Simulation and design of individual neutron dosimeter and optimization of energy response using an array of semiconductor sensors

At present, most of the developed neutron dosimeters that have a moderator with a single counter, applied in neutron radiation fields within large range energies from thermal to MeV neutrons, are not a satisfaction to energy response. The purpose of the article is designing a suitable neutron dosimeter for the radiation protection purpose. In order to overcome the disadvantage of the energy response of the neutron dosimeters combined a single sphere with a single counter, three spheres and three 3He counters were combined for the detector design. The response function of moderators with different thicknesses combined with SP9 3He counters were calculated with MCNP program MCNP4C [1]. The selection of three different thicknesses of the moderating polyethylene sphere was done with a Matlab program [2]. A suitable combination of three different thicknesses was confirmed for the detector design. The electronic system of the neutron dosimeter was introduced. The fluence to ambient dose-equivalent conversion coefficient were calculated, analyzed and compared with the values recommended in the ICRP 74 Publication [3]. The calculated result explain that it is very significance to this design of neutron dosimeter, it may be applied to the monitor of the ambient dose in the neutron radiation fields, improving at present the status of the energy response of neutron dosimeters.

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The Design of an Ambient Neutron Dose-Equivalent Meter

Journal of Engineering for Gas Turbines and Power ◽

10.1115/1.4002818 ◽

2011 ◽

Vol 133 (8) ◽

Author(s):

Xia Wenming ◽

Jia Mingchun ◽

Guo Zhirong

Keyword(s):

Neutron Radiation ◽

Monte Carlo Code ◽

Energy Response ◽

Dose Equivalent ◽

Neutron Dosimeter ◽

Radiation Fields ◽

Ambient Dose Equivalent ◽

Ambient Dose ◽

Detector Design ◽

Single Counter

At present, most of the developed neutron dosimeters used to measure the neutron ambient dose-equivalent that has a moderator with a single counter, applied in neutron radiation fields within large range energies from thermal to MeV neutrons, are not a satisfaction to energy response. The purpose of this article is to design a suitable neutron dosimeter for radiation protection purpose. In order to overcome the disadvantage of the energy response of the neutron dosimeters combining a single sphere with a single counter, three spheres and three H3e counters were combined for the detector design. The response function of moderators with different thicknesses combined with SP9 H3e counters were calculated with Monte Carlo code MCNP 4C. The selection of three different thicknesses of the moderating polyethylene sphere was done with a MATLAB program. A suitable combination of three different thicknesses was confirmed for the detector design. The electronic system of the neutron dosimeter was introduced. The results of ambient dose-equivalent per unit fluence in different radiation areas were calculated, analyzed, and compared with the values recommended in the ISO standard. The calculated result explains that it is very significant to this design of neutron dosimeter; it may be applied to the monitor of the ambient dose in the neutron radiation fields, improving at present the status of the energy response of neutron dosimeters.

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Use of borated polyethylene to improve low energy response of a prompt gamma based neutron dosimeter

Nuclear Instruments and Methods in Physics Research Section A Accelerators Spectrometers Detectors and Associated Equipment ◽

10.1016/j.nima.2016.02.095 ◽

2016 ◽

Vol 819 ◽

pp. 139-143 ◽

Cited By ~ 6

Author(s):

P. Priyada ◽

U. Ashwini ◽

P.K. Sarkar

Keyword(s):

Low Energy ◽

Prompt Gamma ◽

Energy Response ◽

Neutron Dosimeter ◽

Borated Polyethylene

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Faculty Opinions recommendation of SnRK1-triggered switch of bZIP63 dimerization mediates the low-energy response in plants.

Faculty Opinions – Post-Publication Peer Review of the Biomedical Literature ◽

10.3410/f.725713006.793509057 ◽

2015 ◽

Author(s):

Sjef Smeekens

Keyword(s):

Low Energy ◽

Energy Response

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COMPARISON OF ENERGY RESPONSE FUNCTION OF STILBENE, BC501 AND EJ309 NEUTRON GAMMA DETECTION SYSTEM

RAP 2019 Conference Proceedings ◽

10.37392/rapproc.2019.09 ◽

2020 ◽

Author(s):

Annesha Karmakar ◽

Anil K. Gourishetty ◽

A. Kelkar

Keyword(s):

Response Function ◽

Detection System ◽

Energy Response ◽

Gamma Detection

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The Energy Response of Calorimeters

10.1093/oso/9780198786351.003.0003 ◽

2018 ◽

Author(s):

Richard Wigmans

Keyword(s):

Sampling Frequency ◽

Integration Time ◽

Signal Integration ◽

Energy Response ◽

Absorption Process ◽

Active Materials ◽

Unit Energy ◽

Sampling Fraction ◽

Signal Integration Time ◽

Calorimeter Response

This chapter deals with the signals produced by particles that are being absorbed in a calorimeter. The calorimeter response is defined as the average signal produced per unit energy deposited in this absorption process, for example in terms of picoCoulombs per GeV. Defined in this way, a linear calorimeter has a constant response. Typically, the response of the calorimeter depends on the type of particle absorbed in it. Also, most calorimeters are non-linear for hadronic shower detection. This is the essence of the so-called non-compensation problem, which has in practice major consequences for the performance of calorimeters. The origins of this problem, and its possible solutions are described. The roles of the sampling fraction, the sampling frequency, the signal integration time and the choice of the absorber and active materials are examined in detail. Important parameters, such as the e/mip and e/h values, are defined and methods to determine their value are described.

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Dosimetric Properties of the Newly Developed LiF:Mg,Cu,Si TL Material

Journal of Scientific Research ◽

10.3329/jsr.v5i1.11935 ◽

2012 ◽

Vol 5 (1) ◽

pp. 25-31 ◽

Cited By ~ 1

Author(s):

M. S. Rahman ◽

J. I. Lee ◽

J. L. Kim ◽

G. Cho

Keyword(s):

Dose Response ◽

Linear Response ◽

Detection Threshold ◽

Atomic Energy ◽

Energy Response ◽

Energy Research ◽

Higher Doses ◽

Research Institute

The dosimetric properties of the newly developed thermoluminescence (TL) material (LiF:Mg,Cu,Si) at Korea Atomic Energy Research Institute (KAERI) were investigated. The energy response of the detector was performed for photon energies from 20 to 662 keV. The dose response for this TL material (LiF:Mg,Cu,Si) was linear up to 10 Gy and a sub-linear response was observed for higher doses. The reusability of this newly developed TL detector sufficiently satisfied IEC standards. Detection threshold of LiF:Mg,Cu,Si TL material was investigated and found to be 930 nGy by Harshaw 4500 TLD reader. © 2013 JSR Publications. ISSN: 2070-0237 (Print); 2070-0245 (Online). All rights reserved.doi: http://dx.doi.org/10.3329/jsr.v5i1.11935 J. Sci. Res. 5 (1), 25-31 (2013)

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