scholarly journals Features of absorbed radiation doses calculation for cattle’s in Krasnoyarsk krai

2021 ◽  
Vol 215 (12) ◽  
pp. 77-86
Author(s):  
A Fedotova

Abstract. The article provides an adapted methodology of absorbed dose calculation for the cattle from the territories with long-term man-made contamination. The methodology was developed according to existing regulatory documents in the RF: veterinarian rules VR 13.73.13/12-00, VR 13.5.13/03-00, methodical instructions MI 13.5.13-00, regulation for the state veterinarian control system in radioactive contamination of veterinary surveillance objects in the Russian Federation. The aim of the work is the development of calculation methodology of absorbed radiation doses for the cattle on the territory with long-term man-made isotopes contamination, taking to the account the radionuclide composition of the soil. Methods. The regulatory documents governing absorbed doses calculation has been analyzed; the contribution of external and internal radiation into total annual absorbed dose has been determined. Results. It has been established, that the calculation of external radiation dose needs to be done considering doses in stable and pasture periods. Pasture period dose is a sum of day and night doses considering day length. According to the data of radio ecological situation in Krasnoyarsk krai the internal radiation dose should be calculated as a sum of 137Cs, 90Sr, 60Co, taking to the account different concentration of these radionuclides in green and coarse fodder. Scientific novelty. The methodology of dose calculation for the cattle according to the radio ecological situation in Krasnoyarsk krai has been introduced for the first time. Practical significance. This methodology is recommended for the specialists of radiological departments of veterinarian laboratories and science officers in the field of agricultural radiobiology.

Author(s):  
V. Bebeshko ◽  
◽  
K. Bruslova ◽  
L. Lyashenko ◽  
T. Pushkariova ◽  
...  

Objective: to establish the relationship between quantitative and qualitative parameters of peripheral blood cells (lymphocytes, neutrophilic granulocytes, monocytes, platelets) depending on the type of somatic diseases and annual internal radiation doses from 137Cs in children – residents of radiologically contaminated territories in the late period after the Chornobyl Nuclear Power Plant (ChNPP) accident. Materials and methods. There were 175 children included in the study comprising residents of radiologically contaminated territories (n = 79) aged from 4 to 18 years. Annual internal radiation doses in children from 137Cs ranged from 0.004 to 0.067 mSv. Certain blood parameters were assessed in a comparative mode in children having got the radiation doses up to 0.01 mSv and higher. The comparison group (n = 96) included children living in settlements not attributed to the radiologically contaminated ones. Incidence and type of somatic diseases and its impact on quantitative and qualitative changes in blood parameters (i.e. lymphocyte, neutrophilic granulocyte, monocyte, and platelet count) were studied. The cell size, state of nucleus, membranes and cytoplasm, signs of proliferative and degenerative processes were taken into account. Results. Incidence and type of somatic diseases in children did not depend on the annual internal radiation dose. Number of cases of monocytosis was significantly higher among the children exposed to ionizing radiation than in the comparison group (16.6 % vs. 7.3 %). There were, however, no correlation between these changes and radiation doses. Number of activated blood monocytes with cytoplasmic basophilia and residues of nucleoli in nuclei was higher in individuals with internal radiation doses > 0.01 mSv. A direct correlation between the qualitative parameters of monocytes and internal radiation doses was established (rs = 0.60; р < 0.001), as well as a direct correlation of different strength between qualitative parameters of blood cells, indicating their unidirectional pattern depending on the somatic morbid conditions. Regardless of annual internal radiation dose, there was an increase in the number of degenerative and aberrant cells vs. the comparison group (р < 0.05), which could be due to the role of non-radiation factors. Conclusions. Results of the assessment of quantitative and qualitative parameters of peripheral blood cells reflected the state of morbid conditions in children and are of a diagnostic value. The identified dose-dependent changes in monocyte lineage of hematopoiesis may be the markers of impact of long-term radionuclide incorporation with food in children living in environmentally unfavorable conditions after the ChNPP accident. Key words: annual internal radiation dose from 137Cs, children, peripheral blood, lymphocytes, neutrophilic granulocytes, monocytes, platelets, qualitative signs.


1990 ◽  
Vol 8 (12) ◽  
pp. 1941-1950 ◽  
Author(s):  
J S Stewart ◽  
V Hird ◽  
D Snook ◽  
B Dhokia ◽  
G Sivolapenko ◽  
...  

From March 1987 to March 1988, a phase I to II study was carried out in 25 patients with ovarian cancer. They received escalating doses of intraperitoneally (IP) administered yttrium-90 (Y-90)-labeled monoclonal antibody, HMFG1, against a tumor cell-surface antigen. Myelosuppression prevented an escalation of the administered Y-90 activity above 25 mCi. Y-90-labeled antibody was absorbed from the peritoneal cavity into the circulation. Maximum blood Y-90 activity was observed 40 hours after the IP injection with a mean of 21% of the injected activity (range, 14.2% to 26.4%) in the circulation. The radiation dose the bone marrow received from circulating Y-90-labeled antibody (the blood radiation dose) was calculated by applying the Medical Internal Radiation Dose (MIRD) formulation to the measured Y-90 activity in patients blood. Myelosuppression occurred following calculated blood radiation doses to bone marrow of only 10 to 30 cGy. The excessive myelosuppression following such modest radiation doses from circulating Y-90-labeled antibody could be explained by the uptake of Y-90 by bone. In an attempt to reduce bone absorption of Y-90, seven patients received an intravenous (IV) infusion of EDTA (Sinclair Pharmaceuticals Ltd, Godalming, United Kingdom). This increased the urinary excretion of Y-90 from a mean of 11.1% to 32.3% of the injected activity (P = .0001). Fourteen patients had assessable tumor at laparoscopy. Tumor regression was observed in one patient, and palliation of ascites in a further patient.


2021 ◽  
Vol 55 (4) ◽  
pp. 86-90
Author(s):  
V.G. Mitrikas ◽  
◽  
E.G. Khorosheva ◽  

Malfunctioning of the reader is likely to be the reason for low radiation doses measured by the Pille dosimeters over the more than 20 years of ISS. Rectified measurements of the average daily absorbed dose rate agreed satisfactorily with readings of the other onboard tools of radiation monitoring.


2018 ◽  
Vol 19 (1) ◽  
pp. 38-42
Author(s):  
AHMR Quddus ◽  
MMA Zaman ◽  
AS Mollah ◽  
MM Zaman

To design appropriate method for treatment planning it is necessary to know the precise radiation dose absorbed by any internal organ in human body. This paper will provide a method for calculating retention, absorbed dose, committed equivalent dose and committed effective doses due to acute ingestion of 1 Bq of Ra-226 in the gastro intestinal (GI) tract of Bangladeshi people for different age groups. Calculations are done by using “Internal Radiation Dose Assessment (IRDA)” software which has been developed in Visual Basic language. GI tract consists of four tissue compartments, e.g. stomach (ST), small intestine (SI), upper large intestine (ULI) and lower large intestine (LLI). One hour after the ingestion, the retention and absorbed dose show the trend ST > SI > ULI > LLI. For tissue compartments the variation of the committed equivalent dose pattern is LLI > ULI > ST > SI for the radionuclide. The variation of absorbed dose, committed equivalent dose and committed effective dose with respect to age follow the pattern: 1 year> 10years > adult female > adult male. The highest committed effective dose is found in the GI tract of 1 year old child. For other age groups these values are slightly less than those for 1 year old child.Bangladesh J. Nuclear Med. 19(1): 38-42, January 2016


2003 ◽  
Vol 66 (11) ◽  
pp. 2051-2056 ◽  
Author(s):  
CHRISTOPHER SOMMERS ◽  
XUETONG FAN ◽  
BRENDAN A. NIEMIRA ◽  
KIMBERLY SOKORAI

Listeria monocytogenes, a psychrotrophic foodborne pathogen, is a frequent postprocessing contaminant of ready-to-eat (RTE) meat products, including frankfurters and bologna. Ionizing radiation can eliminate L. monocytogenes from RTE meats. When they are incorporated into fine-emulsion sausages, sodium diacetate (SDA) and potassium lactate (PL) mixtures inhibit the growth of L. monocytogenes. The radiation resistance of L. monocytogenes, and its ability to proliferate during long-term refrigerated storage (9°C), when inoculated into beef bologna that contained 0% SDA–0% PL, 0.07% SDA–1% PL, and 0.15% SDA–2% PL, were determined. The radiation doses required to eliminate 90% of the viable L. monocytogenes cells were 0.56 kGy for bologna containing 0% SDA–0% PL, 0.53 kGy for bologna containing 0.07% SDA–1% PL, and 0.46 kGy for bologna containing 0.15% SDA–2% PL. L. monocytogenes was able to proliferate on bologna containing 0% SDA–0% PL during refrigerated storage, but the onset of proliferation was delayed by the addition of the SDA-PL mixtures. An ionizing radiation dose of 3.0 kGy prevented the proliferation of L. monocytogenes and background microflora in bologna containing 0.07% SDA–1% PL and in bologna containing 0.15% SDA–2% PL over 8 weeks of storage at 9°C. Little effect on lipid oxidation and color of the control bologna, or bologna containing SDA-PL mixtures, was observed upon irradiation at either 1.5 or 3.0 kGy.


2013 ◽  
Vol 4 (1) ◽  
pp. 135-143
Author(s):  
AHMR Quddus ◽  
M Moksed Ali ◽  
MMA Zaman ◽  
AS Mollah

Retention, absorbed dose, committed equivalent dose and committed effective doses have been assessed due to acute ingestion of 1 Bq of 60Co in human body. Calculations are done using “Internal Radiation Dose Assessment (IRDA)” software which has been developed based on the biokinetic model. Due to ingestion maximum radiation dose is deposited in the gastro intestinal (GI) tract, assumed to consist of four tissue compartments, e.g. stomach (ST), small intestine (SI), upper large intestine (ULI) and lower large intestine (LLI). In this work actual tissue masses of GI Tract of Bangladeshi people have been considered to calculate the above mentioned quantities for different age groups, such as 1 yr, 10 yrs and adult (female and male). One hour after the ingestion, the retention and absorbed dose show the trend ST > SI > ULI > LLI. Regarding tissue compartments the variation of the committed equivalent dose pattern is LLI > ULI > ST > SI for the radionuclide. The variation of absorbed dose, committed equivalent dose and committed effective dose with respect to age follow the pattern: 1 yr > 10yrs > adult female > adult male. The highest committed effective dose for ingestion of 1 Bq of the radionuclide under the study is found in the GI tract of 1 yr old child. This value is 6.56 x 10-6 mSv. For other age groups these values are slightly less. DOI: http://dx.doi.org/10.3329/bjmp.v4i1.14703 Bangladesh Journal of Medical Physics Vol.4 No.1 2011 135-143


2006 ◽  
Vol 24 (18_suppl) ◽  
pp. 5558-5558
Author(s):  
M. A. List ◽  
E. E. Vokes ◽  
E. W. Cohen ◽  
K. M. Stenson ◽  
T. Karrison ◽  
...  

5558 Background: CTX regimens are often limited by severe acute toxicities and long-term functional impairment. This paper presents patient (pt) reported side effects and performance outcome in 3 sequential groups of stage IV HNC pts treated at the University of Chicago with IndCT and lowering radiation doses with the goal of maintaining survival while minimizing negative sequelae. Methods: Pts. were treated with IndCT followed by alternating weeks of concurrent CTX with lowering doses of radiotherapy to gross disease/ high risk microscopic/low risk microscopic disease: Group A - 75/60/45 Gy (n = 36 pts); Group B - 75/54/39 Gy (n = 34 pts); Group C - 72/51/36 Gy (n = 60 pts), respectively (treatment details & survival analyses presented separately). Pts were assessed for quality of life, performance (Performance Status Scale for HNC) and side effects (Radiotherapy Questionnaire) pretreatment, during CTX, at 3 & 12 months and annually thereafter. Controlling for baseline scores, differences between the groups were examined on- treatment and at 12-months. Results: Baseline and 12-month data were available for 81/114 pts. While all pts declined in performance (e.g., diet) and reported increased side effects (e.g., dry mouth, mouth pain, swallowing problems) on CTX, there were no statistically significant differences based on radiation dose. Similarly, there was improvement in most symptoms by 12 months with little difference among groups. In contrast, on normalcy of diet, fewer patients in Group C (20%) showed declines of more than 20 points from baseline compared to A (46%; p = .085) and B (45%, p = .09). Overall, 4% of patients were unable to take anything orally at 12-months with no difference among groups. Conclusions: This study showed no differences in pt reported symptoms on-treatment or at 12-months based on lowered radiation doses during CXT. On the other hand, while there continued to be some restriction in long-term diet, pts in the lowest radiation dose group showed somewhat less decline from baseline. These findings suggest the continued need to explore ways of decreasing both acute and long term toxicities in the use of CTX regimens. [Table: see text]


2019 ◽  
Vol 21 (1) ◽  
pp. 26-30
Author(s):  
Abdus Sattar Mollah ◽  
Mohammad Ruhul Quddus ◽  
Sayeed Mohammad Iqubal

In nuclear medicine practices, internal radiation dosimetry offers methods for calculation of radiation absorbed dose and risks from radionuclides incorporated inside the body. To manually perform internal radiation dosimetry is time-consuming and errors can occur in each step leading to developing software tools to ease users. There are many software packages available; however, many of them have limited functions. Locally developed IRDE software has been used to calculate the absorbed dose per unit of radioactivity in the target organ. The dose calculation methodology in nuclear medicine practices is described in this study along with a preliminary result on dose calculation for Bangladeshi population due to ingestion of 131I radioisotope in nuclear medicine practices. IRDE is user-friendly, graphic user interface-based software. It can be performed all steps of internal dosimetry within single environment lead to reducing calculation time and reducing possibility of error. IRDE also provides fast and accurate results which may be useful for a routine work in nuclear medicine facilities. Bangladesh J. Nuclear Med. 21(1): 26-30, January 2018


2020 ◽  
Vol 35 (1) ◽  
pp. 56-63
Author(s):  
Bojan Rankovic ◽  
Nikolina Nikolic ◽  
Slobodan Masic ◽  
Ivica Vujcic

The distribution of the absorbed dose within the irradiated product is a complex function of the product density and homogeneity, the position and shape of the radiation source, as well as the design of the irradiator. In this paper, detailed mapping of absorbed radiation doses in products of different density: gauze, plastic, and soil, is performed. Positions of minimum and maximum absorbed radiation dose were determined, and the homogeneity of irradiation of products was calculated using the ethanol-monochlorobenzene oscillotitrator dosimetry system.


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