test loop. It is then subjected to a power transient, obtained by the fast depressurization of the 3He neutron absorber gas from the transient rods located in the core. One of the central parameters of the experiment is the energy deposition in the test pin, which is currently not measured during a transient. Instead, it is assumed that the relative energy distribution between the core and the test pin is constant regardless the operational state of the reactor. Currently, this correlation is measured in steady state. As such, the impact of the variations in the neutron flux, fuel and moderator temperatures during the transient is assumed equivalent on the energy deposition in the core and in the test pin. The goal of this work is to improve our knowledge on the mechanisms involved in the transient energy deposition. The aim of this paper is to present a methodological approach for the energy deposition estimation during a CABRI transient, based on static Monte Carlo calculations. The results suggest that the transient energy deposition rate is mainly dependent on the helium pressure and the Doppler feedback, and the relative energy distribution between the core and test pin changes during the transient.

scholarly journals The effect of ionic defect interactions on the hydration of yttrium-doped barium zirconate

2021 ◽  
Author(s):  
Sebastian Eisele ◽  
Fabian M. Draber ◽  
Steffen Grieshammer
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Simulations ◽  
First Principles ◽  
Barium Zirconate ◽  
First Principles Calculations ◽  
Defect Interactions ◽  
The Impact ◽  
Ionic Defect

First principles calculations and Monte Carlo simulations reveal the impact of defect interactions on the hydration of barium-zirconate.

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