scholarly journals The average effective dose of 4-amino-5-(furan-2-yl)-4H-1 ,2,4-triazole-3-thiol in experimental hepatitis

2014 ◽  
Vol 0 (2) ◽  
Author(s):  
I. M. Belay ◽  
E. O. Mihayluk ◽  
V. V. Parchenko ◽  
O. I. Panasenko ◽  
E. G. Knysh
2021 ◽  
Vol 14 (4) ◽  
pp. 309-316

Abstract: The aim of the current study was to measure indoor radon concentration levels and its resulting doses received by the students and staff in schools of the directorate of education in the north of Hebron region- Palestine, during the summer months from June to September (2018), using CR-39 detectors. In this study, a total of 567 CR-39-based radon detectors were installed in the selected schools. The average radon concentrations were found to be 90.0, 66.5 and 58.0 Bqm-3 in Halhul, Beit Umar and Alarrub camp schools, respectively. Based on the measured indoor radon data, the overall average effective dose for the studied area was found to be 0.31 mSvy-1. Reported values for radon concentrations and corresponding doses are lower than ICRP recommended limits for workplaces. The results show no significant radiological risk for the pupils and staff in the schools under investigation. Consequently, the health hazards related to radiation are expected to be negligible. Keywords: Radon concentration, Alpha particles, Annual effective dose, Schools. PACs: 29.40.−n.


2016 ◽  
Vol 57 (4) ◽  
pp. 422-430 ◽  
Author(s):  
Masahiro Hosoda ◽  
Shinji Tokonami ◽  
Yasutaka Omori ◽  
Tetsuo Ishikawa ◽  
Kazuki Iwaoka

Abstract Due to the Fukushima Daiichi Nuclear Power Plant (FDNPP) accident, the evacuees from Namie Town still cannot reside in the town, and some continue to live in temporary housing units. In this study, the radon activity concentrations were measured at temporary housing facilities, apartments and detached houses in Fukushima Prefecture in order to estimate the annual internal exposure dose of residents. A passive radon–thoron monitor (using a CR-39) and a pulse-type ionization chamber were used to evaluate the radon activity concentration. The average radon activity concentrations at temporary housing units, including a medical clinic, apartments and detached houses, were 5, 7 and 9 Bq m −3 , respectively. Assuming the residents lived in these facilities for one year, the average annual effective doses due to indoor radon in each housing type were evaluated as 0.18, 0.22 and 0.29 mSv, respectively. The average effective doses to all residents in Fukushima Prefecture due to natural and artificial sources were estimated using the results of the indoor radon measurements and published data. The average effective dose due to natural sources for the evacuees from Namie Town was estimated to be 1.9 mSv. In comparison, for the first year after the FDNPP accident, the average effective dose for the evacuees due to artificial sources from the accident was 5.0 mSv. Although residents' internal and external exposures due to natural radionuclides cannot be avoided, it might be possible to lower external exposure due to the artificial radionuclides by changing some behaviors of residents.


2015 ◽  
Vol 167 (4) ◽  
pp. 671-677 ◽  
Author(s):  
Vitalija Samerdokiene ◽  
Albinas Mastauskas ◽  
Vydmantas Atkocius

Author(s):  
A. A. Spasov ◽  
D. S. Yakovlev ◽  
D. V. Maltsev ◽  
M. V. Miroshnikov ◽  
K. T. Sultanova ◽  
...  

Thearticlepresentstheresultsofastudyoftheneurotoxicologicalprofileofanew5-HT2A-antagonist(compoundI) using the method of multi-test observation by «S. Irwin». The test parameters were evaluated in parallel groups, receiving the compound in doses beginning with the average effective dose (ED50) and with a multiple increase of 2, 5, 7.5 and 10 times.The study revealed that the neurotoxicological properties of compound I are characterized by dose-dependent activity. It has been shown that neurotoxicological changes in the behavior of the animals did not occur with the administration of compound I at average effective dose of 10 mg / kg and doses, exceeding the effective by 2 and 5 times; the animals welfare corresponds to that of the control group. The most significant effects by the administration of the studied compound developed in high doses, exceeding the effective by 7.5 and 10 times. The limits of the minimum toxic dose (TDmin) for compound I by oral administration has been found to be 50 mg / kg <TDmin≤75 mg / kg.


2021 ◽  
pp. 039156032199444
Author(s):  
Bob Yang ◽  
Noorunisa Suhail ◽  
Johan Marais ◽  
James Brewin

Background: Urolithiasis patients often require frequent urinary tract imaging, leading to high radiation exposure. CT Kidney-Ureter-Bladder (CT-KUB) is the gold standard in urolithiasis detection, however it is thought to harbour significant radiation load. Urologists have therefore utilised abdominal radiographs (XR-KUB) as an alternative, though with markedly lower sensitivity and specificity. We present the first contemporary UK study comparing the effective doses of XR-KUBs with low dose CT-KUBs. Method: Fifty-three patients were retrospectively identified in a single centre who underwent both a XR-KUB and a CT-KUB in 2018. Effective-Dose was measured by converting the recorded ‘Dose Area/Length Product’ via the International Commission on Radiological Protection formula. Results: The average effective dose of XR-KUBs and low dose CT-KUBs were 5.10 mSv and 5.31 mSv respectively. Thirty-four percent (18/53) of patients had a XR-KUBs with a higher effective dose than their low dose CT-KUB. Patients with higher Weight, BMI and AP diameter had higher effective doses for both their XR and low dose CT-KUBs. All patients in our study weighing over 92 kg or with a BMI greater than 32 had a XR-KUBs with a higher effective dose than their low dose CT-KUB. Conclusion: This data supports moving away from XR-KUBs for the investigation of urolithiasis, particularly in patients with a high BMI.


2021 ◽  
Vol 14 (1) ◽  
pp. 86-101
Author(s):  
A. V. Panov ◽  
A. V. Trapeznikov ◽  
A. V. Korzhavin ◽  
I. V. Geshel ◽  
S. V. Korovin ◽  
...  

The article provides a radiation-hygienic assessment of the current state of drinking water supply sources for the population in the observation area of the the Beloyarsk NPP and the Institute of Nuclear Materials. We determined the content of natural (234U, 238U, 226Ra, 228Ra, 210Po, 222Rn, 210Pb, 228Th, 230Th, 232Th) and technogenic (3H, 14C, 60Co, 90Sr, 134Cs, 137Cs, 238Pu, 239,240Pu, 241Am) radionuclides in drinking water of tap water, water boreholes and water wells in test settlements located at different distances and directions from radiation hazardous facilities. Results of monitoring of water sources in 2012–2013 and 2019 showed the radiation safety of drinking water in the vicinity of the Beloyarsk NPP according to several criteria. Thus, the maximum levels of the gross specific alpha-activity of radionuclides in water samples were 3.9 times lower than the control level (0.2 Bq/kg), the gross specific beta-activity was 5.7 times lower than the control level (1 Bq/ kg). Over the entire observation period, none of the drinking water samples exceeded the control levels both for individual radionuclides and for the sum of the ratios of specific activities to control levels. The content of natural and artificial radionuclides in drinking water near the Beloyarsk NPP decreases in the following order: water wells > water boreholes > tap water. For the past 20 years, there was a decrease in tritium specific activity in drinking water of the Beloyarsk NPP region by 20–35%, depending on the source of water supply. It was noted that the launch of the BN-800 reactor also did not lead to an increase in the content of other artificial radionuclides (90Sr, 137Cs) in groundwater. The average annual effective dose of internal exposure of the population due to drinking water consumption in the vicinity of the Beloyarsk NPP is 0.05 mSv, according to conservative estimates – 0.07 mSv, which is below the radiation safety threshold (0.1 mSv/a) recommended by the WHO. Natural radionuclides play the primary role in the formation of the annual average effective dose for internal irradiation (98.9%) due to drinking water consumption on the considered territories. 210Po makes the largest contribution to the dose from natural radioisotopes – 43%, somewhat less is made by 210Pb – 25%. The third place in the dose formation from natural radionuclides belongs to 234U (8%), 228Ra (7%), 226Ra (6%) and 230Th (6%). The contribution of other natural radioisotopes in the formation of the internal radiation dose from drinking water consumption does not exceed 2-3%. The contribution of technogenic radionuclides to the annual average effective dose from the consumption of drinking water is negligible (about 1%). Of the technogenic components, 90Sr (60%), 3H (20%), and 241Am (12%) play the most significant role in the formation of the internal exposure dose.


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