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Wyszukujesz frazę "131I" wg kryterium: Temat


Wyświetlanie 1-12 z 12
Tytuł:
Dosimetry of 131 I for Occupational Radiation Workers by Whole Body Counting System
Autorzy:
Rahman, M. S.
Haydar, M. A.
Patwary, M. K. A.
Shome, S. M.
Paul, S.
Paul, D.
Meaze, A. K. M. M. H.
Powiązania:
https://bibliotekanauki.pl/articles/411910.pdf
Data publikacji:
2014
Wydawca:
Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
Tematy:
Internal Dosimetry
Whole Body Counter
IMBA
131I
Opis:
Internal radiation dosimetry of occupational radiation workers due to inhalation of 131 I during maintenance at iodine 131 I hot cell of Radioisotope Production Division (RIPD) of Bangladesh Atomic Energy Commission have been performed with Whole Body Counter (WBC) containing two large size NaI detector. The contaminated radioactivity of the radiation workers by 131 I was immediately conducted using a WBC (CANBERRA, FASTSCAN model 2250) and counting was repeated again a few days later. The performance of whole body counter was checked by CANBERRA transfer phantom (model 2257) with a mixed source (20 ml vial). The intake was calculated by Apex-Invivo counting software and then corresponding dose in thyroid were estimated by using Integrated Modules for Bioassay Analysis (IMBA) Professional Plus code modules. The body activity due to intake of 131 I and the total effective and equivalent dose in thyroid were also estimated and discussed.
Źródło:
International Letters of Chemistry, Physics and Astronomy; 2014, 20, 1; 21-27
2299-3843
Pojawia się w:
International Letters of Chemistry, Physics and Astronomy
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Assessment of exposure of workers to ionizing radiation from radioiodine and technetium in nuclear medicine departmental facilities
Ocena narażenia pracowników na promieniowanie jonizujące radiojodu i technetu w zakładach medycyny nuklearnej
Autorzy:
Krajewska, Grażyna
Pachocki, Krzysztof A.
Powiązania:
https://bibliotekanauki.pl/articles/2166302.pdf
Data publikacji:
2014-11-05
Wydawca:
Instytut Medycyny Pracy im. prof. dra Jerzego Nofera w Łodzi
Tematy:
radiojod 131I
technet 99mTc
medycyna nuklearna
dawka skuteczna
ekspozycja zawodowa
radioiodine 131I
technetium 99mTc
nuclear medicine
effective dose
occupational exposure
Opis:
Background: Due to its use of ionising radiation, the field of nuclear medicine is a unique and significant part of medical diagnostics and patient treatment. The aim of this study was to assess the internal exposure of nuclear medicine employees to radioiodine 131I and technetium 99mTc as well as to assess the external exposure doses. Material and Methods: The radioiodine 131I and technetium 99mTc contents in the thyroid of staff members (about 100 persons) dealing with these radionuclides have been measured in four departments of nuclear medicine. The measurements were conducted with a portable detection unit for in situ measurements of radioiodine and technetium. High sensitivity environmental thermoluminescent dosimeters (TLD) were used to measure the external exposure dose. Results: The average values and ranges of radioiodine 131I activity measured in the thyroids of all of the medical units' employees were: 83 Bq (range: 70-250 Bq), 280 Bq (range: 70-4000 Bq), 275 Bq (range: 70-1000 Bq) for technical staff, nuclear medicine staff and hospital services staff, respectively. The mean value of technetium 99mTc content in the thyroids of nuclear medicine staff was approximately 1500 Bq (range: 50- -1800 Bq). External exposure dose rates were in the range of 0.5-10 μGy/h. Conclusions: The calculated average effective dose for particular person caused by the inhalation of radioiodine 131I is below 5% of 20 mSv/year (occupational exposure limit). Med Pr 2013;64(5):625–630
Wprowadzenie: Ze względu na stosowanie promieniowania jonizującego medycyna nuklearna jest istotną i unikalną gałęzią metod diagnostycznych i leczniczych. Celem podjętych badań była ocena narażenia wewnętrznego pracowników zakładów medycyny nuklearnej na jod promieniotwórczy 131I i technet 99mTc oraz ocena dawek pochodzących z ekspozycji zewnętrznej. Materiał i metody: Pomiary zawartości radiojodu 131I i technetu 99mTc w tarczycy osób pracujących z tymi radionuklidami (ok. 100 osób) wykonano w 4 ośrodkach medycyny nuklearnej. Zastosowano przenośny zestaw detekcyjny mierzący radionuklidy in situ. Dawki pochodzące z ekspozycji zewnętrznej mierzono, wykorzystując środowiskowe dozymetry termoluminescencyjne (thermoluminescent dosimeters - TLD) o dużej czułości. Wyniki: Zawartość radiojodu 131I w tarczycy wynosiła średnio: 83 Bq (zakres aktywności: 70-250 Bq) w grupie personelu technicznego, 280 Bq (zakres: 70-4000 Bq) w grupie personelu medycznego i 275 Bq (zakres: 70-1000 Bq) w grupie personelu pomocniczego. Średnia zawartość technetu 99mTc w tarczycy wynosiła ok. 1500 Bq (zakres: 50-1800 Bq). Otrzymana moc dawek pochodzących z ekspozycji zewnętrznej mieściła się w zakresie 0,5-10 μGy/godz. Wnioski: Oszacowana średnia dawka skuteczna pochodząca z inhalacji radiojodu 131I stanowiła mniej niż 5% rocznego limitu dla narażenia zawodowego, które wynosi 20 mSv/rok. Med. Pr. 2013;64(5):625–630
Źródło:
Medycyna Pracy; 2013, 64, 5; 625-630
0465-5893
2353-1339
Pojawia się w:
Medycyna Pracy
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Historia zrealizowanego projektu
History of the completed project
Autorzy:
Birnbaum, Grażyna
Powiązania:
https://bibliotekanauki.pl/articles/2055834.pdf
Data publikacji:
2021
Wydawca:
Instytut Chemii i Techniki Jądrowej
Tematy:
produkcja I-131
wzbogacony w Te-130 ditlenek telluru
production of I-131
Te-130 enriched tellurium dioxide
Opis:
Zastosowanie w reaktorze jądrowym wzbogaconego w nuklid Te-130 ditlenku telluru do otrzymywania I-131, w wyniku reakcji jądrowej (n, γ). W artykule przedstawiono korzyści, jakie można uzyskać po wprowadzeniu nowego surowca i plan dalszych badań
The use of Te-130 nuclide enriched tellurium dioxide in a nuclear reactor for the preparation of I-131 as a result of a nuclear reaction (n, γ). The article present the benefits that can be obtained after the introduction of a new raw material and a plan for further research.
Źródło:
Postępy Techniki Jądrowej; 2021, 3; 23--24
0551-6846
Pojawia się w:
Postępy Techniki Jądrowej
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Comparative Study of Anion Exchange Resins Purolite NRW-6000 and Duolite A-143 by Application Isotopic Technique
Autorzy:
Singare, P.U.
Powiązania:
https://bibliotekanauki.pl/articles/411790.pdf
Data publikacji:
2013
Wydawca:
Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
Tematy:
isotopic technique
tracer isotopes
131I
82Br
resin characterization
industrial grade resins
Purolite NRW-6000
Duolite A-143
Opis:
Isotopic tracer technique using 131I and 82Br was used to characterize Purolite NRW-6000 and Duolite A-143 anion exchange resins. The characterization study was done by carrying out iodide and bromide ion-isotopic exchange reactions taking place between the resin surface and the external labeled ionic solution. For the two resins it was observed that under identical experimental conditions, the values of specific reaction rate (min-1), amount of ion exchanged (mmol) and initial rate of ion exchange (mmol/min) were calculated to be lower for bromide ion-isotopic exchange reaction than that for iodide ion-isotopic exchange reaction. Also during both the ion-isotopic exchange reactions, under identical experimental conditions for the two resins, the values of specific reaction rate increases with increase in ionic concentration and was observed to decrease with rise in temperature. For a constant temperature of 35.0 °C, as the concentration of labeled bromide ion solution increases from 0.001 mol/L to 0.004 mol/L, the percentage of bromide ions exchanged increases from 67.80 % to 72.76 % using Purolite NRW-6000 resin and from 42.54 % to 50.45 % using Duolite A-143 resin. However when the temperature was raised from 30.0 °C to 45.0 °C by keeping the concentration of labeled bromide ion solution constant at 0.002 mol/L, the percentage of bromide ions exchanged decreases from 70.68 % to 67.32 % using Purolite NRW-6000 resin and from 47.50 % to 42.25 % using Duolite A-143 resin. From the results it appears that Purolite NRW-6000 resins show superior performance over Duolite A-143 resins under identical experimental conditions. It is expected that the present isotopic tracer technique can be applied further as an efficient nondestructive technique in characterization of various ion exchange resins so as to bring about their efficient industrial applications.
Źródło:
International Letters of Chemistry, Physics and Astronomy; 2013, 12; 1-13
2299-3843
Pojawia się w:
International Letters of Chemistry, Physics and Astronomy
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Radio Analytical Nondestructive Technique in Performance Evaluation of Organic Base Ion Exchange Resins Purolite NRW-6000 and Duolite A-378
Autorzy:
Singare, P. U.
Powiązania:
https://bibliotekanauki.pl/articles/412155.pdf
Data publikacji:
2013
Wydawca:
Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
Tematy:
anion exchange
resins
Purolite NRW-6000
Duolite A-378
isotopic exchange tracer isotopes
131I
82Br
nondestructive technique
Opis:
Nondestructive radioanalytical technique using short lived isotopes 131I and 82Br was used as tracers to study the kinetics of iodide and bromide ion-isotopic exchange reactions. The kinetic data so obtained was used to evaluate the performance of organic base anion exchange resins Purolite NRW-6000 and Duolite A-378. It was observed that for iodide ion-isotopic exchange reaction performed at 40.0 °C using 1.000 g of ion exchange resins and 0.003 mol/L labeled iodide ion solution, the values of specific reaction rate (min-1), amount of iodide ion exchanged (mmol), initial rate of iodide ion exchange (mmol/min) and log Kd were calculated as 0.332, 0.582, 0.193 and 16.2 respectively for Purolite NRW-6000 resin, which was higher than the respective values of 0.210, 0.421, 0.088 and 14.7 as that obtained for Duolite A-378 resins. Also at a constant temperature of 40.0 °C, as the concentration of labeled iodide ion solution increases from 0.001 mol/L to 0.004 mol/L, the percentage of iodide ions exchanged increases from 74.68 % to 79.48 % using Purolite NRW-6000 resins and from 52.30 % to 58.90 % using Duolite A-378 resins. The overall results indicate superior performance of Purolite NRW-6000 resins over Duolite A-378 resins under identical operational parameters. It is expected here that the present technique can be extended further for characterization of different ion exchange resins which will further help in the selection of those reins for the specific industrial application.
Źródło:
International Letters of Chemistry, Physics and Astronomy; 2013, 13; 77-89
2299-3843
Pojawia się w:
International Letters of Chemistry, Physics and Astronomy
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Radiotracer Technique in Study of Strongly Basic Anion Exchange Resins Dowex-SBR LC and Indion-454
Autorzy:
Singare, P. U.
Powiązania:
https://bibliotekanauki.pl/articles/411866.pdf
Data publikacji:
2013
Wydawca:
Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
Tematy:
anion exchange resins
Indion-454
Dowex-SBR LC
radioisotopes
131I
82Br
ion-isotopic exchange reaction
reaction kinetics
characterization
Opis:
The present paper demonstrates application of isotopic tracer technique in characterization of anion exchange resins Dowex-SBR LC and Indion-454 for which 131I and 82Br radio isotopes were used. The characterization was made based on iodide and bromide ion-isotopic exchange reaction kinetic data obtained for the two resins. It was observed that during iodide ion-isotopic exchange reaction performed at 35.0 °C, 1.000 g of ion exchange resins and 0.002 mol/L labeled iodide ion solution, the values of specific reaction rate (min-1), amount of ion exchanged (mmol), initial rate of ion exchange (mmol/min) and log Kd were 0.379, 0.426, 0.161 and 16.2 respectively for Dowex-SBR LC resin, which was higher than the respective values of 0.156, 0.243, 0.038 and 13.4 as that obtained by using Indion-454 resins. The identical trend was observed for the two resins during bromide ion-isotopic exchange reaction. The results of present investigation also indicate that during the two ion-isotopic exchange reactions, for both the resins, there exists a strong positive linear correlation between amount of ions exchanged and concentration of ionic solution; and strong negative correlation between amount of ions exchanged and temperature of exchanging medium. Based on overall results it appears that under identical experimental conditions, as compared to Indion-454 resins, Dowex-SBR LC resins show superior performance. It is expected here that the present technique can be extended further for characterization of different ion exchange resins which will further help in the selection of those reins for the specific industrial application.
Źródło:
International Letters of Chemistry, Physics and Astronomy; 2013, 13; 37-49
2299-3843
Pojawia się w:
International Letters of Chemistry, Physics and Astronomy
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Nondestructive Radioactive Tracer Technique in Characterization of Anion Exchange Resins Purolite NRW-8000 and Duolite A-368
Autorzy:
Singare, P.U.
Powiązania:
https://bibliotekanauki.pl/articles/411749.pdf
Data publikacji:
2013
Wydawca:
Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
Tematy:
ion-exchange resin
anion exchange
Purolite NRW-8000
Duolite A-368
radio tracer isotopes
131I
82Br
characterization
isotopic Exchange
Opis:
Radioactive tracer isotopes 131I and 82Br were used to characterize anion exchange resins Purolite NRW-8000 and Duolite A-368 by application of nondestructive technique. The resin characterization was based on their performance during iodide and bromide ion-isotopic exchange reactions. It was observed that during the iodide ion-isotopic exchange reaction at a constant temperature of 40.0 °C, as the concentration of labeled iodide ion solution increases from 0.001 mol/L to 0.004 mol/L, the percentage of iodide ions exchanged increases from 62.10 % to 68.10 % using Purolite NRW-8000 resins and from 44.20 % to 46.80 % using Duolite A-368 resins. Also at a constant temperature of 40.0 °C, 1.000 g of ion exchange resins and 0.003 mol/L labeled iodide ion solution, the values of specific reaction rate (min-1), amount of iodide ion exchanged (mmol), initial rate of iodide ion exchange (mmol/min) and log Kd were calculated as 0.260, 0.500, 0.130 and 11.8 respectively for Purolite NRW-8000 resin, which was higher than the respective values of 0.130, 0.345, 0.045 and 6.7 as that obtained for Duolite A-368 resins. The similar trend was observed for the two resins during bromide ion-isotopic exchange reaction. From the overall results it appears that under identical experimental conditions, Purolite NRW-8000 resins show superior performance over Duolite A-368 resins. It is expected here that the present nondestructive technique can be extended further for characterization of different industrial grade ion exchange resins, which will help in their selection for specific industrial application.
Źródło:
International Letters of Chemistry, Physics and Astronomy; 2013, 12; 14-27
2299-3843
Pojawia się w:
International Letters of Chemistry, Physics and Astronomy
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Non Destructive Application of Radioactive Tracer Isotopes for Performance Evaluation of Industrial Grade Anion Exchange Resins Tulsion A-33 and Indion NSSR
Autorzy:
Singare, P. U.
Powiązania:
https://bibliotekanauki.pl/articles/411857.pdf
Data publikacji:
2013
Wydawca:
Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
Tematy:
radioisotopes
non-destructive technique
Tulsion A-33
Indion NSSR
nuclear grade resin
anion exchange resins
performance evaluation
operational parameters
131I
82Br
Opis:
The present study deals with non-destructive application of radioactive tracer isotopes to evaluate the performance of Tulsion A-33 (nuclear grade) and Indion NSSR (non-nuclear grade) anion exchange resins. The performance evaluation was done by carrying out the iodide and bromide ion-isotopic exchange reactions using the above resins. It was observed that at a constant temperature of 40.0 °C, as the concentration of labeled iodide ion solution increases 0.001 M to 0.004 M, the percentage of iodide ions exchanged increases from 58.0 % to 64.0 % for Tulsion A-33 resins; and from 48.4 % to 50.8 % for Indion NSSR resins. Similarly in case of bromide ion-isotopic exchange reaction under identical experimental conditions, the percentage of bromide ions exchanged increases from 45.6 % to 50.4 % for Tulsion A-33 resin; and from 39.8 % to 44.6 % for Indion NSSR resin. It was also observed that during iodide ion-isotopic exchange reaction at 40.0 °C, using 1.000 g of ion exchange resins and 0.003 M labeled ionic solution, using Tulsion A-33 resin the values of specific reaction rate (min-1), amount of iodide ion exchanged (mmol), initial rate of iodide ion exchange (mmol/min) and log Kd were 0.229, 0.469, 0.107 and 10.6 respectively, which was higher than the values of 0.167, 0.375, 0.063 and 7.6 respectively as obtained by using Indion NSSR resins under identical experimental conditions. The overall results indicate superior performance of Tulsion A-33 over Indion NSSR resin under identical operational parameters.
Źródło:
International Letters of Chemistry, Physics and Astronomy; 2013, 13; 50-62
2299-3843
Pojawia się w:
International Letters of Chemistry, Physics and Astronomy
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Verification of Reaching the Regulatory Limit for the Release of Radioactive Liquid Waste in Nuclear Medicines
Autorzy:
Alfayyadh, Linda
Naimi, Sepanta
Mizban, Fadhil
Al-Hamami, Naheel
Alguraibawi, Marwah
Powiązania:
https://bibliotekanauki.pl/articles/24201728.pdf
Data publikacji:
2023
Wydawca:
Polskie Towarzystwo Inżynierii Ekologicznej
Tematy:
radioactive iodine
I-131
liquid waste
storage system
decay system
nuclear medicine
authorisation limit
Opis:
The research was conducted at one of Iraq’s nuclear medical facilities in Baghdad, which uses radioactive iodine (I-131) to treat thyroid patients, the major purpose of this research was to meet the national legal limit for the release of radioactive liquid waste into the environment, a high purity germanium reagent radiation detector was used to evaluate nine iodine I-131 samples. From 2021 and 2023, the concentration of waste prior to storage and disposal was between 24498 Bq/L and 5.7 Bq/L. Short-lived radionuclides, such as I-131 with an 8.04-day half-life, may be released into the sewage system in line with Iraq’s Nationally Approved Limits and Austria’s International Atomic Energy Agency (IAEA). Moreover, it is stored for 10 times the half-life, or four months, until the choice to release it into the environment is made.
Źródło:
Journal of Ecological Engineering; 2023, 24, 5; 329--336
2299-8993
Pojawia się w:
Journal of Ecological Engineering
Dostawca treści:
Biblioteka Nauki
Artykuł
Tytuł:
Application of Nondestructive Radio Tracer Technique in Performance Evaluation of Anion Exchange Resins Duolite ARA-9366 and Duolite A-171
Autorzy:
Singare, P. U.
Powiązania:
https://bibliotekanauki.pl/articles/412526.pdf
Data publikacji:
2013
Wydawca:
Przedsiębiorstwo Wydawnictw Naukowych Darwin / Scientific Publishing House DARWIN
Tematy:
non-destructive tracer technique
radio analytical technique
radioactive tracer isotopes
131I
82Br
reaction kinetics
ion-isotopic exchange reactions
nuclear grade resin
Duolite ARA-9366
Duolite A-171
Opis:
Radio analytical technique as a non-destructive technique was used in the present investigation to trace the kinetics of ion-isotopic exchange reaction taking place in Duolite ARA-9366 (nuclear grade) and Duolite A-171 (non-nuclear grade) anion exchange resins. The kinetics data suggest that during iodide ion-isotopic exchange reactions under identical experimental conditions of 40.00C, 1.000 g of ion exchange resins and 0.003 M labeled iodide ion solution, the values of specific reaction rate (min-1), amount of iodide ion exchanged (mmol), initial rate of iodide ion exchange (mmol/min) and log Kd were 0.176, 0.383, 0.067 and 7.8 respectively for Duolite ARA-9366 resin, which was higher than 0.142, 0.353, 0.050 and 7.0 respectively as that obtained for Duolite A-171 resins. Also it is observed that at a constant temperature of 40.0 °C, as the concentration of labeled iodide ion solution increases 0.001 M to 0.004 M, the percentage of iodide ions exchanged increases from 49.20 % to 51.80 % for Duolite ARA-9366 resins; and from 45.20 % to 47.80 % for Duolite A-171 resins. The similar trend was observed for the two resins during bromide ion-isotopic exchange reactions. The overall results indicate superior performance of Duolite ARA-9366 resins over Duolite A-171 resins under identical operational parameters.
Źródło:
International Letters of Chemistry, Physics and Astronomy; 2013, 13; 63-76
2299-3843
Pojawia się w:
International Letters of Chemistry, Physics and Astronomy
Dostawca treści:
Biblioteka Nauki
Artykuł
    Wyświetlanie 1-12 z 12

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