Measurement of the individual dose of external irradiation

Atomic Energy ◽  
1999 ◽  
Vol 87 (3) ◽  
pp. 678-682
Author(s):  
A. L. Kononovich
Keyword(s):  
External Irradiation ◽  
Individual Dose ◽  
The Individual

Dismantling of a Nuclear Fuel Fabric - Release of Building Rubble and Site: An Overview

2001 ◽  
Author(s):  
Elisabeth T. Aberl ◽  
Karl-Heinz Lehmann
Keyword(s):  
Nuclear Fuel ◽  
Specific Activity ◽  
Total Activity ◽  
Mean Value ◽  
Salt Mine ◽  
Individual Dose ◽  
Dose Limit ◽  
Uranium Fuel ◽  
Industrial Use ◽  
The Individual

Abstract Uranium fuel rods were produced in the nuclear fuel site. The buildings should be dismantled after decontamination and the site should be released for industrial use. The individual dose to the critical group is limited to an annual value of about 10 μSv. The determined specific activity for remediation of the site was a mean value of 60 mBq/g total activity. For the building rubble and soil primarily two pathways, disposal at a landfill and refill of a disused salt mine, were considered. As a result of the investigations the total activity for the disposal at a landfill had to be limited to about 6,6 GBq. For the refill of the salt mine the estimated individual dose fell below the dose limit in the range of 10 μSv/y.

Recommendation of dose banding of cytotoxics according to pharmacokinetic criteria.

2012 ◽  
Vol 30 (15_suppl) ◽  
pp. 2549-2549
Author(s):  
Etienne Chatelut ◽  
Melanie White-Koning ◽  
Ron H.J. Mathijssen ◽  
Sharyn D. Baker ◽  
Alex Sparreboom
Keyword(s):  
Capacity Planning ◽  
Simple Procedure ◽  
Drug Stability ◽  
Exposure Dose ◽  
Analytical Control ◽  
Individual Dose ◽  
Significant Difference ◽  
Patient Waiting Time ◽  
The Individual

2549 Background: Dose-banding has been recently suggested in order to optimize chemotherapy preparation. Ranges (or bands) of body surface area (BSA) are predefined. The individual dose of a particular patient is calculated according to a single BSA value per band, usually the mid-point of the BSA band in which the actual BSA of the patient lies. Thanks to this simple procedure, chemotherapy provision can be rationalized and chemotherapies can be prepared in advance for drugs with sufficient long-term drug stability. The primary purpose of dose-banding is to reduce patient waiting time and improve capacity planning of the pharmacy production, but additional benefits can also be found, such as reduced potential for medication errors, reduced drug wastage, and prospective quality control of preparations. The objective of this analysis was to compare dose-banding to individual BSA-dosing (current practice) according to pharmacokinetic (PK) criteria. Methods: Dose-banding was defined according to three bands of BSA: BSA<1.7m², 1.7m²≤BSA<1.9m², and BSA≥1.9m² for which the values of 1.55m², 1.80m², and 2.05m² were allocated, respectively. By using individual actual values of clearance of six drugs (cisplatin, docetaxel, paclitaxel, doxorubicin, topotecan, and irinotecan) from a total of 1,206 adult cancer patients, the AUCs corresponding to the two dosing methods were compared to a target value of AUC for each drug. Results: Over all 6 drugs, by using dose-banding the percent change of individual dose in comparison with BSA dosing ranged between -14% and +22%. In terms of capacity to attain the target AUC, there was no significant difference in precision when using dose-banding as compared to BSA-dosing for all drugs except paclitaxel (precision of 23.2% versus 21.8%, respectively). For all drugs including paclitaxel, distributions of AUC values were very similar with both dosing methods. Conclusions: For these 6 drugs and maybe others, dose-banding may be implemented without any risk of increasing interindividual plasma exposure. Dose-banding would make it possible to anticipate chemotherapy preparation and analytical control without any delay for the patients.

SUBSTANTIATION OF THE MODEL FOR CALCULATING THE INDIVIDUAL DOSE OF CYTOSTATICS USING CT VOLUMETRY FOR ISOLATED LUNG CHEMIOPERFUSION WITH METASTASECTOMY

2018 ◽  
Vol 64 (3) ◽  
pp. 319-324
Author(s):  
Yevgeniy Levchenko ◽  
VAN TIN ◽  
ChZhAN VEN ◽  
P. Kalinin ◽  
Tatyana Dubinina ◽  
...  
Keyword(s):  
Lung Disease ◽  
Software Package ◽  
Strong Positive Correlation ◽  
Individual Dose ◽  
Ct Volumetry ◽  
Anatomical Features ◽  
Isolated Lung ◽  
Metastatic Lung ◽  
Three Stages ◽  
The Individual

In order to create conditions for increasing the effectiveness of treatment of patients with metastatic lung disease a new method for calculating the dose of antitumor drug for performing isolated chemo-perfusion of the lung with metasta-sectomy taking into account the anatomical features of patients and previous operations on the lung was developed. The study consisted of three stages. As a result of the first stage of the study the effectiveness of the software package was measured in the volume of lung patients based on the presence of a strong positive correlation between the volumes of left lungs (Rs = 0.91, p

Final Results From a Phase II Trial with the First in Class Recombinant Polyclonal Antibody Product Rozrolimupab in Primary Immune Thrombocytopenia

Blood ◽  
2011 ◽  
Vol 118 (21) ◽  
pp. 527-527 ◽  
Author(s):  
Tadeusz Robak ◽  
Jacek Trelinski ◽  
Mario von Depka Prondzinski ◽  
Aristoteles Giagounidis ◽  
Chantal Doyen ◽  
...  
Keyword(s):  
Platelet Count ◽  
Adverse Events ◽  
Phase Ii ◽  
Adverse Reactions ◽  
Phase Ii Trial ◽  
Individual Dose ◽  
Safety And Efficacy ◽  
Platelet Counts ◽  
The Individual ◽  
Antibody Mixture

Abstract Abstract 527 Background: Rozrolimupab is the first in-class fully human, recombinant antibody mixture for the treatment of ITP. Rozrolimupab comprises 25 unique human antibodies with documented binding capacity to the Rhesus D antigen on red blood cells, and constitutes a promising, modern counter-part to the blood-derived immunoglobulin products currently used in the treatment of ITP. The antibody mixture constituting rozrolimupab is produced by a novel single batch manufacturing strategy. Objectives and Endpoints: The objectives of the trial were to investigate the safety and efficacy of a single dose of rozrolimupab in RhD positive, non-splenectomized adult patients with primary ITP. The primary endpoint was incidence and severity of Adverse Events (AEs) during the 6-week trial period. Secondary endpoints included identification of the optimal dose of rozrolimupab and percentage of patients responding to treatment at 72 hours, 7 and 15 days. Methods: Patients from 27 sites in 11 countries were enrolled in this dose escalation (75 μg/kg – 300 μg/kg), multicentre, open label trial. Inclusion criteria included confirmed presence of thrombocytopenia with two individual pre-dose platelet counts of < 30 × 109/L. The patients received a single iv dose of rozrolimupab, and were followed for 6 weeks with frequent evaluations for safety and efficacy. Response was defined as platelet count ≥ 30 ×109/L and increase in platelet count from baseline by > 20 × 109/L. Results: A total of 61 ITP patients were treated with rozrolimupab: 75 μg/kg (11 patients), 100 μg/kg (10 patients), 125 μg/kg (10 patients), 150 μg/kg (5 patients), 200 μg/kg (6 patients), 250 μg/kg (6 patients) and 300 μg/kg (13 patients). Data from the 300 μg/kg cohort were not available for this abstract, but will be included in the final presentation.Given the small size of this study, the dose cohorts differed in a number of baseline characteristics. 60–90% of patients were females in all dose cohorts except in the 75 μg/kg cohort where 73% were males. Median platelet count before trial entry ranged from 11.5 to 22.3 × 109/L, and median time from first ITP diagnosis ranged from 5 to 68 months. In the individual dose groups, up to 83% of the patients responded at day 7. Up to 50% and 60% of the patients responded at 24 and 72 hours, respectively, and some responses lasted for the duration of the 6 weeks follow up period. Platelet responses also included patients who had baseline platelet counts below 10 ×109/L. A total of 51 AEs considered related to trial drug were reported in 20 patients. The most frequently reported adverse reactions were headache (7 events in 5 patients) and pyrexia (5 events in 4 patients). All but 2 of the adverse reactions (one headache, one extravascular haemolysis) were of mild or moderate intensity. Four of the 51 adverse reactions were categorized as Serious Adverse Events: One mild haemoglobin decrease in the 100 μg/kg cohort, one extravascular haemolysis in the 200 μg/kg cohort (mentioned above) and two mild to moderate, transient increases in D-dimer with no clinical symptoms in the 250 μg/kg cohort. Laboratory data showed a mean maximum decrease in haemoglobin ranging from 1.1 g/dL to 2.7 g/dL in individual cohorts with a slight dose dependency. A drop in haemoglobin of ≥ 3 g/dL was seen in 2 patients, one of 3.1 g/dL in the 100 μg/kg cohort and one of 4.5 g/dL in the 200 μg/kg cohort. Conclusions: Rozrolimupab is well tolerated with a favourable safety profile. In the individual dose groups, up to 83% of patients responded at day 7 including patients who had baseline platelet counts below 10 ×109/L. Final safety and efficacy data from all dose groups in the completed Phase II trial of rozrolimupab in primary ITP patients will be presented. Disclosures: Wiktor-Jedrzejczak: Celgene: Honoraria; Janssen-Cilag: Honoraria; Novartis: Honoraria, Research Funding. Flensburg:Symphogen: Employment. Petersen:Symphogen: Employment.

scholarly journals VADER: a variable dose-rate external 137Cs irradiator for internal emitter and low dose rate studies

2020 ◽  
Vol 10 (1) ◽  
Author(s):  
Guy Garty ◽  
Yanping Xu ◽  
Gary W. Johnson ◽  
Lubomir B. Smilenov ◽  
Simon K. Joseph ◽  
...  
Keyword(s):  
Dose Rate ◽  
Low Dose ◽  
Computer Control ◽  
Whole Body ◽  
External Irradiation ◽  
Dose Rates ◽  
Low Dose Rate ◽  
The Individual ◽  
Variable Dose

AbstractIn the long term, 137Cs is probably the most biologically important agent released in many accidental (or malicious) radiation disasters. It can enter the food chain, and be consumed, or, if present in the environment (e.g. from fallout), can provide external irradiation over prolonged times. In either case, due to the high penetration of the energetic γ rays emitted by 137Cs, the individual will be exposed to a low dose rate, uniform, whole body, irradiation. The VADER (VAriable Dose-rate External 137Cs irradiatoR) allows modeling these exposures, bypassing many of the problems inherent in internal emitter studies. Making use of discarded 137Cs brachytherapy seeds, the VADER can provide varying low dose rate irradiations at dose rates of 0.1 to 1.2 Gy/day. The VADER includes a mouse “hotel”, designed to allow long term simultaneous residency of up to 15 mice. Two source platters containing ~ 250 mCi each of 137Cs brachytherapy seeds are mounted above and below the “hotel” and can be moved under computer control to provide constant low dose rate or a varying dose rate mimicking 137Cs biokinetics in mouse or man. We present the VADER design and characterization of its performance over 18 months of use.

The National Research Council, Study of the Isolation System for Geologic Disposal of Radioactive Wastes

1983 ◽  
Vol 26 ◽  
Author(s):  
Thomas H. Pigford
Keyword(s):  
Individual Dose ◽  
Spent Fuel ◽  
Geologic Repository ◽  
Isolation System ◽  
Waste Forms ◽  
The Individual ◽  
Long Term Performance ◽  
Term Performance ◽  
Environmental Releases

ABSTRACTThis study was conducted for the U. S. Department of Energy by the Waste Isolation Systems Panel appointed by the National Academies of Science and Engineering. The panel was charged to review the alternative technologies available for Isolating of radioactive waste in mined geologic repositories, evaluate the performance benefits from these technologles as potential elements of a waste Isolation system, and identify appropriate technical criteria for satisfactory long-term performance of a geologic repository. Conceptual repositories in basalt, granite, salt, and tuff were considered. Site-specific data on geology, hydrology, and geochemical properties were evaluated and used to define parameters for estimating long-term environmental releases, supplemented when necessary by generic properties.The technology for solid waste forms and waste packages was reviewed and evaluated. Borosilicate glass and unreprocessed spent fuel are the waste forms appropriate for further testing and for repository designs. Testing in a simulated repository environment is necessary to develop an adeauate prediction of the long term performance of waste packages in a geologic repository. Back-up research and development on alternative waste forms should be continued. The expected functions of backfill placed between the rock and waste package need clearer definition and validation.The overall criterion to be used by federal agencies in designing a geologic waste-isolation system and in evaluating its nerformance has not yet been specified. As a guideline, the panel selected an average annual dose of 10-4 sieverts to a maximally exposed individual at any future time, if the exposure is from expected events such as the slow dissolution of waste solids in wet-rock repositories and the groundwater transport of dissolved radionuclides to the biosphere. Risks from unexpected events such as human intrusion were not evaluated.Calculations were made of the long-term isolation and environmental releases for conceptual repositories in basalt, granite, salt, and tuff. The major contributors to geologic isolation are the slow dissolution of key radioelements as limited by solubility and by diffusion and convection in groundwater surrounding the waste solids, long water travel times from the waste to the environment, and sorption retardation in the media surrounding the repository. Dilution by surface water can reduce the individual radiation exposures that can result from the small fraction of the waste radioactivity that may ultimately reach the environment. Estimates of environmental releases and individual doses were made both for unreprocessed spent fuel and for reprocessing wastes.Accelerated dissolution of waste exposed to groundwater during the period of repository heating was also considered. Long-term environmental releases of radioactivity from some repositories were calculated to cause doses to maximally exposed individuals that are several orders of magnitude below the Individual dose criterion of 10-4 Sieverts per year. Other conceptual repositories were found to not meet the individual dose criterion, although these repositories could still meet the radioactivity release limits in the standard proposed by the Environmental Protection Agency.The technology for geologic waste disposal has advanced to the state of a preliminary technical plan, suitable for testing, verification, and for pllot-facility confirmation. The waste Isolation program needs a reliable prediction of long-term performance that will serve as a basis for final design, construction, licensing, and waste emplacement.

scholarly journals Consideration of the contribution of the natural background component during individual control of radiation doses to personnel

2021 ◽  
Vol 14 (4) ◽  
pp. 122-128
Author(s):  
S. Yu. Bazhin ◽  
G. N. Kaidanovsky
Keyword(s):  
Background Radiation ◽  
Radiation Doses ◽  
Individual Dose ◽  
External Radiation ◽  
Natural Background ◽  
Natural Radiation ◽  
Radiation Background ◽  
Natural Background Radiation ◽  
The Individual ◽  
Natural Component

When ensuring radiation safety in the Russian Federation, there is a principle of separate independent assessment of doses from natural, medical, emergency and technogenic exposure. In practice, it is not always possible to comply with this principled approach. The established dose limits are related only to man-made radiation during normal operation of sources of ionizing radiation. However, during the formation of regional and federal databases on individual doses of personnel exposure, information is entered not on technogenic exposure, but on industrial exposure, that is, without subtracting the natural radiation background. The natural component of the individual dose at low radiation doses is quite significant. Failure to its subtraction leads to an overestimation of the individual dose of external exposure of personnel. Difficulties arise in the implementation of the subtraction of the natural radiation background: 1) in what cases it is necessary to subtract the background, 2) what value to choose for the subtracted background, 3) what method to measure the background, 4) at what stage of processing the measurement information to subtract the background. This article proposes a method for solving the problem of subtracting the natural background radiation from the values of individual doses of external exposure to personnel based on results of individual dosimetric control. Using the example of the city of St. Petersburg, the natural background radiation was measured by the thermoluminescent method of individual dosimetry at 50 control points for three consecutive years (2018-2020). To measure the natural background, we used individual thermoluminescent dosimeters of the same type as those used to measure individual equivalents of external radiation doses to personnel. The choice of using the thermoluminescent method as a predominant one for adjusting the average doses of external radiation from technogenic sources of ionizing radiation when subtracting the natural component of the dose has been substantiated. Comparison of official data on personnel exposure doses with the data obtained as a result of our own measurements is made. Recommendations are given on the use of the obtained values of the average natural radiation background in the formation of regional and federal databases on individual doses of personnel exposure. 

Feasibility on the spectrometric determination of the individual dose rate for detected gamma nuclides using the dose rate spectroscopy

2014 ◽  
Vol 97 ◽  
pp. 172-177 ◽  
Author(s):  
Young-Yong Ji ◽  
Kun Ho Chung ◽  
Wanno Lee ◽  
Doo-Won Park ◽  
Mun-Ja Kang
Keyword(s):  
Dose Rate ◽  
Individual Dose ◽  
The Individual
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