New Neutron Detector Design Optimization by Monte Carlo Simulation

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F16%3A00306342" target="_blank" >RIV/68407700:21340/16:00306342 - isvavai.cz</a>

Nalezeny alternativní kódy

RIV/68407700:21670/16:00306342

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

New Neutron Detector Design Optimization by Monte Carlo Simulation

Popis výsledku v původním jazyce

The main aim of the project Advanced Detectors for Better Awareness of Neutrons and Gamma Rays in Environment (Czech-Norwegian Research Programme) is to develop a portable highly efficient and large area neutron sensitive detecting device for measurement of composition and spectral characteristics of mixed radiation fields. The device development tends to use in environmental and health research with a special attention to radiation protection and medical use of radiation One of the goal is to provide simulation results of developed device under irradiation from different radiation sources. Monte Carlo code MCNPX has been employed for particle transport (as well as nuclear reactions) simulations in the matter. The paper presents results of simulation of different structures to be etched into sensors (to increase neutron detection efficiency) over plain planar configuration as well as different conversion layer materials. Further, influence of various dead layer thickness and aluminum contacts in/on silicon detector layer has been compared and evaluated in the context of the neutron detection efficiency. Results of the simulation have been utilized in design of sensor by cooperating Norwegian organization.

Název v anglickém jazyce

New Neutron Detector Design Optimization by Monte Carlo Simulation

Popis výsledku anglicky

The main aim of the project Advanced Detectors for Better Awareness of Neutrons and Gamma Rays in Environment (Czech-Norwegian Research Programme) is to develop a portable highly efficient and large area neutron sensitive detecting device for measurement of composition and spectral characteristics of mixed radiation fields. The device development tends to use in environmental and health research with a special attention to radiation protection and medical use of radiation One of the goal is to provide simulation results of developed device under irradiation from different radiation sources. Monte Carlo code MCNPX has been employed for particle transport (as well as nuclear reactions) simulations in the matter. The paper presents results of simulation of different structures to be etched into sensors (to increase neutron detection efficiency) over plain planar configuration as well as different conversion layer materials. Further, influence of various dead layer thickness and aluminum contacts in/on silicon detector layer has been compared and evaluated in the context of the neutron detection efficiency. Results of the simulation have been utilized in design of sensor by cooperating Norwegian organization.

Druh

O - Ostatní výsledky

CEP obor

BG - Jaderná, atomová a molekulová fyzika, urychlovače

OECD FORD obor

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Projekt

<a href="/cs/project/7F14358" target="_blank" >7F14358: Advanced Detectors for Better Awareness of Neutrons and Gamma rays in environment</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2016

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů