Evaluation of all dose components in the LVR-15 reactor epithermal neutron beam using Fricke gel dosimeter layers

Bartesaghi, G.; Burian, J.; Gambarini, G.; Marek, M.; Negri, A.; Viererbl, L.

doi:10.1016/j.apradiso.2009.03.049

Cited by 15 publications

(6 citation statements)

References 8 publications

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“…Determination of stable free radicals produced during irradiation can be achieved using different analytical methods, like magnetic resonance or an inexpensive alternative readout based on spectrophotometry, proposed by Gupta et al 15 , 16 The FXG dosimetry by thin layers optically analyzed, originally developed by Prof. Gambarini, 17 , 18 has been demonstrated to be a suitable and reliable tool for wide applications, including standard radiation therapy modalities, like intensity‐modulated radiotherapy, (19) measurements of dose profiles and multiple fields irradiations, 11 , 20 , 21 and high‐dose‐rate brachytherapy, (22) among other conventional and nonconventional procedures. The latter include mainly Boron neutron capture therapy (BNCT), for which this technique proved to be even capable of assessing the different dose contributions, then separating therapeutic from other components 23 , 24 , 25 , 26 , 27 , 28 , 29 …”

Section: Introductionmentioning

confidence: 99%

Fricke gel dosimeter with improved sensitivity for low‐dose‐level measurements

Valente

Molina

Silva

et al. 2016

J Applied Clin Med Phys

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Fricke solution has a wide range of applications as radiation detector and dosimetry. It is particularly appreciated in terms of relevant comparative advantages, like tissue‐equivalence when prepared in aqueous media like gel matrix, continuous mapping capability, independence of dose rate and incident direction, as well as linear dose response. This work presents the development and characterization of an improved Fricke gel system, based on modified chemical compositions, making possible its application in clinical radiology due to its improved sensitivity. Properties of standard Fricke gel dosimeter for high‐dose levels are used as a starting point, and suitable chemical modifications are introduced and carefully investigated in order to attain high resolution for low‐dose ranges, like those corresponding to radiology interventions. The developed Fricke gel radiation dosimeter system achieves the expected typical dose‐dependency, showing linear response in the dose range from 20 up to 4000 mGy. Systematic investigations including several chemical compositions are carried out in order to obtain an adequate dosimeter response for low‐dose levels. A suitable composition from among those studied is selected as a good candidate for low‐dose‐level radiation dosimetry consisting of a modified Fricke solution fixed to a gel matrix containing benzoic acid along with sulfuric acid, ferrous sulfate, Xylenol orange, and tridistilled water. Dosimeter samples are prepared in standard vials for in‐phantom irradiation and further characterization by spectrophotometry measuring visible light transmission and absorbance before and after irradiation. Samples are irradiated using typical X‐ray tubes for radiology and calibrated Farmer‐type ionization chamber is used as reference to measure dose rates inside phantoms at vial locations. Once sensitive material composition is optimized, dose‐response curves show significant improvement regarding overall sensitivity for low dose levels. The aim of this work consists of implementing the optimized gel dosimeter to perform direct measurements of absorbed dose in samples irradiated during microcomputed tomography scanning in order to preliminary assess dose levels for further scanning of small animals for further applications in veterinary and paleontology. As a first attempt, dose distributions were measured in water‐equivalent phantoms having dimensions comparable to small animals, 100 to 1000 cm3, approximately. According to the obtained results, it is found that the proposed method shows satisfactory reliability and adequate performance for a promising gel dosimetry system.PACS number(s): 87.53.Bn, 87.57.uq, 87.59.‐e

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Section: Introductionmentioning

confidence: 99%

Fricke gel dosimeter with improved sensitivity for low‐dose‐level measurements

Valente

Molina

Silva

et al. 2016

J Applied Clin Med Phys

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“…The derived graphs for absorbed dose in the liver tissue and other components of mentioned system (per emitted neutrons) by both Monte Carlo simulation with nps: 10 6 and analytical method (Turbo-Pascal programming) are as Figures 6,7,8,9,10,11,and 12. In addition the neutron fluence [n/cm 2 ] or on the other hand the number of neutrons which reach the liver tissue and other components is obtained as Figure 13. Meantime the X-axis means the neutron energies reached the phantom's components that are low energies [eV].…”

Section: Resultsmentioning

confidence: 99%

“…The results of computation provide assurance that whether the absorbed dose in cancerous and healthy tissues is in accord with requirements [8,9]. Then neutron therapy would be implemented on the patient.…”

Section: Introductionmentioning

confidence: 93%

Design and Simulation of a New Model for Treatment by NCT

Shirazi

Sardari

2012

Science and Technology of Nuclear Installations

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In this investigation, neutron capture therapy (NCT) through high energy neutrons using Monte Carlo method has been studied. In this study a new method of NCT for a sample liver phantom has been defined, and interaction of 12 MeV neutrons with a multilayer spherical phantom is considered. In order to reach the desirable energy range of neutrons in accord with required energy in absence of eligible clinical neutron source for NCT, this model of phantom might be utilized. The neutron flux and the deposited dose in the all components and different layers of the mentioned phantom are computed by Monte Carlo simulation. The results of Monte Carlo method are compared with analytical method results so that by using a computer program in Turbo-Pascal programming, the deposited dose in the liver phantom has been computed.

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“…In the pres ent study, Monte Carlo N-Par ti cle trans port code (MCNP-4C) de vel oped by Los Alamos Na tional Labo ra tory has been used to per form the sim u la tions. MCNP is a gen eral multipurposes code which can be used ef fec tively to cal cu late mass at ten u a tion co ef ficients of dif fer ent types of mix tures and also has a wide range of ca pa bil i ties which makes it use ful for med i cal and in dus trial pur poses [33][34][35][36][37]. The Monte Carlo method is based on gen er at ing ran dom num bers to sim u late any prob lem hav ing proba bil is tic in ter preta tion such as pho ton trans port through the mat ter.…”

Section: Simulationmentioning

confidence: 99%

Theoretical and experimental determination of mass attenuation coefficients of lead-based ceramics and their comparison with simulation

Vejdani-Noghreiyan

Aliakbari

Ebrahimi-Khankook

et al. 2016

Nucl Technol Radiat Prot

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Mass at ten u a tion co ef fi cient of lead-based ce ram ics have been mea sured by ex per i men tal meth ods and com pared with the o ret i cal and Monte Carlo sim u la tion re sults. Lead-based ceram ics were pre pared us ing mixed ox ide method and the X-ray dif frac tion anal y sis was done to eval u ate the crys tal struc ture of the pro duced hand made ce ram ics.The ex per i men tal re sults show good agree ment with the o ret i cal and sim u la tion re sults. How ever at two gamma ray ener gies, small dif fer ences be tween ex per i men tal and the o ret i cal re sults have been ob served. By add ing other ad di tives to ce ram ics and ob serv ing the changes in the shield ing prop er ties such as flex i bil ity, one can syn the size and op ti mize ce ram ics as a neu tron shield. Key words: at ten u a tion co ef fi cient, CsI(Tl) de tec tor, lead-based ce ramic, MCNP-4CA. Vejdani-Noghreiyan, et al.: The o ret i cal and Ex per i men tal De ter mi na tion of .

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Evaluation of all dose components in the LVR-15 reactor epithermal neutron beam using Fricke gel dosimeter layers

Cited by 15 publications

References 8 publications

Fricke gel dosimeter with improved sensitivity for low‐dose‐level measurements

Fricke gel dosimeter with improved sensitivity for low‐dose‐level measurements

Design and Simulation of a New Model for Treatment by NCT

Theoretical and experimental determination of mass attenuation coefficients of lead-based ceramics and their comparison with simulation

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