A Randomized Dose-Ranging Study of Neuropeptide Y in Patients with Posttraumatic Stress Disorder.

Science.gov (United States)

Sayed, Sehrish; Van Dam, Nicholas T; Horn, Sarah R; Kautz, Marin M; Parides, Michael; Costi, Sara; Collins, Katherine A; Iacoviello, Brian; Iosifescu, Dan V; Mathé, Aleksander A; Southwick, Steven M; Feder, Adriana; Charney, Dennis S; Murrough, James W

2018-01-01

Anxiety and trauma-related disorders are among the most prevalent and disabling medical conditions in the United States, and posttraumatic stress disorder in particular exacts a tremendous public health toll. We examined the tolerability and anxiolytic efficacy of neuropeptide Y administered via an intranasal route in patients with posttraumatic stress disorder. Twenty-six individuals were randomized in a cross-over, single ascending dose study into 1 of 5 cohorts: 1.4 mg (n=3), 2.8 mg (n=6), 4.6 mg (n=5), 6.8 mg (n=6), and 9.6 mg (n=6). Each individual was dosed with neuropeptide Y or placebo on separate treatment days 1 week apart in random order under double-blind conditions. Assessments were conducted at baseline and following a trauma script symptom provocation procedure subsequent to dosing. Occurrence of adverse events represented the primary tolerability outcome. The difference between treatment conditions on anxiety as measured by the Beck Anxiety Inventory and the State-Trait Anxiety Inventory immediately following the trauma script represented efficacy outcomes. Twenty-four individuals completed both treatment days. Neuropeptide Y was well tolerated up to and including the highest dose. There was a significant interaction between treatment and dose; higher doses of neuropeptide Y were associated with a greater treatment effect, favoring neuropeptide Y over placebo on Beck Anxiety Inventory score (F1,20=4.95, P=.038). There was no significant interaction for State-Trait Anxiety Inventory score. Our study suggests that a single dose of neuropeptide Y is well tolerated up to 9.6 mg and may be associated with anxiolytic effects. Future studies exploring the safety and efficacy of neuropeptide Y in stress-related disorders are warranted. The reported study is registered at: http://clinicaltrials.gov (ID: NCT01533519). © The Author(s) 2017. Published by Oxford University Press on behalf of CINP.

Evaluating the maximum patient radiation dose in cardiac interventional procedures

International Nuclear Information System (INIS)

Kato, M.; Chida, K.; Sato, T.; Oosaka, H.; Tosa, T.; Kadowaki, K.

2011-01-01

Many of the X-ray systems that are used for cardiac interventional radiology provide no way to evaluate the patient maximum skin dose (MSD). The authors report a new method for evaluating the MSD by using the cumulative patient entrance skin dose (ESD), which includes a back-scatter factor and the number of cine-angiography frames during percutaneous coronary intervention (PCI). Four hundred consecutive PCI patients (315 men and 85 women) were studied. The correlation between the cumulative ESD and number of cine-angiography frames was investigated. The irradiation and overlapping fields were verified using dose-mapping software. A good correlation was found between the cumulative ESD and the number of cine-angiography frames. The MSD could be estimated using the proportion of cine-angiography frames used for the main angle of view relative to the total number of cine-angiography frames and multiplying this by the cumulative ESD. The average MSD (3.0±1.9 Gy) was lower than the average cumulative ESD (4.6±2.6 Gy). This method is an easy way to estimate the MSD during PCI. (authors)

Acumulación de hojarasca en un pastizal de Panicum maximum y en un sistema silvopastoril de Panicum maximum y Leucaena leucocephala Litter accumulation in a Panicum maximum grassland and in a silvopastoral system of Panicum maximum and Leucaena leucocephala

Directory of Open Access Journals (Sweden)

Saray Sánchez

2007-09-01

Full Text Available Se realizó un estudio en la Estación Experimental de Pastos y Forrajes "Indio Hatuey", Matanzas, Cuba, con el objetivo de determinar la acumulación de la hojarasca en un pastizal de Panicum maximum Jacq cv. Likoni y en un sistema silvopastoril de Panicum maximum y Leucaena leucocephala (Lam de Wit cv. Cunningham. En los pastizales de P. maximum de ambos sistemas se determinó la acumulación de la hojarasca según la técnica propuesta por Bruce y Ebershon (1982, mientras que la hojarasca de L. leucocephala acumulada en el sistema silvopastoril se determinó según Santa Regina et al. (1997. De forma general, los resultados demostraron que en ambos pastizales la guinea acumuló una menor cantidad de hojarasca durante el período junio-diciembre, etapa en la que se produce su mayor desarrollo vegetativo. En la leucaena la mayor producción de hojarasca ocurrió en el período de diciembre a enero, asociada con la caída natural de sus hojas que se produce por efecto de las temperaturas más bajas y la escasa humedad en el suelo. En el sistema silvopastoril la hojarasca de leucaena representó el mayor porcentaje de peso dentro de la producción total, con un contenido más alto de nitrógeno y de calcio que el de la hojarasca del estrato herbáceo. En la guinea la lluvia fue el factor climático que mayor correlación negativa presentó con la producción de hojarasca en ambos sistemas, y en la leucaena la mayor correlación negativa se encontró con la temperatura mínima.A study was carried out at the Experimental Station of Pastures and Forages "Indio Hatuey", Matanzas, Cuba, with the objective of determining the litter accumulation in a pastureland of Panicum maximum Jacq cv. Likoni and in a silvopastoral system of Panicum maximum and Leucaena leucocephala (Lam de Wit cv. Cunningham. In the P. maximum pasturelands of both systems the litter accumulation was determined by means of the technique proposed by Bruce and Ebershon (1982, while

Maximum tolerable radiation doses recommended by the Israel Advisory Committee on nuclear safety

International Nuclear Information System (INIS)

Tadmor, J.; Litai, D.; Lubin, E.

1978-01-01

Maximum tolerable doses have been recommended by the Israel Advisory Committee on Nuclear Safety. The recommendations which are based on a comparison with risks tolerated in other human activities, are for doses to radiation workers, for individual members of the population at the fence of a nuclear installation, and for the population at large, for both normal operating and accident conditions. Tolerable whole-body doses and doses to different critical organs are listed

Enjebi Island dose assessment

International Nuclear Information System (INIS)

Robison, W.L.; Conrado, C.L.; Phillips, W.A.

1987-07-01

We have updeated the radiological dose assessment for Enjebi Island at Enewetak Atoll using data derived from analysis of food crops grown on Enjebi. This is a much more precise assessment of potential doses to people resettling Enjebi Island than the 1980 assessment in which there were no data available from food crops on Enjebi. Details of the methods and data used to evaluate each exposure pathway are presented. The terrestrial food chain is the most significant potential exposure pathway and 137 Cs is the radionuclide responsible for most of the estimated dose over the next 50 y. The doses are calculated assuming a resettlement date of 1990. The average wholebody maximum annual estimated dose equivalent derived using our diet model is 166 mremy;the effective dose equivalent is 169 mremy. The estimated 30-, 50-, and 70-y integral whole-body dose equivalents are 3.5 rem, 5.1 rem, and 6.2 rem, respectively. Bone-marrow dose equivalents are only slightly higher than the whole-body estimates in each case. The bone-surface cells (endosteal cells) receive the highest dose, but they are a less sensitive cell population and are less sensitive to fatal cancer induction than whole body and bone marrow. The effective dose equivalents for 30, 50, and 70 y are 3.6 rem, 5.3 rem, and 6.6 rem, respectively. 79 refs., 17 figs., 24 tabs

Change in the alpha criterion policy: variable based on the maximum individual dose function

International Nuclear Information System (INIS)

Freitas Acosta Perez, C. de; Sordi, G.M.A.A.

2006-01-01

The Alpha value is an extremely important criterion because it determines the time that a country takes to achieve its proposals in order to decrease the workers doses involved with ionizing radiation sources. Currently the countries adopt a single value for alpha based on the annual gross national product, GNP, per capita. The aim of this paper is to show that the selection of a curve for the alpha in place of a single value would be more efficient. This curve would provide alpha values that would will be constraints to the biggest individual doses presented in each optimization process as applied both to designs and to operations. These maximum individual doses would represent the dose distribution among the workers team. To build the curve, the alpha values suggested are not based on the GNP per capita but on a distribution function of the maximum individual doses and on the time necessary to reach the proposal of 1/10 of the annual dose limit foreseen in the sequential optimization processes, that is to reach the region where the individual doses are considered acceptable. So, the differential equations will be - d X/dS =α(H m ax). To clarify our sight about the alpha value we started using the uranium mine example presented in ICRP publication 55, adopting the decision-aiding technique known as extended cost-benefit. for right. Then we used the same example in a hypothetical curve with portions: constant, linear, quadratic and exponential. Eventually we discussed briefly the different shapes of the curves that the alpha value can assume in function of the individual doses. Each of these shapes can correspond to the so called 'risk neutral attitude', 'risk adverse attitude' or 'risk prone attitude' suggested in the appendix B of the ICRP publication 55

Effect of the Maximum Dose on White Matter Fiber Bundles Using Longitudinal Diffusion Tensor Imaging

Energy Technology Data Exchange (ETDEWEB)

Zhu, Tong; Chapman, Christopher H. [Department of Radiation Oncology, University of Michigan, Ann Arbor, Michigan (United States); Tsien, Christina [Department of Radiation Oncology, Washington University at St Louis, St Louis, Missouri (United States); Kim, Michelle; Spratt, Daniel E.; Lawrence, Theodore S. [Department of Radiation Oncology, University of Michigan, Ann Arbor, Michigan (United States); Cao, Yue, E-mail: yuecao@umich.edu [Department of Radiation Oncology, University of Michigan, Ann Arbor, Michigan (United States); Department of Radiology, University of Michigan, Ann Arbor, Michigan (United States); Department of Biomedical Engineering, University of Michigan, Ann Arbor, Michigan (United States)

2016-11-01

Purpose: Previous efforts to decrease neurocognitive effects of radiation focused on sparing isolated cortical structures. We hypothesize that understanding temporal, spatial, and dosimetric patterns of radiation damage to whole-brain white matter (WM) after partial-brain irradiation might also be important. Therefore, we carried out a study to develop the methodology to assess radiation therapy (RT)–induced damage to whole-brain WM bundles. Methods and Materials: An atlas-based, automated WM tractography analysis was implemented to quantify longitudinal changes in indices of diffusion tensor imaging (DTI) of 22 major WM fibers in 33 patients with predominantly low-grade or benign brain tumors treated by RT. Six DTI scans per patient were performed from before RT to 18 months after RT. The DTI indices and planned doses (maximum and mean doses) were mapped onto profiles of each of 22 WM bundles. A multivariate linear regression was performed to determine the main dose effect as well as the influence of other clinical factors on longitudinal percentage changes in axial diffusivity (AD) and radial diffusivity (RD) from before RT. Results: Among 22 fiber bundles, AD or RD changes in 12 bundles were affected significantly by doses (P<.05), as the effect was progressive over time. In 9 elongated tracts, decreased AD or RD was significantly related to maximum doses received, consistent with a serial structure. In individual bundles, AD changes were up to 11.5% at the maximum dose locations 18 months after RT. The dose effect on WM was greater in older female patients than younger male patients. Conclusions: Our study demonstrates for the first time that the maximum dose to the elongated WM bundles causes post-RT damage in WM. Validation and correlative studies are necessary to determine the ability and impact of sparing these bundles on preserving neurocognitive function after RT.

Location of radiosensitive organs, measurement of absorbed dose to radiosensitive organs and use of bismuth shields in paediatric anthropomorphic phantoms

International Nuclear Information System (INIS)

Inkoom, S.

2014-08-01

thyroid organ dose was reduced to 46% (10-y-old). The combined use of single shield and AEC reduced the thyroid surface dose to a maximum of 70% (5-y-old); whilst the thyroid organ dose was reduced to 62% (10-y-old). The use of double shields and AEC activation further reduced the surface / organ dose to 76% / 65% (5-y-old). The maximum dose to the eye lenses due to neck CT was 7.0 mGy / 6.2 mGy (10-y-old) for FTC / AEC. The maximum breast dose attributable to neck CT was 0.6 mGy for 5-, and 10-y-old phantoms for all protocols. For thorax CT scans, the use of AEC induced a significant increase in the thyroid organ dose by a maximum value of 70% (1-y-old), and thyroid surface dose by 70% (newborn), and mean breast surface dose by 69% (newborn). The maximum increase of the effective dose as a result of application of AEC was 54% (newborn). In conclusion, the production of charts of radiosensitive organs inside paediatric anthropomorphic phantoms for dosimetric purposes was feasible. In-plane bismuth thyroid shielding decreases radiation dose in MDCT with/without deteriorating image quality. AEC was more effective in thyroid dose reduction than in-plane bismuth shields (head and neck CT, neck CT). AEC increased the absorbed dose to both the thyroid and the breast, as well as the effective dose in thorax CT. Thus, AEC should be abandoned as a dose optimisation tool during thoracic MDCT, especially in neonates, infants and children younger than 10-years-old. Placement of the spacer between shield and surface had no significant impact on the measured doses, but significantly decreased the image noise. (au)

Dosimetric systems of high dose, dose rate and dose uniformity in food and medical products; Sistemas dosimetricos de altas dosis, tasa de dosis y uniformidad de dosis en alimentos y producto medico

Energy Technology Data Exchange (ETDEWEB)

Vargas, J.; Vivanco, M.; Castro, E., E-mail: jvargas@ipen.gob.pe [Instituto Peruano de Energia Nuclear, Av. Canada 1470, San Borja, Lima (Peru)

2014-08-15

In the Instituto Peruano de Energia Nuclear (IPEN) we use the chemical dosimetry Astm-E-1026 Fricke as a standard dosimetric system of reference and different routine dosimetric systems of high doses, according to the applied doses to obtain the desired effects in the treated products and the doses range determined for each type of dosimeter. Fricke dosimetry is a chemical dosimeter in aqueous solution indicating the absorbed dose by means an increase in absorbance at a specific wavelength. A calibrated spectrophotometer with controlled temperature is used to measure absorbance. The adsorbed dose range should cover from 20 to 400 Gy, the Fricke solution is extremely sensitive to organic impurities, to traces of metal ions, in preparing chemical products of reactive grade must be used and the water purity is very important. Using the referential standard dosimetric system Fricke, was determined to March 5, 2013, using the referential standard dosimetric system Astm-1026 Fricke, were irradiated in triplicate Fricke dosimeters, to 5 irradiation times (20; 30; 40; 50 and 60 seconds) and by linear regression, the dose rate of 5.400648 kGy /h was determined in the central point of the irradiation chamber (irradiator Gamma cell 220 Excel), applying the decay formula, was compared with the obtained results by manufacturers by means the same dosimetric system in the year of its manufacture, being this to the date 5.44691 kGy /h, with an error rate of 0.85. After considering that the dosimetric solution responds to the results, we proceeded to the irradiation of a sample of 200 g of cereal instant food, 2 dosimeters were placed at the lateral ends of the central position to maximum dose and 2 dosimeters in upper and lower ends as minimum dose, they were applied same irradiation times; for statistical analysis, the maximum dose rate was 6.1006 kGy /h and the minimum dose rate of 5.2185 kGy /h; with a dose uniformity of 1.16. In medical material of micro pulverized bone for

Radiation dose to Sri Lankan infants from Caesium-137 in contaminated milk

International Nuclear Information System (INIS)

Hewamanna, R.; Dias, M.P.

1999-01-01

The radiation dose to infants due to ingestion of milk containing the maximum limit of radioactivity in milk powder imported to Sri Lanka has been calculated. The radioactivity of Cs-137 was used as an index of fission products for setting radioactivity limits. The computation for milk powder was based on an average daily intake of 125 g by infants, (a critical group of population) during the first year after birth. The recommended dose commitment to the general public is 1 mSv/y. The maximum permissible limit of 20 Bq/kg of Cs-137 in milk powder as stipulated by the Atomic Energy Authority for milk powder imported to Sri Lanka would yield a dose equivalent of 12.6 micro seivert/y from Cs-137

Neutron spectrum and dose-equivalent in shuttle flights during solar maximum

Energy Technology Data Exchange (ETDEWEB)

Keith, J E; Badhwar, G D; Lindstrom, D J [National Aeronautics and Space Administration, Houston, TX (United States). Lyndon B. Johnson Space Center

1992-01-01

This paper presents unambiguous measurements of the spectrum of neutrons found in spacecraft during spaceflight. The neutron spectrum was measured from thermal energies to about 10 MeV using a completely passive system of metal foils as neutron detectors. These foils were exposed to the neutron flux bare, covered by thermal neutron absorbers (Gd) and inside moderators (Bonner spheres). This set of detectors was flown on three U.S. Space Shuttle flights, STS-28, STS-36 and STS-31, during the solar maximum. We show that the measurements of the radioactivity of these foils lead to a differential neutron energy spectrum in all three flights that can be represented by a power law, J(E){approx equal}E{sup -0.765} neutrons cm{sup -2} day {sup -1} MeV{sup -1}. We also show that the measurements are even better represented by a linear combination of the terrestrial neutron albedo and a spectrum of neutrons locally produced in a aluminium by protons, computed by a previous author. We use both approximations to the neutron spectrum to produce a worst case and most probable case for the neutron spectra and the resulting dose-equivalents, computed using ICRP-51 neutron fluence-dose conversion tables. We compare these to the skin dose-equivalents due to charged particles during the same flights. (author).

Treatment of advanced pancreatic carcinoma with 90Y-Clivatuzumab Tetraxetan: a phase I single-dose escalation trial.

Science.gov (United States)

Gulec, Seza A; Cohen, Steven J; Pennington, Kenneth L; Zuckier, Lionel S; Hauke, Ralph J; Horne, Heather; Wegener, William A; Teoh, Nick; Gold, David V; Sharkey, Robert M; Goldenberg, David M

2011-06-15

Humanized antibody hPAM4 specifically binds a mucin glycoprotein expressed in pancreatic adenocarcinomas. This phase I study evaluated a single dose of (90)Y-clivatuzumab tetraxetan ((90)Y-labeled hPAM4) in patients with advanced pancreatic cancer. Twenty-one patients (4 stage III; 17 stage IV) received (111)In-hPAM4 for imaging and serum sampling before (90)Y-hPAM4. Study procedures evaluated adverse events, safety laboratories, computed tomography (CT) scans, biomarkers, pharmacokinetics, radiation dosimetry, and immunogenicity (HAHA). (111)In-hPAM4 showed normal biodistribution with radiation dose estimates to red marrow and solid organs acceptable for radioimmunotherapy and with tumor targeting in 12 patients. One patient withdrew before (90)Y-hPAM4; otherwise, 20 patients received (90)Y doses of 15 (n = 7), 20 (n = 9), and 25 mCi/m(2) (n = 4). Treatment was well tolerated; the only significant drug-related toxicities were (NCI CTC v.3) grade 3 to 4 neutropenia and thrombocytopenia increasing with (90)Y dose. There were no bleeding events or serious infections, and most cytopenias recovered to grade 1 within 12 weeks. Three patients at 25 mCi/m(2) encountered dose-limiting toxicity with grade 4 cytopenias more than 7 days, establishing 20 mCi/m(2) as the maximal tolerated (90)Y dose. Two patients developed HAHA of uncertain clinical significance. Most patients progressed rapidly and with CA19-9 levels increasing within 1 month of therapy, but 7 remained progression-free by CT for 1.5 to 5.6 months, including 3 achieving transient partial responses (32%-52% tumor diameter shrinkage). (90)Y-Clivatuzumab tetraxetan was well tolerated with manageable hematologic toxicity at the maximal tolerated (90)Y dose, and is a potential new therapeutic for advanced pancreatic cancer. ©2011 AACR.

Prediction of the maximum dosage to man from the fallout of nuclear devices V. Estimation of the maximum dose from internal emitters in aquatic food supply

International Nuclear Information System (INIS)

Tamplin, A.R.; Fisher, H.L.; Chapman, W.H.

1968-01-01

A method is described for estimating the maximum internal dose that could result from the radionuclides released to an aquatic environment. By means of this analysis one can identify the nuclides that could contribute most to the internal dose, and determine the contribution of each nuclide to the total dose. The calculations required to estimate the maximum dose to an infant's bone subsequent to the construction of a sea-level canal are presented to illustrate the overall method. The results are shown to serve the basic aims of preshot rad-safe analysis and of guidance for postshot documentation. The usefulness of the analysis in providing guidance for device design is further pointed out. (author)

Calculate the maximum expected dose for technical radio physicists a cobalt machine

International Nuclear Information System (INIS)

Avila Avila, Rafael; Perez Velasquez, Reytel; Gonzalez Lapez, Nadia

2009-01-01

Considering the daily operations carried out by technicians Radiophysics Medical Service Department of Radiation Oncology Hospital V. General Teaching I. Lenin in the city of Holguin, during a working week (Between Monday and Friday) as an important element in calculating the maximum expected dose (MDE). From the exponential decay law which is subject the source activity, we propose corrections to the cumulative doses in the weekly period, leading to obtaining a formula which takes into a cumulative dose during working days and sees no dose accumulation of rest days (Saturday and Sunday). The estimate factor correction is made from a power series expansion convergent is truncated at the n-th term coincides with the week period for which you want to calculate the dose. As initial condition is adopted ambient dose equivalent rate as a given, which allows estimate MDE in the moments after or before this. Calculations were proposed use of an Excel spreadsheet that allows simple and accessible processing the formula obtained. (author)

Application of maximum values for radiation exposure and principles for the calculation of radiation doses

International Nuclear Information System (INIS)

2007-08-01

The guide presents the definitions of equivalent dose and effective dose, the principles for calculating these doses, and instructions for applying their maximum values. The limits (Annual Limit on Intake and Derived Air Concentration) derived from dose limits are also presented for the purpose of monitoring exposure to internal radiation. The calculation of radiation doses caused to a patient from medical research and treatment involving exposure to ionizing radiation is beyond the scope of this ST Guide

Exposure dose estimation of nursing personnel and visitors following "1"2"5I brachytherapy

International Nuclear Information System (INIS)

Nakazato, Kazuhisa; Kikuchi, Hirosumi; Hotta, Harumi; Nishizawa, Kunihide

2007-01-01

An automated access management system to the controlled sickrooms for "1"2"5I brachytherapy was developed. The system consists of access control and video surveillance units. The patients implanted "1"2"5I seeds were isolated for about 20 h after surgery in the controlled sickrooms. The maximum doses and dose rates of the nurses and visitors were estimated by using the legal upper limit activity of 1,300 MBq, the measured longest staying time, and the shortest distance between the patients and individuals. Video analysis revealed activities of the nurses, patients, and visitors in the controlled sickroom, and relationships between the access frequency and staying time. The nurses' measured doses ranged from 1 to 3 μSv, and averaged 1.6 μSv. The nurses' maximum dose and dose rate were 16 μSv and 5.6 nSv·h"-"1·MBq"-"1. The visitors' maximum dose and dose rate were 6 μSv and 2.6 nSv·h"-"1·MBq"-"1. The nurses and visitors' exposure doses per patient were estimated to be negligible compared with the annual limit of the public. (author)

Somatostatin-based radiotherapy with [90Y-DOTA]-TOC in neuroendocrine tumors: long-term outcome of a phase I dose escalation study.

Science.gov (United States)

Marincek, Nicolas; Jörg, Ann-Catherine; Brunner, Philippe; Schindler, Christian; Koller, Michael T; Rochlitz, Christoph; Müller-Brand, Jan; Maecke, Helmut R; Briel, Matthias; Walter, Martin A

2013-01-15

We describe the long-term outcome after clinical introduction and dose escalation of somatostatin receptor targeted therapy with [90Y-DOTA]-TOC in patients with metastasized neuroendocrine tumors. In a clinical phase I dose escalation study we treated patients with increasing [90Y-DOTA]-TOC activities. Multivariable Cox regression and competing risk regression were used to compare efficacy and toxicities of the different dosage protocols. Overall, 359 patients were recruited; 60 patients were enrolled for low dose (median: 2.4 GBq/cycle, range 0.9-7.8 GBq/cycle), 77 patients were enrolled for intermediate dose (median: 3.3 GBq/cycle, range: 2.0-7.4 GBq/cycle) and 222 patients were enrolled for high dose (median: 6.7 GBq/cycle, range: 3.7-8.1 GBq/cycle) [90Y-DOTA]-TOC treatment. The incidences of hematotoxicities grade 1-4 were 65.0%, 64.9% and 74.8%; the incidences of grade 4/5 kidney toxicities were 8.4%, 6.5% and 14.0%, and the median survival was 39 (range: 1-158) months, 34 (range: 1-118) months and 29 (range: 1-113) months. The high dose protocol was associated with an increased risk of kidney toxicity (Hazard Ratio: 3.12 (1.13-8.59) vs. intermediate dose, p = 0.03) and a shorter overall survival (Hazard Ratio: 2.50 (1.08-5.79) vs. low dose, p = 0.03). Increasing [90Y-DOTA]-TOC activities may be associated with increasing hematological toxicities. The dose related hematotoxicity profile of [90Y-DOTA]-TOC could facilitate tailoring [90Y-DOTA]-TOC in patients with preexisting hematotoxicities. The results of the long-term outcome suggest that fractionated [90Y-DOTA]-TOC treatment might allow to reduce renal toxicity and to improve overall survival. (ClinicalTrials.gov number NCT00978211).

Application of maximum values for radiation exposure and principles for the calculation of radiation dose

International Nuclear Information System (INIS)

2000-01-01

The guide sets out the mathematical definitions and principles involved in the calculation of the equivalent dose and the effective dose, and the instructions concerning the application of the maximum values of these quantities. further, for monitoring the dose caused by internal radiation, the guide defines the limits derived from annual dose limits (the Annual Limit on Intake and the Derived Air Concentration). Finally, the guide defines the operational quantities to be used in estimating the equivalent dose and the effective dose, and also sets out the definitions of some other quantities and concepts to be used in monitoring radiation exposure. The guide does not include the calculation of patient doses carried out for the purposes of quality assurance

Application of maximum values for radiation exposure and principles for the calculation of radiation dose

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-07-01

The guide sets out the mathematical definitions and principles involved in the calculation of the equivalent dose and the effective dose, and the instructions concerning the application of the maximum values of these quantities. further, for monitoring the dose caused by internal radiation, the guide defines the limits derived from annual dose limits (the Annual Limit on Intake and the Derived Air Concentration). Finally, the guide defines the operational quantities to be used in estimating the equivalent dose and the effective dose, and also sets out the definitions of some other quantities and concepts to be used in monitoring radiation exposure. The guide does not include the calculation of patient doses carried out for the purposes of quality assurance.

Studies on the establishment of maximum permissible exposure dose for reference Korean

International Nuclear Information System (INIS)

Kim, Y.J.; Lee, K.S.; Chun, K.C.; Kim, C.B.; Chung, K.H.; Kim, S.L.; Kim, M.J.

1981-01-01

In order to establish the Reference Korean and maximum permissible exposure dose of Reference Korean, for the first year a total of 9,758 males and 7,019 females were surveyed for the height, weight, a body surface area, and a total of 879 individuals of 180 households located in different 30 localities were analyzed for food consumption and a total of radioactive substances (β-ray) contained in food per capita per day. In this report the external and internal exposure dose were also estimated on the basis of data mostly published in other country as well as in Korea in part

Rendimiento y calidad de semilla de pasto guinea (Panicum maximum Jacq. cv. Tanzania usando la fitohormona esteroidal cidef-4

Directory of Open Access Journals (Sweden)

Bertín Maurilio Joaquín Torres

2010-01-01

Full Text Available El objetivo fue evaluar el efecto de la fitohormona esteroidal cidef-4 en el rendimiento y calidad de semilla en Panicum maximum cv. Tanzania. El experimento se realizó durante el 2001 en Tejupilco, Estado de México. Los tratamientos evaluados fueron, T1=testigo, T2=4 mg L-1 de ingrediente activo (i.a. aplicados al inicio de antesis, T3=4 mg L-1 de i.a. aplicados antes del espigamiento e inicio de antesis, T4=8 mg L-1 de i.a. aplicados al inicio de antesis, T5=8 mg L-1 de i.a. aplicados antes del espigamiento e inicio de antesis y T6=12 mg L-1 de i.a. aplicados únicamente al inicio de antesis. Se utilizó un diseño de bloques al azar, con tres repeticiones. Se evaluó el rendimiento de semilla total (RST, rendimiento de semilla pura (RSP, número de panículas m-2, longitud de panícula, semillas producidas y cosechadas por panícula, peso de 1,000 semillas y germinación. Se detectaron diferencias (P0.05 entre tratamientos. Se concluye que la fitohormona esteroidal cidef-4 incrementó el rendimiento de semilla de P. maximum cv. tanzania, independientemente de la concentración y momento de aplicación. La calidad de la semilla, no fue afectada por ninguno de los tratamientos evaluados.

Maximum tolerated dose in a phase I trial on adaptive dose painting by numbers for head and neck cancer

International Nuclear Information System (INIS)

Madani, Indira; Duprez, Fréderic; Boterberg, Tom; Van de Wiele, Christophe; Bonte, Katrien; Deron, Philippe; De Gersem, Werner; Coghe, Marc; De Neve, Wilfried

2011-01-01

Purpose: To determine the maximum tolerated dose (MTD) in a phase I trial on adaptive dose-painting-by-numbers (DPBN) for non-metastatic head and neck cancer. Materials and methods: Adaptive intensity-modulated radiotherapy was based on voxel intensity of pre-treatment and per-treatment [ 18 F]fluoro-2-deoxy-D-glucose positron emission tomography ( 18 F-FDG-PET) scans. Dose was escalated to a median total dose of 80.9 Gy in the high-dose clinical target volume (dose level I) and 85.9 Gy in the gross tumor volume (dose level II). The MTD would be reached, if ⩾33% of patients developed any grade ⩾4 toxicity (DLT) up to 3 months follow-up. Results: Between February 2007 and August 2009, seven patients at dose level I and 14 at dose level II were treated. All patients completed treatment without interruption. At a median follow-up for surviving patients of 38 (dose level I) and 22 months (dose level II) there was no grade ⩾4 toxicity during treatment and follow-up but six cases of mucosal ulcers at latency of 4–10 months, of which five (36%) were observed at dose level II. Mucosal ulcers healed spontaneously in four patients. Conclusions: Considering late mucosal ulcers as DLT, the MTD of a median dose of 80.9 Gy has been reached in our trial.

Hazards and maximum permissible doses of radiation for man

International Nuclear Information System (INIS)

Walinder, G.

1977-11-01

Maximum permissible dose levels are primarely based on risks for genetic damage and cancer. The reason for this is the observation that such late effects of radiation seem to arise even after doses that are to low to give rise to acute effects. In contrast to the tumour incidence found in irradiated human populations no genetic effects of radiation have been observed in man. This does not mean that genetic effects have not been induced but that it has been impossible to find an increase or to discern them among all the congenital defects, that can not be ascribed to the irradiation. As a consequence, the radiological risk estimation has been concentrated on the hazard of malignant diseases. Tumour risks are generally expressed as excess rates of incidence and mortality per million persons per rem. These figures are, however, not obtained from direct epidemiological observations but have been calculated from such data under the assumption of a linear relationship between effect and radiation dose. This formal extrapolation of observed data involves an uncertainty which, of course, is proportionately greater for the calculated effects in the millirem range. However, although the calculated tumour risks can not be said to be founded on direct scientific evidence, there are scientific reasons to believe that the figures derived from the formal extrapolations constitute an upper limit of possible ri02050

The Northern Marshall Islands Radiological Survey: data and dose assessments.

Science.gov (United States)

Robison, W L; Noshkin, V E; Conrado, C L; Eagle, R J; Brunk, J L; Jokela, T A; Mount, M E; Phillips, W A; Stoker, A C; Stuart, M L; Wong, K M

1997-07-01

Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for 137Cs, 90Sr, 239+240Pu and 241Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from 137Cs. 90Sr is the second most significant radionuclide via ingestion. External gamma exposure from 137Cs accounts for about 10% to 30% of the dose. 239+240Pu and 241Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y(-1) to 2.1 mSv y(-1). The background dose in the Marshall Islands is estimated to be 2.4 mSv y(-1). The combined dose from both background and bomb related radionuclides ranges from slightly

Somatostatin-based radiotherapy with [90Y-DOTA]-TOC in neuroendocrine tumors: long-term outcome of a phase I dose escalation study

Directory of Open Access Journals (Sweden)

Marincek Nicolas

2013-01-01

Full Text Available Abstract Background We describe the long-term outcome after clinical introduction and dose escalation of somatostatin receptor targeted therapy with [90Y-DOTA]-TOC in patients with metastasized neuroendocrine tumors. Methods In a clinical phase I dose escalation study we treated patients with increasing [90Y-DOTA]-TOC activities. Multivariable Cox regression and competing risk regression were used to compare efficacy and toxicities of the different dosage protocols. Results Overall, 359 patients were recruited; 60 patients were enrolled for low dose (median: 2.4 GBq/cycle, range 0.9-7.8 GBq/cycle, 77 patients were enrolled for intermediate dose (median: 3.3 GBq/cycle, range: 2.0-7.4 GBq/cycle and 222 patients were enrolled for high dose (median: 6.7 GBq/cycle, range: 3.7-8.1 GBq/cycle [90Y-DOTA]-TOC treatment. The incidences of hematotoxicities grade 1–4 were 65.0%, 64.9% and 74.8%; the incidences of grade 4/5 kidney toxicities were 8.4%, 6.5% and 14.0%, and the median survival was 39 (range: 1–158 months, 34 (range: 1–118 months and 29 (range: 1–113 months. The high dose protocol was associated with an increased risk of kidney toxicity (Hazard Ratio: 3.12 (1.13-8.59 vs. intermediate dose, p = 0.03 and a shorter overall survival (Hazard Ratio: 2.50 (1.08-5.79 vs. low dose, p = 0.03. Conclusions Increasing [90Y-DOTA]-TOC activities may be associated with increasing hematological toxicities. The dose related hematotoxicity profile of [90Y-DOTA]-TOC could facilitate tailoring [90Y-DOTA]-TOC in patients with preexisting hematotoxicities. The results of the long-term outcome suggest that fractionated [90Y-DOTA]-TOC treatment might allow to reduce renal toxicity and to improve overall survival. (ClinicalTrials.gov number NCT00978211.

Somatostatin-based radiotherapy with [90Y-DOTA]-TOC in neuroendocrine tumors: long-term outcome of a phase I dose escalation study

Science.gov (United States)

2013-01-01

Background We describe the long-term outcome after clinical introduction and dose escalation of somatostatin receptor targeted therapy with [90Y-DOTA]-TOC in patients with metastasized neuroendocrine tumors. Methods In a clinical phase I dose escalation study we treated patients with increasing [90Y-DOTA]-TOC activities. Multivariable Cox regression and competing risk regression were used to compare efficacy and toxicities of the different dosage protocols. Results Overall, 359 patients were recruited; 60 patients were enrolled for low dose (median: 2.4 GBq/cycle, range 0.9-7.8 GBq/cycle), 77 patients were enrolled for intermediate dose (median: 3.3 GBq/cycle, range: 2.0-7.4 GBq/cycle) and 222 patients were enrolled for high dose (median: 6.7 GBq/cycle, range: 3.7-8.1 GBq/cycle) [90Y-DOTA]-TOC treatment. The incidences of hematotoxicities grade 1–4 were 65.0%, 64.9% and 74.8%; the incidences of grade 4/5 kidney toxicities were 8.4%, 6.5% and 14.0%, and the median survival was 39 (range: 1–158) months, 34 (range: 1–118) months and 29 (range: 1–113) months. The high dose protocol was associated with an increased risk of kidney toxicity (Hazard Ratio: 3.12 (1.13-8.59) vs. intermediate dose, p = 0.03) and a shorter overall survival (Hazard Ratio: 2.50 (1.08-5.79) vs. low dose, p = 0.03). Conclusions Increasing [90Y-DOTA]-TOC activities may be associated with increasing hematological toxicities. The dose related hematotoxicity profile of [90Y-DOTA]-TOC could facilitate tailoring [90Y-DOTA]-TOC in patients with preexisting hematotoxicities. The results of the long-term outcome suggest that fractionated [90Y-DOTA]-TOC treatment might allow to reduce renal toxicity and to improve overall survival. Trial registration ClinicalTrials.gov number:NCT00978211 PMID:23320604

Technical basis for beta skin dose calculations at the Y-12 Plant

International Nuclear Information System (INIS)

Thomas, J.M.; Bogard, R.S.

1994-03-01

This report describes the methods for determining shallow dose equivalent to workers at the Oak Ridge Y-12 Plant from skin contamination detected by survey instrumentation. Included is a discussion of how the computer code VARSKIN is used to calculate beta skin dose and how the code input parameters affect skin dose calculation results. A summary of Y-12 Plant specific assumptions used in performing VARSKIN calculations is presented. Derivations of contamination levels that trigger the need for skin dose assessment are given for both enriched and depleted uranium with the use of Y-12 Plant site-specific survey instruments. Department of Energy recording requirements for nonuniform exposure of the skin are illustrated with sample calculations

The Northern Marshall Islands radiological survey: Data and dose assessments

International Nuclear Information System (INIS)

Robison, W.L.; Noshkin, V.E.; Conrado, C.L.

1997-01-01

Fallout from atmospheric nuclear tests, especially from those conducted at the Pacific Proving Grounds between 1946 and 1958, contaminated areas of the Northern Marshall Islands. A radiological survey at some Northern Marshall Islands was conducted from September through November 1978 to evaluate the extent of residual radioactive contamination. The atolls included in the Northern Marshall Islands Radiological Survey (NMIRS) were Likiep, Ailuk, Utirik, Wotho, Ujelang, Taka, Rongelap, Rongerik, Bikar, Ailinginae, and Mejit and Jemo Islands. The original test sites, Bikini and Enewetak Atolls, were also visited on the survey. An aerial survey was conducted to determine the external gamma exposure rate. Terrestrial (soil, food crops, animals, and native vegetation), cistern and well water samples, and marine (sediment, seawater, fish and clams) samples were collected to evaluate radionuclide concentrations in the atoll environment. Samples were processed and analyzed for 137 Cs, 90 Sr, 239+240 Pu and 241 Am. The dose from the ingestion pathway was calculated using the radionuclide concentration data and a diet model for local food, marine, and water consumption. The ingestion pathway contributes 70% to 90% of the estimated dose. Approximately 95% of the dose is from 137 Cs accounts for about 10% to 30% of the dose. 239+240 Pu and 241 Am are the major contributors to dose via the inhalation pathway; however, inhalation accounts for only about 1% of the total estimated dose, based on surface soil levels and resuspension studies. All doses are computed for concentrations decay corrected to 1996. The maximum annual effective dose from manmade radionuclides at these atolls ranges from .02 mSv y -1 . The background dose in the Marshall Islands is estimated to be 2.4 mSv y -1 to 4.5 mSv y -1 . The 50-y integral dose ranges from 0.5 to 65 mSv. 35 refs., 2 figs., 9 tabs

Efecto de la altura de poda en Leucaena leucocephala y su influencia en el rebrote y rendimiento de Panicum maximum

Directory of Open Access Journals (Sweden)

H. M. Bacab

2012-01-01

Full Text Available Una de las prácticas importantes de manejo en los sistemas de Leucaena leucocephala asociada con pastos tropicales, como Panicum maximum, es la poda; en la actualidad se continúan los estudios para determinar los efectos de esta práctica en el componente arbóreo y herbáceo. Por todo ello, en el presente trabajo se evaluó el efecto de tres alturas de poda en Leucaena leucocephala cv. Cunningham y su influencia en la pastura asociada (Panicum maximum cv. Tanzania. El estudio se realizó en la época poco lluviosa del año (marzo a mayo de 2010, se utilizó un diseño de bloques completos al azar con cuatro repeticiones. Al inicio del experimento se asignaron los tratamientos (alturas de poda de 20, 40 y 60 cm sobre el nivel del suelo para Leucaena leucocephala. En el caso de Panicum maximum, se realizó una poda a 5 cm sobre el nivel del suelo en todas las parcelas experimentales. Los resultados obtenidos indicaron que la poda de la leguminosa a 40 y 60 cm permitió obtener brotes de mayor talla, sin afectar a la gramínea asociada. De igual manera, al incrementar la altura de poda, la leguminosa presentó mayor rendimiento y proporción de forraje comestible; sin embargo, se afectó negativamente a la pastura asociada. Ante ello, considerándose el aspecto animal, se recomienda no reducir la altura de poda de Leucaena leucocephala a menos de 40 cm, ya que se reduce significativamente el rendimiento y la proporción de forraje comestible de esta leguminosa, el cual es de mayor calidad para la alimentación animal.

Reduction in cardiovascular risk factors and insulin dose, but no beta-cell regeneration 1 year after Roux-en-Y gastric bypass in an obese patient with type 1 diabetes

DEFF Research Database (Denmark)

Dirksen, Carsten; Jacobsen, Siv H; Bojsen-Møller, Kirstine N

2013-01-01

Experience with Roux-en-Y gastric bypass in patients with type 1 diabetes is very limited, despite an increasing prevalence of obesity also in this population. We describe changes in anthropometric measures, insulin dose, HbA1c, blood pressure, lipid status, and metabolic response to a liquid mixed...... meal throughout the first year after RYGB in an obese patient with type 1 diabetes. No change in HbA1c was observed, but a 48% reduction in weight-adjusted insulin dose and improvements in cardiovascular risk factors was seen 1 year after surgery. Exaggerated secretions of anorexigenic gut hormones...

Radiolabeling optimization and reduced staff radiation exposure for high-dose 90Y-ibritumomab tiuxetan (HD-Zevalin)

International Nuclear Information System (INIS)

Papi, Stefano; Martano, Luigi; Garaboldi, Lucia; Rossi, Annalisa; Cremonesi, Marta; Grana, Chiara Maria; Paolucci, Daniele; Sansovini, Maddalena; Paganelli, Giovanni; Chinol, Marco

2010-01-01

Introduction: 90 Y-Zevalin labeling may cause severe finger radiation exposure, especially in high-dose protocols (HD-Zevalin), where up to 7.4 GBq could be injected. In this work, we optimized the labeling of HD-Zevalin with special regard to simplicity, speed, safety and radiation protection. Methods: Factors influencing labeling outcome (activity, specific activity, time, final volume, stability) were studied separately. The critical steps of a standard radiolabeling procedure were optimized to reduce finger exposure, developing an alternative labeling procedure and including a different 90 Y supplier. Finger doses were monitored by thermoluminescent dosimeters at each fingertip under anti-X gloves, considering both absolute values and values after normalization to 1.48 GBq. Results: Labeling of 90 Y-Zevalin was safe and reproducible up to 7.4 GBq with a simple and single-step procedure offering good stability for several hours. Radiolabeling specific activity was found critical, being kept at 740 MBq.mg -1 . Radiochemical purity values ≥98% were routinely achieved. The alternative procedure allowed a sensible reduction of finger dose, due to both the different 90 Y vial and the handling. Finger exposure was reduced from 6.6±4.3 to 3.1±0.8 mSv/1.48 GBq in the case of the original 90 Y vial and from 1.5±0.9 to 0.3±0.1 mSv/1.48 GBq using a shielded 90 Y vial. Conclusions: HD-Zevalin can be prepared in a safe and reproducible way, giving high radiochemical purity values, good stability and low finger exposure. This study may improve the safety of nuclear medicine professionals involved in the preparation of Zevalin.

Maximum likelihood estimation of dose-response parameters for therapeutic operating characteristic (TOC) analysis of carcinoma of the nasopharynx

International Nuclear Information System (INIS)

Metz, C.E.; Tokars, R.P.; Kronman, H.B.; Griem, M.L.

1982-01-01

A Therapeutic Operating Characteristic (TOC) curve for radiation therapy plots, for all possible treatment doses, the probability of tumor ablation as a function of the probability of radiation-induced complication. Application of this analysis to actual therapeutic situation requires that dose-response curves for ablation and for complication be estimated from clinical data. We describe an approach in which ''maximum likelihood estimates'' of these dose-response curves are made, and we apply this approach to data collected on responses to radiotherapy for carcinoma of the nasopharynx. TOC curves constructed from the estimated dose-response curves are subject to moderately large uncertainties because of the limitations of available data.These TOC curves suggest, however, that treatment doses greater than 1800 rem may substantially increase the probability of tumor ablation with little increase in the risk of radiation-induced cervical myelopathy, especially for T1 and T2 tumors

External radiation dose from patients received diagnostic doses of 201 T1-Chloride and 99 Tc-MIBI

International Nuclear Information System (INIS)

Dadashzadeh, S.; Sattari, A.; Nasiroghli, G.A.

2002-01-01

Patients receiving diagnostic doses of radiopharmaceuticals become a source of contamination and exposure for those who come in contact with them, such as nuclear medicine technologists, relatives and nurses. Therefore, the measurement of external radiation dose from these patients is necessary. In this study, the dose rates at distances of 10, 50 and 100 cm from 70 patients who received diagnostic amounts of 201 T1-Chloride and 99 Tc-MIBI was measures. The results showed that the maximum external radiation dose rates for 201 T1 and 99 Tc-MIBI were 18.4 and 75.0 μ Sv.h -1 , respectively, at 5 cm distance from the patients. The average radiation dose received by nuclear medicine technologists, considering their close contact during one working day was 12.5 ± 3.4μ Sv. The highest received dose was 22.7 μSv, which was well below the acceptable dose limit

[MAXIMUM SINGLE DOSE OF COLLOIDAL SILVER NEGATIVELY AFFECTS ERYTHROPOIESIS IN VITRO].

Science.gov (United States)

Tishevskayal, N V; Zakharovl, Y M; Bolotovl, A A; Arkhipenko, Yu V; Sazontova, T G

2015-01-01

Erythroblastic islets (EI) of rat bone marrow were cultured for 24 h in the presence of silver nanoparticles (1.07 · 10(-4) mg/ml; 1.07 · 10(-3) mg/ml; and 1.07 · 10(-2) mg/mL). The colloidal silver at 1.07 · 10(-3) mg/ml concentration inhibited the formation of new Elby disrupting contacts of bone marrow macrophages with CFU-E (erythropoiesis de novo) by 65.3% (p Colloidal silver nanoparticles suppressed the reconstruction of erythropoiesis and inhibited the formation of new EI by disrupting contacts of CFU-E and central macrophages with matured erythroidal "crown" (erythropoiesis de repeto). The colloidal silver concentration of 1.07 · 10(-3) mg/ml in the culture medium also reduced the number of self-reconstructing EI by 67.5% (p colloidal silver reduced this value by 93.7% (p Silver nanoparticles retarded maturation of erythroid cells at the stage of oxiphylic normoblast denucleation: 1.07 · 10(-3) mg/ml colloidal silver increased the number of mature El by 53% (p colloidal silver in concentration equivalent to the maximum single dose is related to the effect of silver nanoparticles rather than glycerol present in the colloidal suspension.

Is the standard dose rate for de-contamination, 0.23 mc-Sv/hr, truly 1 mSv/year?

International Nuclear Information System (INIS)

Furuta, Sadaaki

2014-01-01

Examined is the validity of the standard dose rates in the title, which have been additionally defined by Ministry of the Environment (ME) to the measures of Fukushima Nuclear Power Plant Accident. The standard 0.23 mc-Sv/hr is the sum of natural ambient dose rate 0.04 mc-Sv/hr in average of Japan as measured with NaI scintillation surveymeter, plus additional accidental exposure dose 1 mSv/y, which is defined equivalent to 0.19 mc-Sv/hr. Here, the equation of addition 0.04+0.19 mc-Sv/hr is not exactly correct because the unit of each dose value has different means as follows. The natural dose is derived from the value 5.8 mc-R/hr (0.038 mc-Sv/hr, effective dose) of the average national natural dose data (2011) of Ministry of Education, Culture, Sports, Science and Technology. However, if the measurement is done with the surveymeter which practically gives 1 cm dose equivalent, the rate is calculated to be 0.06 mc-Sv/hr. When the Fukushima prefectural natural dose rate 6.4 mc-R/hr is employed, the calculation gives 0.07 mc-Sv/hr. ME defines the additional doses to be 0.19 mc-Sv/hr and 1 mSv/y, which are derived from the calculation: (0.19 mc-Sv/hr x 8 hr outdoor + 0.19 mc-Sv/hr x 0.4 indoor, shielded) x 365 d/y= 1 mSv/y. The dose is assumed to be measurable with the surveymeter (1 cm dose equivalent) and thereby calculation, if the source is mainly "1"3"4Cs and "1"3"7Cs, gives the effective dose of 0.32 mc-Sv/hr to be managed by the meter. As this, the effective dose unit and 1 cm equivalent dose unit are used for calculation of the administrative standard dose rate of 1 mSv/y, which should be recognized by both radiological experts and administration for the explanation to general public. (T.T.)

Potential radionuclide emissions from stacks on the Hanford Site. Part 1: Dose assessment

International Nuclear Information System (INIS)

Davis, W.E.; Barnett, J.M.

1994-06-01

On February 3, 1993, the US Department of Energy, Richland Operations Office (RL) received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency (EPA), Region 10. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company (WHC) stacks registered with the Washington State Department of Health (WAC 246-247) on the Hanford Site. Stacks that have the potential emissions to cause an effective dose equivalent (EDE) to a maximum exposed individual (MEI) greater than 0.1 mrem y -1 must be monitored continuously for radionuclide emissions. Five methods were approved by EPA, Region 10 for performing the assessments: Release Fractions from Appendix D of 40 CFR 61, Back Calculations Using A HEPA Filtration Factor, Nondestructive Assay of HEPA Filters, A Spill Release Fraction, and Upstream of HEPA Filter Air Concentrations. The first two methods were extremely conservative for estimating releases. The third method which used a state-of-the-art portable gamma spectrometer, yielded surprising results from the distribution of radionuclides on the HEPA filters. All five methods are described

Dose assessment around TR-2 reactor due to maximum credible accident

International Nuclear Information System (INIS)

Turgut, M. H.; Adalioglu, U.; Aytekin, A.

2001-01-01

The revision of safety analysis report of TR-2 research reactor had been initiated in 1995. The whole accident analysis and accepted scenario for maximum credible accident has been revised according to the new safety concepts and the impact to be given to the environment due to this scenario has been assessed. This paper comprises all results of these calculations. The accepted maximum credible accident scenario is the partial blockage of the whole reactor core which resulted in the release of 25% of the core inventory. The DOSER code which uses very conservative modelling of atmospheric distributions were modified for the assessment calculations. Pasquill conditions based on the local weather observations, topography, and building affects were considered. The thyroid and whole body doses for 16 sectors and up to 10 km of distance around CNAEM were obtained. Release models were puff and a prolonged one of two hours of duration. Release fractions for the active isotopes were chosen from literature which were realistic

Correlation of patient maximum skin doses in cardiac procedures with various dose indicators

International Nuclear Information System (INIS)

Domienik, J.; Papierz, S.; Jankowski, J.; Peruga, J.Z.; Werduch, A.; Religa, W.

2008-01-01

In most countries of European Union, legislation requires the determination of the total skin dose received by patients during interventional procedures in order to prevent deterministic damages. Various dose indicators like dose-area product (DAP), cumulative dose (CD) and entrance dose at the patient plane (EFD) are used for patient dosimetry purposes in clinical practice. This study aimed at relating those dose indicators with doses ascribed to the most irradiated areas of the patient skin usually expressed in terms of local maximal skin dose (MSD). The study was performed in two different facilities for two most common cardiac procedures coronary angiography (CA) and percutaneous coronary interventions (PCI). For CA procedures, the registered values of fluoroscopy time, total DAP and MSD were in the range (0.7-27.3) min, (16-317) Gy cm 2 and (43-1507) mGy, respectively, and for interventions, accordingly (2.1-43.6) min, (17-425) Gy cm 2 , (71-1555) mGy. Moreover, for CA procedures, CD and EFD were in the ranges (295-4689) mGy and (121-1768) mGy and for PCI (267-6524) mGy and (68-2279) mGy, respectively. No general and satisfactory correlation was found for safe estimation of MSD. However, results show that the best dose indicator which might serve for rough, preliminary estimation is DAP value. In the study, the appropriate trigger levels were proposed for both facilities. (authors)

Phase I/II 90Y-Zevalin (yttrium-90 ibritumomab tiuxetan, IDEC-Y2B8) radioimmunotherapy dosimetry results in relapsed or refractory non-Hodgkin's lymphoma

International Nuclear Information System (INIS)

Wiseman, G.A.; Dunn, W.L.; White, C.A.; Berlfein, J.R.; Ding, E.; Grillo-Lopez, A.J.; Stabin, M.; Erwin, W.; Spies, S.; Dahlbom, M.; Silverman, D.H.S.; Raubitschek, A.; Karvelis, K.; Schultheiss, T.; Witzig, T.E.; Belanger, R.

2000-01-01

Dosimetry studies in patients with non-Hodgkin's lymphoma were performed to estimate the radiation absorbed dose to normal organs and bone marrow from 90 Y-Zevalin (yttrium-90 ibritumomab tiuxetan, IDEC-Y2B8) treatment in this phase I/II, multicenter trial. The trial was designed to determine the dose of Rituximab (chimeric anti-CD20, Rituxan, IDEC-C2B8, MabThera), the unlabeled antibody given prior to the radioconjugate to clear peripheral blood B cells and optimize distribution, and to determine the maximum tolerated dose of 90 Y-Zevalin [7.4, 11, or 15 MBq/kg (0.2, 0.3, or 0.4 mCi/kg)]. Patients received 111 In-Zevalin (indium-111 ibritumomab tiuxetan, IDEC-In2B8) on day 0 followed by a therapeutic dose of 90 Y-Zevalin on day 7. Both doses were preceded by an infusion of the chimeric, unlabeled antibody Rituximab. Following administration of 111 In-Zevalin, serial anterior/posterior whole-body scans were acquired. Major-organ radioactivity versus time estimates were calculated using regions of interest. Residence times were computed and entered into the MIRDOSE3 computer software program to calculate estimated radiation absorbed dose to each organ. Initial analyses of estimated radiation absorbed dose were completed at the clinical site. An additional, centralized dosimetry analysis was performed subsequently to provide a consistent analysis of data collected from the seven clinical sites. In all patients with dosimetry data (n=56), normal organ and red marrow radiation absorbed doses were estimated to be well under the protocol-defined upper limit of 20 Gy and 3 Gy, respectively. Median estimated radiation absorbed dose was 3.4 Gy to liver (range 1.2-7.8 Gy), 2.6 Gy to lungs (range 0.72-4.4 Gy), and 0.38 Gy to kidneys (range 0.07-0.61 Gy). Median estimated tumor radiation absorbed dose was 17 Gy (range 5.8-67 Gy). No correlation was noted between hematologic toxicity and the following variables: red marrow radiation absorbed dose, blood T 1/2 , blood AUC

Radiation doses deriving from patients undergoing 111In-DTPA-d-Phe-1-octreotide scintigraphy

International Nuclear Information System (INIS)

Kurtaran, A.; Pfreitfellner, J.; Smith-Jones, P.; Schaffarich, P.; Niederle, B.; Raderer, M.; Virgolini, I.; Bergmann, H.; Havlik, E.

1997-01-01

The purpose of this study was to estimate the radiation doses to nursing staff, other patients, accompanying persons and family members deriving from patients undergoing 111 In-DTPA-d-Phe-1-octreotide ( 111 In-OCT) scintigraphy. Dose rates were measured from 16 patients who had received an intravenous injection of 140±40 MBq 111 In-OCT. The measurements were performed at three different distances (0.5, 1 and 2 m) at 10-20 min, 5-7 h and 24 h (and in some cases, up to 48 h) after administration of 111 In-OCT. The effective half-lives of the biexponential decrease of the dose rates were estimated to be 2.94±0.27 h (T 1 ) and 65.17±0.58 h (T 2 ). The calculated maximum dose to other persons in the waiting area was 27.2 μSv, to family members 61.5 μSv, to nursing staff in a ward 24.1 μSv and to neighbouring patients in the ward 69.5 μSv. Our results clearly demonstrate that the calculated maximum radiation exposure to accompanying persons, personnel, family members and other patients is well below the maximum annual dose limit for non-professionally exposed persons. (orig.)

Radiation Doses to Hanford Workers from Natural Potassium-40

Energy Technology Data Exchange (ETDEWEB)

Strom, Daniel J. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Lynch, Timothy P. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Weier, Dennis R. [Pacific Northwest National Lab. (PNNL), Richland, WA (United States)

2009-02-01

The chemical element potassium is an essential mineral in people and is subject to homeostatic regulation. Natural potassium comprises three isotopes, ³⁹K, ⁴⁰K, and ⁴¹K. Potassium-40 is radioactive, with a half life of 1.248 billion years. In most transitions, it emits a β particle with a maximum energy of 0.560 MeV, and sometimes a gamma photon of 1.461 MeV. Because it is ubiquitous, ⁴⁰K produces radiation dose to all human beings. This report contains the results of new measurements of ⁴⁰K in 248 adult females and 2,037 adult males performed at the Department of Energy Hanford Site in 2006 and 2007. Potassium concentrations diminish with age, are generally lower in women than in men, and decrease with body mass index (BMI). The average annual effective dose from ⁴⁰K in the body is 0.149 mSv y^-1 for men and 0.123 mSv y^-1 women respectively. Averaged over both men and women, the average effective dose per year is 0.136 mSv y^-1. Calculated effective doses range from 0.069 to 0.243 mSv y^-1 for adult males, and 0.067 to 0.203 mSv y^-1 for adult females, a roughly three-fold variation for each gender. The need for dosimetric phantoms with a greater variety of BMI values should be investigated. From our data, it cannot be determined whether the potassium concentration in muscle in people with large BMI values differs from that in people with small BMI values. Similarly, it would be important to know the potassium concentration in other soft tissues, since much of the radiation dose is due to beta radiation, in which the source and target tissues are the same. These uncertainties should be evaluated to determine their consequences for dosimetry.

Production and bromatologic composition of grass-mombaça (Panicum maximum Jacq., submitted to different sources and doses of acidity corrective / Produção e composição bromatológica da forragem do capim-mombaça (Panicum maximum Jacq., submetidos a diferentes fontes e doses de corretivo de acidez

Directory of Open Access Journals (Sweden)

Francisco Maximino Fernandes

2010-04-01

Full Text Available The experiment was carried in protected (greenhouse atmosphere, in University of Engineering, UNESP of Ilha Solteira-SP, with the objective of evaluating sources (limestone and calcium silicate slag and doses (0,0 – 0,5 – 1,0 – 1,5 – 2,0 times the recommended dose of corrective in the bromatologic composition, tillering and production of dry matter of the grass mombaça (Panicum maximum Jacq.. The lineation was completely randomized design, with four repetitions. It was evaluated the tiller number, the production of dry matter, the gross protein, neutral detergent fiber (NDF and acid detergent fiber (ADF. The corrective influenced the tillering in almost all of the countings. The limestone provided larger production of dry matter in the doses of 1,5 and 2,0 times the recommended dose. The bromatologic composition of the forage was not influenced by the corrective and doses.O experimento foi conduzido em ambiente protegido (estufa, na Faculdade de Engenharia, UNESP de Ilha Solteira, com o objetivo de avaliar fontes (calcário e escória silicatada e doses (0,0 – 0,5 – 1,0 – 1,5 – 2,0 vezes a dose recomendada de corretivos na composição bromatológica, perfilhamento e produção de matéria seca do capim-mombaça (Panicum maximum Jacq.. O delineamento experimental utilizado foi inteiramente casualizado, com quatro repetições. Avaliou-se o número de perfilhos, a produção de matéria seca e os teores de proteína bruta (PB, fibra em detergente neutro (FDN e fibra em detergente ácido (FDA. Os corretivos influenciaram o perfilhamento em quase todas as contagens. O calcário proporcionou maior produção de matéria seca nas doses de 1,5 e 2,0 vezes a dose recomendada. A composição bromatológica da forragem não foi influenciada pelos corretivos e doses utilizadas.

Reference beta radiations for calibrating dosemeters and dose ratemeters and for determining their response as a function of beta radiation energy. 1. ed.

International Nuclear Information System (INIS)

1984-01-01

This International Standard specifies the requirements for reference beta radiations produced by radionuclide sources to be used for the calibration of protection level dosemeters and dose ratemeters, and for the determination of their response as a function of beta energy. It gives the characteristics of radionuclides which have been used to produce reference beta radiations, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta energy and the absorbed dose rate at a depth of 7 mg·cm -2 in a semi-infinite tissue-equivalent medium. The energy range involved lies between 66 keV and 3.6 MeV and the absorbed dose rates are in the range from about 10 μGy·h -1 (1 mrad·h -1 ) to at least 10 Gy·h -1 (10 3 rad·h -1 ). This International Standard proposes two series of beta reference radiations from which the radiation necessary for determining the characteristics (calibration and energy response) of an instrument shall be selected. Series 1 reference radiations are produced by radionuclide sources used with beam flattening filters designed to give uniform dose rates over a large area at a specific distance. The proposed sources of 90 Sr+ 90 Y, 204 TI and 147 Pm produce maximum dose rates of approximately 5mGy·h -1 (0.5 rad·h -1 ). Series 2 reference radiations are produced without the use of beam flattening filters which allows a range of source-to-calibration plane distances to be used. Close to the sources only relatively small areas of uniform dose rate are produced but this Series has the advantage of extending the energy and dose rate ranges beyond those of Series 1. The radionuclides used are those of Series 1 with the addition of the radionuclides 14 C and 106 Ru+ 106 Rh; these sources produce dose rates of up to 10 Gy·h -1 (10 3 rad·h -1 )

Estimated radiological doses to the maximumly exposed individual and downstream populations from releases of tritium, strontium-90, ruthenium-106, and cesium-137 from White Oak Dam

International Nuclear Information System (INIS)

Little, C.A.; Cotter, S.J.

1980-01-01

Concentrations of tritium, 90 Sr, 106 Ru, and 137 Cs in the Clinch River for 1978 were estimated by using the known 1978 releases of these nuclides from the White Oak Dam and diluting them by the integrated annual flow rate of the Clinch River. Estimates of 50-year dose commitment to a maximumly exposed individual were calculated for both aquatic and terestrial pathways of exposure. The maximumly exposed individual was assumed to reside at the mouth of White Oak Creek where it enters the Clinch River and obtain all foodstuffs and drinking water at that location. The estimated total-body dose from all pathways to the maximumly exposed individual as a result of 1978 releases was less than 1% of the dose expected from natural background. Using appropriate concentrations of to subject radionuclides diluted downstream, the doses to populations residing at Harriman, Kingston, Rockwood, Spring City, Soddy-Daisy, and Chattanooga were calculated for aquatic exposure pathways. The total-body dose estimated for aquatic pathways for the six cities was about 0.0002 times the expected dose from natural background. For the pathways considered in this report, the nuclide which contributed the largest fraction of dose was 90 Sr. The largest dose delivered by 90 Sr was to the bone of the subject individual or community

Galvanomagnetic effects in n-Hg1-x-yCdxMnyTe and n-Hg1-yMnyTe crystals with εg>0

International Nuclear Information System (INIS)

Gluzman, N.G.; Lerinman, N.K.; Sabirzyanova, L.D.; Bodnaruk, O.A.; Gorbatyuk, I.N.; Rarenko, I.M.

1989-01-01

Longitudinal ρ zz and transverse ρ xx magnetoresistances and R hall coefficient in H magnetic fields up to 100 kE at 1.2≤T≤300 K are measured at n-Hg 1-x-y Cd x Mn y Te and n-Hg 1-y Mn y Te crystals (100≤ε g ≤260 meV) with N D -N A ≅10 15 cm -3 . Shubnikov-de-Gaas (SG) oscillations were observed at all specimens. Maxima positions of SG oscillations depend on T. For Hg 1-y Mn y Te crystals the position of zero maximum is shifted to large H direction, it is caused by abrupt (as compared to zone one) reduction of summary g-factor. Magnetophonon oscillations are determined at longitudinal magnetoresistance. Transition from metal conductivity to activation one occuring in magnetic field is studied; activation energy in nonmetallic range is determined. Some peculiarities of galvanomagnetic phenomena in n-Hg 1-y Mn y Te specimens, which indicate presence of p-type inclusions in n-type crystals, are determined

An overview of the report: Correlation between carcinogenic potency and the maximum tolerated dose: Implications for risk assessment

International Nuclear Information System (INIS)

Krewski, D.; Gaylor, D.W.; Soms, A.P.; Szyszkowicz, M.

1993-01-01

Current practice in carcinogen bioassay calls for exposure of experimental animals at doses up to and including the maximum tolerated dose (MTD). Such studies have been used to compute measures of carcinogenic potency such as the TD 50 as well as unit risk factors such as q 1 for predicting low-dose risks. Recent studies have indicated that these measures of carcinogenic potency are highly correlated with the MTD. Carcinogenic potency has also been shown to be correlated with indicators of mutagenicity and toxicity. Correlation of the MTDs for rats and mice implies a corresponding correlation in TD 50 values for these two species. The implications of these results for cancer risk assessment are examined in light of the large variation in potency among chemicals known to induce tumors in rodents. 119 refs., 2 figs., 4 tabs

Natural background radiation and population dose distribution in India

International Nuclear Information System (INIS)

Nambi, K.S.V.; Bapat, V.N.; David, M.; Sundaram, V.K.; Sunta, C.M.; Soman, S.D.

1986-01-01

A country-wide survey of the outdoor natural background gamma radiation levels has been made using mailed thermoluminescent dosimeters (TLDs). The salient features of the results are: (1) The air-kerma levels and the population doses in various states follow log-normal and normal distributions respectively. (2) The national average value for the air dose (air-kerma) is 775 ± 370 (1σ)μGy/y. (3) The lowest air-kerma recorded is 0.23 mGy/y at Minicoy (Laccadive Islands) and the highest is 26.73 mGy/y at Chavra (monazite areas, Kerala). (4) There are significant temporal variation s (even as high as ± 40 per cent) of the background radiation level at many locations and at least in 10 locations where radon/thoron measurements are available, these could be associated with the seasonal variations in radon/thoron levels. (5) The mail control TLDs indicate a country-wide average value of 785 ± 225 μGy/y for the air-kerma which can be considered to provide a truly national average value for the natural background radiation level in India. (6) The mean natural radiation per caput for the country works out to be 690 ± 200 (1σ) Sv/y. (7) The natural radiation per caput seems to be maximum for Andhra Pradesh (1065 ± 325 μSv/y) and minimum for Maharashtra (370 ± 80 μSv/y). (8) The population dose from the external natural background radiation is estimated to be half a million person-Sievert. (9) Assuming 1 CRP risk factor, it can be estimated that just one out of the 43 cancer deaths occurring on an average per 100,000 population in India, can be attributed to the external natural background radiation. (author). 18 refs., 13 tabs., 9 figs

Validation of calculated tissue maximum ratio obtained from measured percentage depth dose (PPD) data for high energy photon beam ( 6 MV and 15 MV)

International Nuclear Information System (INIS)

Osei, J.E.

2014-07-01

During external beam radiotherapy treatments, high doses are delivered to the cancerous cell. Accuracy and precision of dose delivery are primary requirements for effective and efficiency in treatment. This leads to the consideration of treatment parameters such as percentage depth dose (PDD), tissue air ratio (TAR) and tissue phantom ratio (TPR), which show the dose distribution in the patient. Nevertheless, tissue air ratio (TAR) for treatment time calculation, calls for the need to measure in-air-dose rate. For lower energies, measurement is not a problem but for higher energies, in-air measurement is not attainable due to the large build-up material required for the measurement. Tissue maximum ratio (TMR) is the quantity required to replace tissue air ratio (TAR) for high energy photon beam. It is known that tissue maximum ratio (TMR) is an important dosimetric function in radiotherapy treatment. As the calculation methods used to determine tissue maximum ratio (TMR) from percentage depth dose (PDD) were derived by considering the differences between TMR and PDD such as geometry and field size, where phantom scatter or peak scatter factors are used to correct dosimetric variation due to field size difference. The purpose of this study is to examine the accuracy of calculated tissue maximum ratio (TMR) data with measured TMR values for 6 MV and 15 MV photon beam at Sweden Ghana Medical Centre. With the help of the Blue motorize water phantom and the Omni pro-Accept software, Pdd values from which TMRs are calculated were measured at 100 cm source-to-surface distance (SSD) for various square field sizes from 5x5 cm to 40x40 cm and depth of 1.5 cm to 25 cm for 6 MV and 15 MV x-ray beam. With the same field sizes, depths and energies, the TMR values were measured. The validity of the calculated data was determined by making a comparison with values measured experimentally at some selected field sizes and depths. The results show that; the reference depth of maximum

Benefits of the maximum tolerated dose (MTD) and maximum tolerated concentration (MTC) concept in aquatic toxicology

International Nuclear Information System (INIS)

Hutchinson, Thomas H.; Boegi, Christian; Winter, Matthew J.; Owens, J. Willie

2009-01-01

There is increasing recognition of the need to identify specific sublethal effects of chemicals, such as reproductive toxicity, and specific modes of actions of the chemicals, such as interference with the endocrine system. To achieve these aims requires criteria which provide a basis to interpret study findings so as to separate these specific toxicities and modes of action from not only acute lethality per se but also from severe inanition and malaise that non-specifically compromise reproductive capacity and the response of endocrine endpoints. Mammalian toxicologists have recognized that very high dose levels are sometimes required to elicit both specific adverse effects and present the potential of non-specific 'systemic toxicity'. Mammalian toxicologists have developed the concept of a maximum tolerated dose (MTD) beyond which a specific toxicity or action cannot be attributed to a test substance due to the compromised state of the organism. Ecotoxicologists are now confronted by a similar challenge and must develop an analogous concept of a MTD and the respective criteria. As examples of this conundrum, we note recent developments in efforts to validate protocols for fish reproductive toxicity and endocrine screens (e.g. some chemicals originally selected as 'negatives' elicited decreases in fecundity or changes in endpoints intended to be biomarkers for endocrine modes of action). Unless analogous criteria can be developed, the potentially confounding effects of systemic toxicity may then undermine the reliable assessment of specific reproductive effects or biomarkers such as vitellogenin or spiggin. The same issue confronts other areas of aquatic toxicology (e.g., genotoxicity) and the use of aquatic animals for preclinical assessments of drugs (e.g., use of zebrafish for drug safety assessment). We propose that there are benefits to adopting the concept of an MTD for toxicology and pharmacology studies using fish and other aquatic organisms and the

Determinación de compuestos hidrocarbonados en la pared celular de P. maximum y L. leucocephala en silvopastoreo Determination of hydrocarbonated compounds in the cell wall from P. maximum and L. leucocephala under silvopastoral system conditions

Directory of Open Access Journals (Sweden)

Tania Sánchez

2009-09-01

Full Text Available Con el objetivo de determinar la concentración de n-alcanos y alcoholes de cadena larga en la pared celular de Panicum maximum cv. Likoni y Leucaena leucocephala cv. Cunningham, se realizó un estudio en una asociación de gramíneas mejoradas y leucaena de 10 años de establecida, la cual ocupa un área de 1,6 ha. Se seleccionaron dichas especies por ser las más representativas en la composición florística. Las muestras se colectaron de enero a diciembre del 2005 y se secaron. La concentración de n-alcanos de cadena impar fue de 167,97 y 222,96 mg/kg de MS y 134,11 y 137,27 mg/kg de MS para guinea y leucaena, en el período poco lluvioso y en el lluvioso, respectivamente. A su vez la concentración de alcoholes de cadena par para la leucaena presentó un valor mayor(2 754,60 y 3 830,18 mg/kg de MS para el período poco lluvioso y lluvioso, respectivamente, que en la guinea (2 571,73-3 679,65 mg/kg de MS para cada período, respectivamente. Se concluye que la concentración de n-alcanos de cadena larga impar fue baja para P. maximum y L. leucocephala en ambos períodos del año; sin embargo, presentaron concentraciones elevadas de alcoholes de cadena larga par, que pudieran ser utilizados como marcadores naturales en las dos especies.With the objective of determining the concentration of n-alkanes and long-chain alcohols in the cell wall of Panicum maximum cv. Likoni and Leucaena leucocephala cv. Cunningham, a study was conducted in an association of improved grasses and leucaena ten years after being established, which occupies an area of 1,6 ha. Such species were selected for being the most representative ones in the floristic composition. The samples were collected from January to December, 2005 and were dried. The concentration of odd-chain n-alkanes was 167,97 and 222,96 mg/kg DM and 134,11 and 137,27 mg/kg DM for Guinea grass and leucaena in the dry and rainy season, respectively. In turn, the concentration of even-chain alcohols for

SU-E-T-346: Effect of Jaw Position On Dose to Critical Structures in 3-D Conformal Radiotherapy Treatment of Pancreatic Cancer

Energy Technology Data Exchange (ETDEWEB)

Paudel, N; Han, E; Liang, X; Morrill, S; Zhang, X; Hardee, M; Penagaricano, J; Ratanatharathorn, V [Vaneerat, University of Arkansas for Medical Sciences, Little Rock, AR (United States)

2015-06-15

Purpose: Three-dimensional conformal therapy remains a valid and widely used modality for pancreatic radiotherapy treatment. It usually meets dose constraints on critical structures. However, careful positioning of collimation jaws can reduce dose to the critical structures. Here we investigate the dosimetric effect of jaw position in MLC-based 3-D conformal treatment planning on critical structures. Methods: We retrospectively selected seven pancreatic cancer patients treated with 3-D conformal radiotherapy. We started with treatment plans (Varian Truebeam LINAC, Eclipse TPS, AAA, 18MV) having both x and y jaws aligned with the farthest extent of the block outline (8mm around PTV). Then we subsequently moved either both x-jaws or all x and y jaws outwards upto 3 cm in 1 cm increments and investigated their effect on average and maximum dose to neighboring critical structures keeping the same coverage to treatment volume. Results: Lateral displacement of both x-jaws by 1cm each increased kidney and spleen mean dose by as much as 1.7% and 1.3% respectively and superior inferior displacement increased liver, right kidney, stomach and spleen dose by as much as 2.1%, 2%, 5.2% and 1.6% respectively. Displacement of all x and y-jaws away by 1cm increased the mean dose to liver, right kidney, left kidney, bowels, cord, stomach and spleen by as much as 4.9%, 5.9%, 2.1%, 2.8%, 7.4%, 10.4% and 4.2% respectively. Percentage increase in mean dose due to 2 and 3cm jaw displacement increased almost linearly with the displaced distance. Changes in maximum dose were much smaller (mostly negligible) than the changes in mean dose. Conclusion: Collimation jaw position affects dose mostly to critical structures adjacent to it. Though treatment plans with MLCs conforming the block margin usually meet dose constraints to critical structures, keeping jaws all the way in, to the edge of the block reduces dose to the critical structures during radiation treatment.

Testicular dose and associated risk from inverted-Y field irradiation in patients with Hodgkin's disease.

Science.gov (United States)

Mazonakis, Michalis; Kokona, Georgiana; Damilakis, John; Varveris, Haris; Gourtsoyiannis, Nicholas

This study aims to estimate testicular dose and the associated risks for infertility and hereditary effects from inverted-Y field irradiation Radiotherapy was simulated on a humanoid phantom using a 6 MV photon beam. Testicular dose was measured for various field sizes and tissue thicknesses along beam axis using an ionization chamber. Gonadal dose was reduced by placing lead cups around the testes supplemented by a field edge block. For a tumor dose of 40 Gy, testicular dose was 0.56-6.52 Gy depending upon the field size and the distance from the inferior field edge. The corresponding dose to shielded testes was 0.12-1.96 Gy. The increase of tissue thickness in reased the testicular dose up to 40%. An excess risk of hereditary disorders of (7-391) per 10000 births was calculated. The treatment parameters, the presence of gonad shield and the somatometric characteristics determine whether testicular dose can exceed 1 Gy which allows a complete recovery of spermatogenesis.

Radiation dose from cigarette tobacco

International Nuclear Information System (INIS)

Papastefanou, Constantin

2008-01-01

The radioactivity in tobacco leaves collected from 15 different regions of Greece before cigarette production was studied in order to estimate the effective dose from cigarette tobacco due to the naturally occurring primordial radionuclides, such as 226 Ra and 210 Pb of the uranium series and 228 Ra of the thorium series and or man-made produced radionuclides, such as 137 Cs of Chernobyl origin. Gamma-ray spectrometry was applied using Ge planar and coaxial type detectors of high resolution and high efficiency. It was concluded that the annual effective dose due to inhalation for adults (smokers) for 226 Ra varied from 42.5 to 178.6 μSv y -1 (average 79.7 μSv y -1 ), while for 228 Ra from 19.3 to 116.0 μSv y -1 (average 67.1 μSv y -1 ) and for 210 Pb from 47.0 to 134.9 μSv y -1 (average 104.7 μSv y -1 ), that is the same order of magnitude for each radionuclide. The sum of the effective dose of the three natural radionuclides varied from 151.9 to 401.3 μSv y -1 (average 251.5 μSv y -1 ). The annual effective dose from 137 Cs of Chernobyl origin was three orders of magnitude lower as it varied from 70.4 to 410.4 μSv y -1 (average 199.3 μSv y -1 ). (author)

Measurement of dose speed absorbed in depth imparted by sources external secondary patterns of beta radiation. Part 1 Measurement of dose speed absorbed in the surface of soft fabric for isotopes of 90Sr/90Y, 147Pm and 204TI

International Nuclear Information System (INIS)

Alvarez R, J.T.

1993-01-01

The dose speed was measured absorbed for depth zero, (superficial) in soft equivalent fabric, for the secondary pattern s four sources of beta radiation, (Nr. 86): 90 Sr/ 90 Y, (1850 MBq and 74 MBq respectively); 147 Pm, (518 MBq) and 204 TI, (18.5 MBq). The measurement is carried out to different distances of source-detecting separation, (11.0, 30.0 and 50.0 cm for the source of 1850 MBq, 30.0 cm for that of 74 MBq; 11.00 cm for the source of 147 Pmand to contact for all the sources); maintaining the radiation sheaf aligned the one axis of symmetry of the detector, (α 0 degrees). The detector employed was a extrapolation chambers of variable electrodes and electrode fixed collector, (30 mm of diameter). In accordance with the principle of Bragg-Gray the volume of the chambers is varied and they register the variations of the current of collected ionization, correcting until for a maximum of thirteen correction factors that take into account the deviation to the suppositions that it establishes this principle. The certain values of the speed of superficial absorbed dose are in the following intervals: 90 Sr/ 90 Y, (1850 MBq, 0.0, 11.0, 30.0 and 50.0 cm): 43.164 mGy S-t, 0.544 mGy s-1 ,0.075 mGy s -1 and 0.027 mGy s -1 , respectively, with a Global Analysis of the order of 1.17%, 1.17%, 1.14% and 1.66%, K J; 90 Sr / 90 Y, (74 MBq, 0.0 and 30 cm): 1.536 mGy s -1 and 0.002 mGy s -1 , with Global Analysis of 1.19.0% and 5.22%, (K = 1) respectively, for the 147 Pm, (0.0 and 11.0 in the interval of: 0.36 μGy s -1 and 0.43 μGy s -1 , with one Global Analysis of 1 .42% and 4.28%, (K = 1), respectively; and finally for the 204 TI, (0.0 cm) in the interval of 0.10 μGy s -1 with a Global Analysis of 1.27%. He calculates of the Global Analysis one carries out of agreement with those recommendations of the BIPM. In all the cases of source-detecting arrangement with separations different from zero, models of simple lineal regression were used. However for the case of the

Enhanced Y1-receptor-mediated vasoconstrictive action of neuropeptide Y (NPY) in superior mesenteric arteries in portal hypertension.

Science.gov (United States)

Wiest, Reiner; Jurzik, Lars; Moleda, Lukas; Froh, Matthias; Schnabl, Bernd; von Hörsten, Stephan; Schölmerich, Juergen; Straub, Rainer H

2006-03-01

Vascular hyporeactivity to catecholamines contributes to arterial vasodilation and hemodynamic dysregulation in portal hypertension. Neuropeptide Y (NPY) is a sympathetic neurotransmitter facilitating adrenergic vasoconstriction via Y1-receptors on the vascular smooth muscle. Therefore, we investigated its role for vascular reactivity in the superior mesenteric artery (SMA) of portal vein ligated (PVL) and sham operated rats. In vitro perfused SMA vascular beds of rats were tested for the cumulative dose-response to NPY dependent on the presence and level of alpha1-adrenergic vascular tone (methoxamine MT: 0.3-10 microM). Moreover, the effect of NPY (50 nM) on vascular responsiveness to alpha1-adrenergic stimulation (MT: 0.3-300 microM) was evaluated. Y1-receptor function was tested by Y1-selective inhibition using BIBP-3226 (1 microM). NPY dose-dependently and endothelium-independently enhanced MT-pre-constriction in SMA. This potentiation was increasingly effective with increasing adrenergic pre-stimulation and being more pronounced in PVL rats as compared to sham rats at high MT concentrations. NPY enhanced vascular contractility only in PVL rats correcting the adrenergic vascular hyporeactivity. Y1-receptor inhibition completely abolished NPY-evoked vasoconstrictive effects. NPY endothelium-independently potentiates adrenergic vasoconstriction via Y1-receptors being more pronounced in portal hypertension improving mesenteric vascular contractility and thereby correcting the splanchnic vascular hyporeactivity. This makes NPY a superior vasoconstrictor counterbalancing arterial vasodilation in portal hypertension.

A dose assessment for a U.S. nuclear test site -- Bikini Atoll

International Nuclear Information System (INIS)

Robison, W.L.; Bogen, K.T.; Conrado, C.L.

1993-07-01

On March 1, 1954, a nuclear weapon test, code-named BRAVO, conducted at Bikini Atoll in the northern Marshall Islands contaminated the major residence island. Here the authors provide a radiological dose assessment for the main residence island, Bikini, using extensive radionuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island. The unique composition of coral soil greatly alters the relative contribution of cesium-137 and strontium-90 to the total estimated dose relative to expectations based on North American and European soils. Cesium-137 produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The estimated maximum annual effective dose is 4.4 mSv y -1 when imported foods, which are now an established part of the diet, are available. The 30-, 50-, and 70-y integral effective doses are 10 cSv, 14 cSv, and 16 cSv, respectively. An analysis of interindividual variability in 0- to 30-y expected integral dose indicates that 95% of Bikini residents would have expected doses within a factor of 3.4 above and 4.8 below the population-average value. A corresponding uncertainty analysis showed that after about 5 y of residence, the 95% confidence limits on population-average dose would be ±35% of its expected value. The authors have evaluated various countermeasures to reduce 137 Cs in food crops. Treatment with potassium reduces the uptake of 137 Cs into food crops, and therefore the ingestion dose, to less than 10% of pretreatment levels and has essentially no negative environmental consequences

SU-G-201-12: Investigation of Beta-Emitter 90Sr-90Y Dose Distribution Using Gafchromic EBT3 Film for Application On Conformal Skin Brachytherapy Device

International Nuclear Information System (INIS)

Ferreira, C; Johnson, D; Ahmad, S; Rasmussen, K; Jung, J

2016-01-01

Purpose: To investigate 90 Sr- 90 Y as a high dose rate (HDR) source for application in a conformal skin brachytherapy (CSBT) device. The CSBT device has been previously developed to provide patient specific treatment for small inoperable lesions and irregular surfaces. Methods: A popular beta emitter, 90 Sr- 90 Y was tested for feasibility in a CSBT device. A 1 cm diameter plaque was used to deliver dose to a solid water phantom containing EBT3 Gafchromic films arranged at the surface and perpendicular to it. Additionally, a 1 cm diameter 6 MeV electron beam was used to irradiate EBT3 film at 100 cm SSD with a 0.5 cm bolus. Films were digitized with an Epson Expression 10000 XL scanner and calibrated with a 6 MeV electron specific dose curve. Normalized percent depth doses (PDD) and dose profiles for both techniques were analyzed using ImageJ. Results: Dose distributions achieved with the 90 Sr- 90 Y sources were compared with those of external electron beam radiation therapy (EBRT). Penumbra (20%- 80%) for EBRT and 90Sr-90Y were 4.3 mm and 1.6 mm, respectively. PDD values of 50% (normalized to 2 mm) were 10.1 mm and 2.8 mm for electron and 90 Sr- 90 Y, respectively. Flatness (80% of the central beam profile) was 14.1% at a 5 mm depth for EBRT and 4.0% at surface for the 90 Sr- 90 Y. Conclusion: As expected, the PDDs of 90 Sr- 90 Y in water are shallower than that of external electron beams for the same field size. 90 Sr- 90 Y can be used in CSBT to provide patient specific treatment where shallower depth doses than that provided by electron external beams may be required: e.g. eyelids, nose, lips, ears, etc. The customizability of EBRT could be replicated by using multiple adjacent 90 Sr- 90 Y plaque placements.

SU-G-201-12: Investigation of Beta-Emitter 90Sr-90Y Dose Distribution Using Gafchromic EBT3 Film for Application On Conformal Skin Brachytherapy Device

Energy Technology Data Exchange (ETDEWEB)

Ferreira, C; Johnson, D; Ahmad, S [University of Oklahoma Health Sciences Center, Oklahoma City, OK (United States); Rasmussen, K [University of Texas HSC SA, San Antonio, TX (United States); Jung, J [East Carolina University Greenville, NC (United States)

2016-06-15

Purpose: To investigate {sup 90}Sr-{sup 90}Y as a high dose rate (HDR) source for application in a conformal skin brachytherapy (CSBT) device. The CSBT device has been previously developed to provide patient specific treatment for small inoperable lesions and irregular surfaces. Methods: A popular beta emitter, {sup 90}Sr-{sup 90}Y was tested for feasibility in a CSBT device. A 1 cm diameter plaque was used to deliver dose to a solid water phantom containing EBT3 Gafchromic films arranged at the surface and perpendicular to it. Additionally, a 1 cm diameter 6 MeV electron beam was used to irradiate EBT3 film at 100 cm SSD with a 0.5 cm bolus. Films were digitized with an Epson Expression 10000 XL scanner and calibrated with a 6 MeV electron specific dose curve. Normalized percent depth doses (PDD) and dose profiles for both techniques were analyzed using ImageJ. Results: Dose distributions achieved with the {sup 90}Sr-{sup 90}Y sources were compared with those of external electron beam radiation therapy (EBRT). Penumbra (20%- 80%) for EBRT and 90Sr-90Y were 4.3 mm and 1.6 mm, respectively. PDD values of 50% (normalized to 2 mm) were 10.1 mm and 2.8 mm for electron and {sup 90}Sr-{sup 90}Y, respectively. Flatness (80% of the central beam profile) was 14.1% at a 5 mm depth for EBRT and 4.0% at surface for the {sup 90}Sr-{sup 90}Y. Conclusion: As expected, the PDDs of {sup 90}Sr-{sup 90}Y in water are shallower than that of external electron beams for the same field size. {sup 90}Sr-{sup 90}Y can be used in CSBT to provide patient specific treatment where shallower depth doses than that provided by electron external beams may be required: e.g. eyelids, nose, lips, ears, etc. The customizability of EBRT could be replicated by using multiple adjacent {sup 90}Sr-{sup 90}Y plaque placements.

Investigation of 1-cm dose equivalent for photons behind shielding materials

International Nuclear Information System (INIS)

Hirayama, Hideo; Tanaka, Shun-ichi

1991-03-01

The ambient dose equivalent at 1-cm depth, assumed equivalent to the 1-cm dose equivalent in practical dose estimations behind shielding slabs of water, concrete, iron or lead for normally incident photons having various energies was calculated by using conversion factors for a slab phantom. It was compared with the 1-cm depth dose calculated with the Monte Carlo code EGS4. It was concluded from this comparison that the ambient dose equivalent calculated by using the conversion factors for the ICRU sphere could be used for the evaluation of the 1-cm dose equivalent for the sphere phantom within 20% errors. Average and practical conversion factors are defined as the conversion factors from exposure to ambient dose equivalent in a finite slab or an infinite one, respectively. They were calculated with EGS4 and the discrete ordinates code PALLAS. The exposure calculated with simple estimation procedures such as point kernel methods can be easily converted to ambient dose equivalent by using these conversion factors. The maximum value between 1 and 30 mfp can be adopted as the conversion factor which depends only on material and incident photon energy. This gives the ambient dose equivalent on the safe side. 13 refs., 7 figs., 2 tabs

Control of Co content and SOFC cathode performance in Y1-ySr2+yCu3-xCoxO7+δ

Science.gov (United States)

Šimo, F.; Payne, J. L.; Demont, A.; Sayers, R.; Li, Ming; Collins, C. M.; Pitcher, M. J.; Claridge, J. B.; Rosseinsky, M. J.

2014-11-01

The electrochemical performance of the layered perovskite YSr2Cu3-xCoxO7+δ, a potential solid oxide fuel cell (SOFC) cathode, is improved by increasing the Co content from x = 1.00 to a maximum of x = 1.30. Single phase samples with x > 1.00 are obtained by tuning the Y/Sr ratio, yielding the composition Y1-ySr2+yCu3-xCoxO7+δ (where y ≤ 0.05). The high temperature structure of Y0.95Sr2.05Cu1.7Co1.3O7+δ at 740 °C is characterised by powder neutron diffraction and the potential of this Co-enriched material as a SOFC cathode is investigated by combining AC impedance spectroscopy, four-probe DC conductivity and powder XRD measurements to determine its electrochemical properties along with its thermal stability and compatibility with a range of commercially available electrolytes. The material is shown to be compatible with doped ceria electrolytes at 900 °C.

Doses to the hand during the administration of radiolabeled antibodies containing Y-90, Tc-99m, I-131, and Lu-177

Energy Technology Data Exchange (ETDEWEB)

Barber, D.E. [Minnesota Univ., Minneapolis, MN (United States). School of Public Health; Carsten, A.L.; Kaurin, D.G.L.; Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

1997-02-01

Exposure of the hands of medical personnel administering radiolabeled antibodies (RABs) was evaluated on the basis of (a) observing and photo-documenting administration techniques, and (b) experimental data on doses to thermoluminescent dosimeters (TLDs) on fingers of phantom hands holding syringes, and on syringes, with radionuclides in the syringes in each case. Actual exposure data for I-131 and Lu-177 were obtained in field studies. Variations in handling and administration techniques were identified. Dose rates measured using TLDs on the surface of loaded syringes were adjusted for differences in electronic stopping power, absorption coefficients, and attenuation between dosimeters and tissue to estimate dose-to-skin averaged over 1 cm{sup 2} at 7 mg cm{sup {minus}2} depth for Y-90, Tc-99m, I-131, and Lu-177. Dose rate coefficients to the skin, if in contact with the syringe wall, were 89, 1.9, 3.8, and 0.41 {micro}Sv s{sup {minus}1} per 37 MBq (1 mCi) for Y-90, Tc-99m, I-131, and Lu-177, respectively. For dose reduction, when using Y-90 the importance was clearly indicated of (a) avoiding direct contact with syringes containing RABs, if practical, and (b) using a beta-particle shield on the syringe. In using a syringe for injection, doses can best be approximated for the geometry studied by (a) wearing a finger dosimeter on the middle finger, toward the outside of the hand, on the hand operating the plunger, and (b) wearing finger dosimeters on the inner (palm) side of the finger on the hand that supports the syringe for energetic beta-particle emitters, such as Y-90 and Re-188.

Doses to the hand during the administration of radiolabeled antibodies containing Y-90, Tc-99m, I-131, and Lu-177

International Nuclear Information System (INIS)

Barber, D.E.

1997-02-01

Exposure of the hands of medical personnel administering radiolabeled antibodies (RABs) was evaluated on the basis of (a) observing and photo-documenting administration techniques, and (b) experimental data on doses to thermoluminescent dosimeters (TLDs) on fingers of phantom hands holding syringes, and on syringes, with radionuclides in the syringes in each case. Actual exposure data for I-131 and Lu-177 were obtained in field studies. Variations in handling and administration techniques were identified. Dose rates measured using TLDs on the surface of loaded syringes were adjusted for differences in electronic stopping power, absorption coefficients, and attenuation between dosimeters and tissue to estimate dose-to-skin averaged over 1 cm 2 at 7 mg cm -2 depth for Y-90, Tc-99m, I-131, and Lu-177. Dose rate coefficients to the skin, if in contact with the syringe wall, were 89, 1.9, 3.8, and 0.41 microSv s -1 per 37 MBq (1 mCi) for Y-90, Tc-99m, I-131, and Lu-177, respectively. For dose reduction, when using Y-90 the importance was clearly indicated of (a) avoiding direct contact with syringes containing RABs, if practical, and (b) using a beta-particle shield on the syringe. In using a syringe for injection, doses can best be approximated for the geometry studied by (a) wearing a finger dosimeter on the middle finger, toward the outside of the hand, on the hand operating the plunger, and (b) wearing finger dosimeters on the inner (palm) side of the finger on the hand that supports the syringe for energetic beta-particle emitters, such as Y-90 and Re-188

Annual absorbed dose rate at the surface of 38 hot and mineral springs in Iran

Energy Technology Data Exchange (ETDEWEB)

Bahreyni Toosi, M.; Orougi, M.H.; Sadeghzadeh, A.; Aghamir, A.; Jomehzadeh, A.; Zare, H. [Mashhad Univ. of Medical Sciences, Medical Physics Dep., Faculty of Medicine (Iran, Islamic Republic of)

2006-07-01

Full text of publication follows: Measurement of background radiation is very important from different points of view especially to human health. In some cases exposure rate near hot and mineral springs are higher than those of normal areas. The high background radiation of hot and mineral springs is primarily due to the presence of very high amounts of Ra 226 and its decay products. In this research, environmental gamma radiation of hot and mineral springs in Khorasan, Mazandaran and Sareeyn town in Ardabil province have been measured. Equipment used in this work included: a survey meter (R.D.S. -110), a tripod and an aluminium frame to hold the survey meter horizontally.R.D.S. -110 is a microprocessor controlled detector. This survey meter has been designed for monitoring X and rays and radiation. Measurements were carried out at one meter above water level in the vicinity of hot and mineral springs. Dose rates were recorded for one hour. The average of all recorded dose rates over one hour period was taken as the exposure rate for each station. The results indicate that in Khorasan province the highest and lowest annual absorbed dose rates were equal to 10.80 mSv/y at Shanigarmab and 0.52 mSv/y at Nasradin source respectively. In Mazandaran province maximum and minimum exposure rates equal to 54.4 and 0.53 mSv/y were obtained at the surface of Talleshmahalleh and Ghormerz sources. Exposure rates at the vicinity of Sarein sources were not very different and ranged from 1.39 to 1.59 mSv/y. The results indicate that in Khorasan province Shahingarmab hot spring has the highest annual absorbed dose rate (10.80 mSv/y) and Nasraddin in Sarbisheh has the lowest level of radiation (0.62 mSv/y). In Mazandaran province Taleshmahalleh hot mineral spring has the highest annual absorbed dose rate (54.41 mSv/y) and Ghormerz mineral spring has the lowest radiation level (0.53 mSv/y). Also in Sareeyn (in Ardabil province) Abechashm source has the highest annual absorbed dose

3D inpatient dose reconstruction from the PET-CT imaging of 90Y microspheres for metastatic cancer to the liver: feasibility study.

Science.gov (United States)

Fourkal, E; Veltchev, I; Lin, M; Koren, S; Meyer, J; Doss, M; Yu, J Q

2013-08-01

The introduction of radioembolization with microspheres represents a significant step forward in the treatment of patients with metastatic disease to the liver. This technique uses semiempirical formulae based on body surface area or liver and target volumes to calculate the required total activity for a given patient. However, this treatment modality lacks extremely important information, which is the three-dimensional (3D) dose delivered by microspheres to different organs after their administration. The absence of this information dramatically limits the clinical efficacy of this modality, specifically the predictive power of the treatment. Therefore, the aim of this study is to develop a 3D dose calculation technique that is based on the PET imaging of the infused microspheres. The Fluka Monte Carlo code was used to calculate the voxel dose kernel for 90Y source with voxel size equal to that of the PET scan. The measured PET activity distribution was converted to total activity distribution for the subsequent convolution with the voxel dose kernel to obtain the 3D dose distribution. In addition, dose-volume histograms were generated to analyze the dose to the tumor and critical structures. The 3D inpatient dose distribution can be reconstructed from the PET data of a patient scanned after the infusion of microspheres. A total of seven patients have been analyzed so far using the proposed reconstruction method. Four patients underwent treatment with SIR-Spheres for liver metastases from colorectal cancer and three patients were treated with Therasphere for hepatocellular cancer. A total of 14 target tumors were contoured on post-treatment PET-CT scans for dosimetric evaluation. Mean prescription activity was 1.7 GBq (range: 0.58-3.8 GBq). The resulting mean maximum measured dose to targets was 167 Gy (range: 71-311 Gy). Mean minimum dose to 70% of target (D70) was 68 Gy (range: 25-155 Gy). Mean minimum dose to 90% of target (D90) was 53 Gy (range: 13-125 Gy). A

The consequences of a reduction in the administratively applied maximum annual dose equivalent level for an individual in a group of occupationally exposed workers

International Nuclear Information System (INIS)

Harrison, N.T.

1980-02-01

An analysis is described for predicting the consequences of a reduction in the administratively applied maximum dose equivalent level to individuals in a group of workers occupationally exposed to ionising radiations, for the situation in which no changes are made to the working environment. This limitation of the maximum individual dose equivalent is accommodated by allowing the number of individuals in the working group to increase. The derivation of the analysis is given, together with worked examples, which highlight the important assumptions that have been made and the conclusions that can be drawn. The results are obtained in the form of the capacity of the particular working environment to accommodate the limitation of the maximum individual dose equivalent, the increase in the number of workers required to carry out the productive work and any consequent increase in the occupational collective dose equivalent. (author)

86Y-DOTA0-d-Phe1-Tyr3-octreotide (SMT487) - a phase 1 clinical study: pharmacokinetics, biodistribution and renal protective effect of different regimens of amino acid co-infusion

International Nuclear Information System (INIS)

Jamar, Francois; Barone, Raffaella; Mathieu, Isabelle; Walrand, Stephan; Labar, Daniel; Carlier, Pascal; De Camps, Joelle; Pauwels, Stanislas; Schran, Horst; Chen, TianLing; Smith, M.Charles; Bouterfa, Hakim; Valkema, Roelf; Krenning, Eric P.; Kvols, Larry K.

2003-01-01

The pharmacokinetics and dosimetry of 86 Y-DOTA 0 -d-Phe 1 -Tyr 3 -octreotide ( 86 Y-SMT487) were evaluated in a phase I positron emission tomography (PET) study of 24 patients with somatostatin receptor-positive neuroendocrine tumours. The effect of amino acid (AA) co-infusion on renal and tumour uptake was assessed in a cross-over randomised setting. Five regimens were tested: no infusion, 4-h infusion of 120 g mixed AA (26.4 g l-lysine + l-arginine), 4 h l-lysine (50 g), 10 h 240 g mixed AA (52.8 g l-lysine + l-arginine) and 4 h Lys-Arg (25 g each). Comparisons were performed on an intra-patient basis. Infusions of AA started 0.5 h prior to injection of 86 Y-SMT487 and PET scans were obtained at 4, 24 and 48 h p.i. Absorbed doses to tissues were computed using the MIRD3 method. 86 Y-SMT487 displayed rapid plasma clearance and exclusive renal excretion; uptake was noted in kidneys, tumours, spleen and, to a lesser extent, liver. The 4-h mixed AA co-infusion significantly (P 86 Y-SMT487 renal uptake by a mean of 21%. This protective effect was significant on the dosimetry data (3.3±1.3 vs 4.4±1.0 mGy/MBq; P 90 Y-SMT487 (maximum allowed dose: MAD) that would result in a 23-Gy cut-off dose to kidneys was calculated for each study: MAD was higher with mixed AA co-infusion by a mean of 46% (10-114%, P<0.05 vs no infusion). In comparison with 4 h mixed AA, the MAD was higher by a mean of 23% (9-37%; P<0.05) with prolonged infusion and by a mean of 16% (2-28%; P<0.05) with Lys-Arg. We conclude that infusion of large amounts of AA reduces renal exposure during peptide-based radiotherapy and allows higher absorbed doses to tumours. The prolongation of the infusion from 4 to 10 h further enhances the protective effect on the kidneys. (orig.)

Comparison of measured and estimated maximum skin doses during CT fluoroscopy lung biopsies

Energy Technology Data Exchange (ETDEWEB)

Zanca, F., E-mail: Federica.Zanca@med.kuleuven.be [Department of Radiology, Leuven University Center of Medical Physics in Radiology, UZ Leuven, Herestraat 49, 3000 Leuven, Belgium and Imaging and Pathology Department, UZ Leuven, Herestraat 49, Box 7003 3000 Leuven (Belgium); Jacobs, A. [Department of Radiology, Leuven University Center of Medical Physics in Radiology, UZ Leuven, Herestraat 49, 3000 Leuven (Belgium); Crijns, W. [Department of Radiotherapy, UZ Leuven, Herestraat 49, 3000 Leuven (Belgium); De Wever, W. [Imaging and Pathology Department, UZ Leuven, Herestraat 49, Box 7003 3000 Leuven, Belgium and Department of Radiology, UZ Leuven, Herestraat 49, 3000 Leuven (Belgium)

2014-07-15

Purpose: To measure patient-specific maximum skin dose (MSD) associated with CT fluoroscopy (CTF) lung biopsies and to compare measured MSD with the MSD estimated from phantom measurements, as well as with the CTDIvol of patient examinations. Methods: Data from 50 patients with lung lesions who underwent a CT fluoroscopy-guided biopsy were collected. The CT protocol consisted of a low-kilovoltage (80 kV) protocol used in combination with an algorithm for dose reduction to the radiology staff during the interventional procedure, HandCare (HC). MSD was assessed during each intervention using EBT2 gafchromic films positioned on patient skin. Lesion size, position, total fluoroscopy time, and patient-effective diameter were registered for each patient. Dose rates were also estimated at the surface of a normal-size anthropomorphic thorax phantom using a 10 cm pencil ionization chamber placed at every 30°, for a full rotation, with and without HC. Measured MSD was compared with MSD values estimated from the phantom measurements and with the cumulative CTDIvol of the procedure. Results: The median measured MSD was 141 mGy (range 38–410 mGy) while the median cumulative CTDIvol was 72 mGy (range 24–262 mGy). The ratio between the MSD estimated from phantom measurements and the measured MSD was 0.87 (range 0.12–4.1) on average. In 72% of cases the estimated MSD underestimated the measured MSD, while in 28% of the cases it overestimated it. The same trend was observed for the ratio of cumulative CTDIvol and measured MSD. No trend was observed as a function of patient size. Conclusions: On average, estimated MSD from dose rate measurements on phantom as well as from CTDIvol of patient examinations underestimates the measured value of MSD. This can be attributed to deviations of the patient's body habitus from the standard phantom size and to patient positioning in the gantry during the procedure.

Comparison of measured and estimated maximum skin doses during CT fluoroscopy lung biopsies

International Nuclear Information System (INIS)

Zanca, F.; Jacobs, A.; Crijns, W.; De Wever, W.

2014-01-01

Purpose: To measure patient-specific maximum skin dose (MSD) associated with CT fluoroscopy (CTF) lung biopsies and to compare measured MSD with the MSD estimated from phantom measurements, as well as with the CTDIvol of patient examinations. Methods: Data from 50 patients with lung lesions who underwent a CT fluoroscopy-guided biopsy were collected. The CT protocol consisted of a low-kilovoltage (80 kV) protocol used in combination with an algorithm for dose reduction to the radiology staff during the interventional procedure, HandCare (HC). MSD was assessed during each intervention using EBT2 gafchromic films positioned on patient skin. Lesion size, position, total fluoroscopy time, and patient-effective diameter were registered for each patient. Dose rates were also estimated at the surface of a normal-size anthropomorphic thorax phantom using a 10 cm pencil ionization chamber placed at every 30°, for a full rotation, with and without HC. Measured MSD was compared with MSD values estimated from the phantom measurements and with the cumulative CTDIvol of the procedure. Results: The median measured MSD was 141 mGy (range 38–410 mGy) while the median cumulative CTDIvol was 72 mGy (range 24–262 mGy). The ratio between the MSD estimated from phantom measurements and the measured MSD was 0.87 (range 0.12–4.1) on average. In 72% of cases the estimated MSD underestimated the measured MSD, while in 28% of the cases it overestimated it. The same trend was observed for the ratio of cumulative CTDIvol and measured MSD. No trend was observed as a function of patient size. Conclusions: On average, estimated MSD from dose rate measurements on phantom as well as from CTDIvol of patient examinations underestimates the measured value of MSD. This can be attributed to deviations of the patient's body habitus from the standard phantom size and to patient positioning in the gantry during the procedure

A formalism for independent checking of Gamma Knife dose calculations

International Nuclear Information System (INIS)

Tsai Jensan; Engler, Mark J.; Rivard, Mark J.; Mahajan, Anita; Borden, Jonathan A.; Zheng Zhen

2001-01-01

For stereotactic radiosurgery using the Leksell Gamma Knife system, it is important to perform a pre-treatment verification of the maximum dose calculated with the Leksell GammaPlan[reg] (D LGP ) stereotactic radiosurgery system. This verification can be incorporated as part of a routine quality assurance (QA) procedure to minimize the chance of a hazardous overdose. To implement this procedure, a formalism has been developed to calculate the dose D CAL (X,Y,Z,d av ,t) using the following parameters: average target depth (d av ), coordinates (X,Y,Z) of the maximum dose location or any other dose point(s) to be verified, 3-dimensional (3-dim) beam profiles or off-center-ratios (OCR) of the four helmets, helmet size i, output factor O i , plug factor P i , each shot j coordinates (x,y,z) i,j , and shot treatment time (t i,j ). The average depth of the target d av was obtained either from MRI/CT images or ruler measurements of the Gamma Knife Bubble Head Frame. D CAL and D LGP were then compared to evaluate the accuracy of this independent calculation. The proposed calculation for an independent check of D LGP has been demonstrated to be accurate and reliable, and thus serves as a QA tool for Gamma Knife stereotactic radiosurgery

Direct dose measurement on patient during percutaneous coronary intervention procedures using radiophotoluminescence glass dosimeters

International Nuclear Information System (INIS)

Kato, Mamoru; Chida, Koichi; Moritake, Takashi; Sato, Tadaya; Oosaka, Hajime; Toyoshima, Hideto; Zuguchi, Masayuki; Abe, Yoshihisa

2017-01-01

The purpose of this research was to measure accurate patient entrance skin dose and maximum skin absorbed dose (MSD) to prevent radiation skin injuries in percutaneous coronary interventions (PCIs). We directly measured the MSD on 50 PCIs by using multiple radiophotoluminescence glass dosimeters and a modified dosimetry gown. Also, we analysed the correlation between the MSD and indirect measurement parameters, such as fluoroscopic time (FT), dose-area product (DAP) and cumulative air kerma (C-AK). There were very strong correlations between MSD and FT, DAP and C-AK, with the correlation between MSD and C-AK being the strongest (r = 0.938). In conclusion, the regression lines using MSD as an outcome value (y) and C-AK as predictor variables (x) were y = 1.12x (R"2 = 0.880). From the linear regression equation, MSD is estimated to be ∼1.12 times that of C-AK in real time. (authors)

Depth dose curves from 90Sr+90Y clinical applicators using the thermoluminescent technique

International Nuclear Information System (INIS)

Antonio, Patricia L.; Caldas, Linda V.E.; Oliveira, Mercia L.

2009-01-01

The 90 Sr+ 90 Y beta-ray sources widely used in brachytherapy applications were developed in the 1950's. Many of these sources, called clinical applicators, are still routinely used in several Brazilian radiotherapy clinics for the treatment of superficial lesions in the skin and eyes, although they are not commercialized anymore. These applicators have to be periodically calibrated, according to international recommendations, because these sources have to be very well specified in order to reach the traceability of calibration standards. In the case of beta-ray sources, the recommended quantity is the absorbed dose rate in water at a reference distance from the source. Moreover, there are other important quantities, as the depth dose curves and the source uniformity for beta-ray plaque sources. In this work, depth dose curves were obtained and studied of five dermatological applicators, using thin thermoluminescent dosimeters of CaSO 4 :Dy and phantoms of PMMA with different thicknesses (between 1.0 mm and 5.0 mm) positioned between each applicator and the TL pellets. The depth dose curves obtained presented the expected attenuation response in PMMA, and the results were compared with data obtained for a 90 Sr+ 90 Y standard source reported by the IAEA, and they were considered satisfactory. (author)

Critical Survey of the Analysis of Microscopic Distribution of some Bone-Seeking Radionuclides and Assessment of Absorbed Dose; Analyse de la Distribution Microscopique de Radionucleides Osteophiles et Determination de la Dose Absorbee; Kriticheskij obzor dannykh analiza mikroskopicheskogo raspredeleniya otkladyvayushchikhsya v kostyakh radioizotopov i opredelenie pogloshchennoj dozy; Estudio Critico de la Distribucion Microscopica de Algunos Radionuclidos Osteofilos y Evaluacion de la Dosis Absorbida

Energy Technology Data Exchange (ETDEWEB)

Jee, W. S.S.

1964-10-15

des rayonnements emis par le plutonium depose en surface sur les diverses parties de la zone distale du femur sont les suivants: trabecule metaphysaire, 3; periode interne, 2,6; trabecule epiphysaire, 1,5; canaux de Havers, 1,2; perioste externe, 1. Le depot en surface maximum localise pour les trabecules des vertebres est 35 a 66 fois plus important que la moyenne calculee de debit de dose du a la retention dans le corps. Les auteurs discutent les modifications de la localisation initiale non uniforme du radium et du plutonium en fonction du temps dans leurs rapports avec la nature du remodelage cellulaire de l'os et avec la perte du radionucleide par echange a long terme. Enfin, dans un exemple avec des mesures de la dose de rayonnements locale du plutonium et du radium, faites compte tenu du volume des cellules irradiees, la retention du corps et l'incidence des tumeurs sont mises en correlation et utilisees pour obtenir une toxicite relative du plutonium par rapport au radium et demontrer la valeur d'une certaine connaissance de la distribution microscopique des doses de rayonnements. (author) [Spanish] Los estudios detallados sobre la distribucion microscopica de la dosis proporcionan informacion sobre la distribucion no uniforme de las radiaciones, a diferencia de la distribucion supuesta uniforme, que se deduce de los datos relativos a la retencion en todo el organismo. En ausencia de cierto conocimiento de la distribucion microscopica de la dosis, tanto en el espacio como en el tiempo, se corre el riesgo, al tratar de acopiar datos comparativos sobre la toxicidad, de llegar a deducciones erroneas y pasar por alto conclusiones importantes. A causa de la complejidad del problema, los datos publicados sobre la medicion de la distribucion microscopica de la dosis de irradiacion son muy escasos. Las tecnicas actuales recurren a la autorradiografia y son muy laboriosas. Exigen el recuento de trazas y trabajos de micro- densitometria. La determinacion de la

Occupational dose trends in Tanzania

International Nuclear Information System (INIS)

Muhogora, W.E.; Nyanda, A.M.; Ngaile, J.E.; Lema, U.S.

1998-01-01

This paper describes the present status of occupational radiation exposure of monitored workers in Tanzania from 1986 to 1997. The analysis of dose records observes over this period, a fluctuating trend both in the individual and collective doses. The trend is more related to the fluctuations of the number of radiation workers than to the possible radiation safety changes of the working conditions. It has been found that, the maximum annual dose for the worker in all work categories was about 18 mSv y -1 . This suggests that the occupational radiation exposure in all practices satisfies the current dose limitation system. The national exposure summary shows that, the highest collective dose of 12.8 man-Sv which is 90% of the total collective dose, was due to medical applications. The applications in industry and research had a contribution of nearly 0.8 and 0.7 man-Sv respectively. From the professional point of view, the medical diagnostic radiographers received the highest collective dose of 11.2 man-Sv. Although the medical physicists recorded the minimum collective dose of nearly 0.07 man-Sv, the data shows that this profession received the highest mean dose of about 33 mSv in 12 years. Some achievements of the personnel monitoring services and suggestions for future improvement are pointed out. (author)

Personnel dose reduction in 90Y microspheres liver-directed radioembolization: from interventional radiology suite to patient ward.

Science.gov (United States)

Law, Martin; Wong, K K; Tso, W K; Lee, Victor; Luk, M Y; Tong, C C; Chu, Ferdinand

2017-03-01

To describe a method to reduce the external radiation exposure emitted from the patient after liver-directed radioembolization using 90 Y glass microspheres, to quantitatively estimate the occupational dose of medical personnel providing patient care to the patient radioembolized with the use of the method and to discuss radiation exposure to patients who are adjacent if the patient radioembolized needs hospitalization. A lead-lined blanket of lead equivalence of 0.5 mm was used to cover the patient abdomen immediately after the 90 Y radioembolization procedure, in order to reduce the radiation emitted from the patient. The interventional radiologist used a rod-type puncture site compressor for haemostasis to avoid direct contact with possible residual radioactivity at the puncture site. Dose rates were measured at the interventional radiologist chest and hand positions during puncture site pressing for haemostasis with and without the use of the blanket. The measurement results were applied to estimate the occupational dose of colleagues performing patient care to the patient radioembolized. The exposure to patients adjacent in the ward was estimated if the patient radioembolized was hospitalized. The radiation exposures measured at the radiologist chest and hand positions have been significantly reduced with the lead-lined blanket in place. The radiologist, performing puncture site pressing at the end of radioembolization procedure, would receive an average hand dose of 1.95 μSv and body dose under his own lead apron of 0.30 μSv for an average 90 Y microsphere radioactivity of 2.54 GBq. Other medical personnel, nurses and porters, would receive occupational doses corresponding to an hour of background radiation. If the patient radioembolized using 90 Y needs hospitalization in a common ward, using the lead-lined blanket to cover the abdomen of the patient and keeping a distance of 2 m from the patient who is adjacent would reduce the exposure by 0

Modelling of hand phantoms and optimisation of dose measurements in inhomogeneous beta-photon radiation fields using the MCNP code

International Nuclear Information System (INIS)

Becker, Frank; Blunck, Christoph; Hegenbart, Lars; Heide, Bernd; Leone, Debora; Nagels, Sven; Schimmelpfeng, Jutta; Urban, Manfred

2008-01-01

Inhomogeneous beta-photon radiation fields make a reliable dose difficult to determine. Routine monitoring with dosemeters does not guarantee any accurate determination of the local skin dose. In general, correction factors are used to correct for the measured dose and the maximum exposure. However, strong underestimations of the maximum exposure are possible, depending on the individual handling and the reliability of dose measurements. Simulations provide the possibility to track the points of highest exposure and the origin of the highest dose. In this connection, simulations are performed with MCNPX. In order to investigate the local skin dose, two hand phantoms are used, a model based on geometrical elements and a voxel hand. A typical case of radio synoviorthesis, handling of a syringe filled with 90 Y, is simulated. Another simulation focuses on the selective internal radio therapy, revealing the origin of the main dose component in the mixed beta-photon radiation field of a 90 Y vial in an opened transport container. (author)

Radiation exposure during paediatric CT in Sudan: CT dose, organ and effective doses

International Nuclear Information System (INIS)

Suliman, I.I.; Khamis, H.M.; Ombada, T.H.; Alzimami, K.; Alkhorayef, M.; Sulieman, A.

2015-01-01

The purpose of this study was to assess the magnitude of radiation exposure during paediatric CT in Sudanese hospitals. Doses were determined from CT acquisition parameters using CT-Expo 2.1 dosimetry software. Doses were evaluated for three patient ages (0-1, 1-5 and 5-10 y) and two common procedures (head and abdomen). For children aged 0-1 y, volume CT air kerma index (C vol ), air Kerma-length product and effective dose (E) values were 19.1 mGy, 265 mGy.cm and 3.1 mSv, respectively, at head CT and those at abdominal CT were 8.8 mGy, 242 mGy.cm and 7.7 mSv, respectively. Those for children aged 1-5 y were 22.5 mGy, 305 mGy.cm and 1.1 mSv, respectively, at head CT and 12.6 mGy, 317 mGy.cm, and 5.1 mSv, respectively, at abdominal CT. Dose values and variations were comparable with those reported in the literature. Organ equivalent doses vary from 7.5 to 11.6 mSv for testes, from 9.0 to 10.0 mSv for ovaries and from 11.1 to 14.3 mSv for uterus in abdominal CT. The results are useful for dose optimisation and derivation of national diagnostic reference levels. (authors)

Rendimiento y calidad de semilla de pasto guinea (Panicum maximum Jacq.) cv. Tanzania usando la fitohormona esteroidal cidef-4

OpenAIRE

Bertín Maurilio Joaquín Torres; Miguel Angel Moreno Carrillo; Santiago Joaquín Cancino; Alfonso Hernández Garay; Jorge Pérez Pérez; Armando Gómez Vázquez

2010-01-01

El objetivo fue evaluar el efecto de la fitohormona esteroidal cidef-4 en el rendimiento y calidad de semilla en Panicum maximum cv. Tanzania. El experimento se realizó durante el 2001 en Tejupilco, Estado de México. Los tratamientos evaluados fueron, T1=testigo, T2=4 mg L-1 de ingrediente activo (i.a.) aplicados al inicio de antesis, T3=4 mg L-1 de i.a. aplicados antes del espigamiento e inicio de antesis, T4=8 mg L-1 de i.a. aplicados al inicio de antesis, T5=8 mg L-1 de i.a. aplicados ante...

Rendimiento y calidad de semilla de pasto guinea (Panicum maximum Jacq.) cv. Tanzania usando la fitohormona esteroidal cidef-4

OpenAIRE

Joaquín Torres, Bertin Maurilio; Moreno Carrillo, Miguel Angel; Joaquín Cancino, Santiago; Hernández Garay, Alfonso; Pérez Pérez, Jorge; Gómez Vázquez, Armando

2010-01-01

El objetivo fue evaluar el efecto de la fitohormona esteroidal cidef-4 en el rendimiento y calidad de semilla en Panicum maximum cv. Tanzania. El experimento se realizó durante el 2001 en Tejupilco, Estado de México. Los tratamientos evaluados fueron: T1=testigo; T2=4 mg L-1 de ingrediente activo (i.a.) aplicados al inicio de antesis; T3=4 mg L-1 de i.a. aplicados antes del espigamiento e inicio de antesis; T4=8 mg L-1 de i.a. aplicados al inicio de antesis; T5=8 mg L-1 de i.a. aplicados ante...

Potential radionuclide emissions from stacks on the Hanford site, Part 1: Dose assessment

Energy Technology Data Exchange (ETDEWEB)

Davis, W.E.; Barnett, J.M. [Westinghouse Hanford Company, Richland, WA (United States)

1995-02-01

On February 3, 1993, the U.S. Department of Energy, Richland Operations Office received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the U.S. Environmental Protection Agency, Region 10. The Compliance Order requires RL to evaluate all radionuclide emission points at the Hanford Site to determine which are subject to continuous emission monitoring requirements in 40 CFR 61, Subpart H, and to continuously monitor radionuclide emissions in accordance with requirements in 40 CFR 61.93. The Information Request required RL to provide a written Compliance Plan to meet the requirements of the Compliance Order. A Compliance Plan was submitted to EPA, Region 10, on April 30, 1993. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company stacks registered with the Washington State Department of Health on the Hanford Site. Stacks that have the potential emissions to cause an effective dose equivalent to a maximum exposed individual greater than 0.1 mrem/y must be monitored continuously for radionuclide emissions. Five methods were approved by EPA, Region 10 for performing the assessments: Release Fractions from Appendix D of 40 CFR 61, Back Calculations Using A HEPA Filtration Factor, Nondestructive Assay of HEPA Filters, A Spill Release Fraction, and Upstream of HEPA Filter Air Concentrations. The first two methods were extremely conservative for estimating releases. The third method, which used a state-of-the-art portable gamma spectrometer, yielded surprising results from the distribution of radionuclides on the HEPA filters. All five methods are described. Assessments using a HEPA Filtration Factor for back calculations identified 32 stacks that would have emissions that would cause an EDE to the MEI greater than 0.1 mrem y{sup {minus}1}. The number was reduced to 15 stacks when the other methods were applied. The paper discusses reasons for the overestimates.

3D inpatient dose reconstruction from the PET-CT imaging of 90Y microspheres for metastatic cancer to the liver: Feasibility study

International Nuclear Information System (INIS)

Fourkal, E.; Veltchev, I.; Lin, M.; Meyer, J.; Koren, S.; Doss, M.; Yu, J. Q.

2013-01-01

Purpose: The introduction of radioembolization with microspheres represents a significant step forward in the treatment of patients with metastatic disease to the liver. This technique uses semiempirical formulae based on body surface area or liver and target volumes to calculate the required total activity for a given patient. However, this treatment modality lacks extremely important information, which is the three-dimensional (3D) dose delivered by microspheres to different organs after their administration. The absence of this information dramatically limits the clinical efficacy of this modality, specifically the predictive power of the treatment. Therefore, the aim of this study is to develop a 3D dose calculation technique that is based on the PET imaging of the infused microspheres.Methods: The Fluka Monte Carlo code was used to calculate the voxel dose kernel for 90 Y source with voxel size equal to that of the PET scan. The measured PET activity distribution was converted to total activity distribution for the subsequent convolution with the voxel dose kernel to obtain the 3D dose distribution. In addition, dose-volume histograms were generated to analyze the dose to the tumor and critical structures.Results: The 3D inpatient dose distribution can be reconstructed from the PET data of a patient scanned after the infusion of microspheres. A total of seven patients have been analyzed so far using the proposed reconstruction method. Four patients underwent treatment with SIR-Spheres for liver metastases from colorectal cancer and three patients were treated with Therasphere for hepatocellular cancer. A total of 14 target tumors were contoured on post-treatment PET-CT scans for dosimetric evaluation. Mean prescription activity was 1.7 GBq (range: 0.58–3.8 GBq). The resulting mean maximum measured dose to targets was 167 Gy (range: 71–311 Gy). Mean minimum dose to 70% of target (D70) was 68 Gy (range: 25–155 Gy). Mean minimum dose to 90% of target (D90

Regulatory Forum Opinion Piece*: Retrospective Evaluation of Doses in the 26-week Tg.rasH2 Mice Carcinogenicity Studies: Recommendation to Eliminate High Doses at Maximum Tolerated Dose (MTD) in Future Studies.

Science.gov (United States)

Paranjpe, Madhav G; Denton, Melissa D; Vidmar, Tom J; Elbekai, Reem H

2015-07-01

High doses in Tg.rasH2 carcinogenicity studies are usually set at the maximum tolerated dose (MTD), although this dose selection strategy has not been critically evaluated. We analyzed the body weight gains (BWGs), mortality, and tumor response in control and treated groups of 29 Tg.rasH2 studies conducted at BioReliance. Based on our analysis, it is evident that the MTD was exceeded at the high and/or mid-doses in several studies. The incidence of tumors in high doses was lower when compared to the low and mid-doses of both sexes. Thus, we recommend that the high dose in male mice should not exceed one-half of the estimated MTD (EMTD), as it is currently chosen, and the next dose should be one-fourth of the EMTD. Because females were less sensitive to decrements in BWG, the high dose in female mice should not exceed two-third of EMTD and the next dose group should be one-third of EMTD. If needed, a third dose group should be set at one-eighth EMTD in males and one-sixth EMTD in females. In addition, for compounds that do not show toxicity in the range finding studies, a limit dose should be applied for the 26-week carcinogenicity studies. © 2014 by The Author(s).

Entrance surface dose in cerebral interventional radiology procedures

Energy Technology Data Exchange (ETDEWEB)

Barrera-Rico, M.; Lopez-Rendon, X.; Rivera-Ordonez, C. E.; Gamboa-deBuen, I. [Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, 04510 DF (Mexico); Instituto Nacional de Neurologia y Neurocirugia Manuel Velasco Suarez, 14269 DF (Mexico); Instituto de Ciencias Nucleares, Universidad Nacional Autonoma de Mexico, 04510 DF (Mexico)

2012-10-23

At the Instituto Nacional de Neurologia y Neurocirugia (INNN) diagnostic as well as therapeutic procedures of interventional radiology are carried out. Since the procedures can last from some minutes to several hours, the absorbed dose for the patient could increase dangerously. An investigation had begun in order to determine the entrance surface dose (ESD) using 25 thermoluminiscent dosimeters TLD-100 and 8 strips of 15 Multiplication-Sign 1 cm{sup 2} of Gafchromic XR-QA2 film bound in a holder of 15 Multiplication-Sign 15 cm{sup 2} in the posteroanterior (PA) and lateral (LAT) positions during all the procedure. The results show that maximum ESD could be from 0.9 to 2.9 Gy for the PA position and between 1.6 and 2.5 Gy for the lateral position. The average ESD was between 0.7 and 1.3 Gy for the PA position, and from 0.44 to 1.1 Gy for the lateral position in a therapeutic procedure.

Entrance surface dose in cerebral interventional radiology procedures

International Nuclear Information System (INIS)

Barrera-Rico, M.; López-Rendón, X.; Rivera-Ordóñez, C. E.; Gamboa-deBuen, I.

2012-01-01

At the Instituto Nacional de Neurología y Neurocirugía (INNN) diagnostic as well as therapeutic procedures of interventional radiology are carried out. Since the procedures can last from some minutes to several hours, the absorbed dose for the patient could increase dangerously. An investigation had begun in order to determine the entrance surface dose (ESD) using 25 thermoluminiscent dosimeters TLD-100 and 8 strips of 15 ×1 cm 2 of Gafchromic XR-QA2 film bound in a holder of 15×15 cm 2 in the posteroanterior (PA) and lateral (LAT) positions during all the procedure. The results show that maximum ESD could be from 0.9 to 2.9 Gy for the PA position and between 1.6 and 2.5 Gy for the lateral position. The average ESD was between 0.7 and 1.3 Gy for the PA position, and from 0.44 to 1.1 Gy for the lateral position in a therapeutic procedure.

Hand Dose in Nuclear Medicine Staff Members

International Nuclear Information System (INIS)

Taha, T.M.; Shahein, A.Y.; Hassan, R.

2009-01-01

Measurement of the hand dose during preparation and injection of radiopharmaceuticals is useful in the assessment of the extremity doses received by nuclear medicine personnel. Hand radiation doses to the occupational workers that handling 99m Tc-labeled compounds, 131 I for diagnostic in nuclear medicine were measured by thermoluminescence dosimetry. A convenient method is to use a TLD ring dosimeter for measuring doses of the diagnostic units of different nuclear medicine facilities . Their doses were reported in millisieverts that accumulated in 4 weeks. The radiation doses to the hands of nuclear medicine staff at the hospitals under study were measured. The maximum expected annual dose to the extremities appeared to be less than the annual limit (500 mSv/y) because all of these workers are on rotation and do not constantly handle radioactivity throughout the year

Robust Maximum Association Estimators

NARCIS (Netherlands)

A. Alfons (Andreas); C. Croux (Christophe); P. Filzmoser (Peter)

2017-01-01

textabstractThe maximum association between two multivariate variables X and Y is defined as the maximal value that a bivariate association measure between one-dimensional projections αX and αY can attain. Taking the Pearson correlation as projection index results in the first canonical correlation

3D inpatient dose reconstruction from the PET-CT imaging of {sup 90}Y microspheres for metastatic cancer to the liver: Feasibility study

Energy Technology Data Exchange (ETDEWEB)

Fourkal, E.; Veltchev, I.; Lin, M.; Meyer, J. [Department of Radiation Oncology, Fox Chase Cancer Center, Philadelphia, Pennsylvania 19111 (United States); Koren, S. [Department of Radiation Oncology, Beth Israel Comprehensive Cancer Center, New York, New York 10011 (United States); Doss, M.; Yu, J. Q. [Department of Diagnostic Imaging, Fox Chase Cancer Center, Philadelphia, Pennsylvania 19111 (United States)

2013-08-15

Purpose: The introduction of radioembolization with microspheres represents a significant step forward in the treatment of patients with metastatic disease to the liver. This technique uses semiempirical formulae based on body surface area or liver and target volumes to calculate the required total activity for a given patient. However, this treatment modality lacks extremely important information, which is the three-dimensional (3D) dose delivered by microspheres to different organs after their administration. The absence of this information dramatically limits the clinical efficacy of this modality, specifically the predictive power of the treatment. Therefore, the aim of this study is to develop a 3D dose calculation technique that is based on the PET imaging of the infused microspheres.Methods: The Fluka Monte Carlo code was used to calculate the voxel dose kernel for {sup 90}Y source with voxel size equal to that of the PET scan. The measured PET activity distribution was converted to total activity distribution for the subsequent convolution with the voxel dose kernel to obtain the 3D dose distribution. In addition, dose-volume histograms were generated to analyze the dose to the tumor and critical structures.Results: The 3D inpatient dose distribution can be reconstructed from the PET data of a patient scanned after the infusion of microspheres. A total of seven patients have been analyzed so far using the proposed reconstruction method. Four patients underwent treatment with SIR-Spheres for liver metastases from colorectal cancer and three patients were treated with Therasphere for hepatocellular cancer. A total of 14 target tumors were contoured on post-treatment PET-CT scans for dosimetric evaluation. Mean prescription activity was 1.7 GBq (range: 0.58–3.8 GBq). The resulting mean maximum measured dose to targets was 167 Gy (range: 71–311 Gy). Mean minimum dose to 70% of target (D70) was 68 Gy (range: 25–155 Gy). Mean minimum dose to 90% of target

Determination of 210Po in leafy vegetables and annual effective dose assessment to the inhabitants of Mumbai city, India

International Nuclear Information System (INIS)

Dubey, J.S.; Sahoo, S.K.; Mohapatra, S.; Patra, A.C.; Lenka, P.; Ravi, P.M.; Tripathi, R.M.; Nair, A.

2014-01-01

Present study deals with the measurement of activity concentration of 210 Po in leafy vegetable of Mumbai city and corresponding ingestion dose assessment to the population. 210 Po activity levels ranged from 44.5-183.3 with an average value of 81.8 mBq/kg. Minimum activity of 210 Po was found in shepu and maximum in methi. The concentration reported here is slightly more than the UNSCEAR value. The estimated total effective dose was found to vary from 0.3 - 1.4 with an average value of 0.6 μSv/y, which is about 1% of global average total ingestion dose due to 210 Po. (author)

Mortality and career radiation doses for workers at a commercial nuclear power plant: feasibility study

International Nuclear Information System (INIS)

Goldsmith, R.; Boice, J.D. Jr.; Hrubec, Z.; Hurwitz, P.E.; Goff, T.E.; Wilson, J.

1989-01-01

Career radiation doses for 8,961 male workers at the Calvert Cliffs Nuclear Power Plant (CCNPP) were determined for both utility (n = 4,960) and contractor (n = 4,001) employees. Workers were followed from the time of first employment at CCNPP (including plant construction) to the end of 1984 (mean follow-up = 5.4 y). Plant operation began in 1975. The mean duration of employment was 1.9 y at CCNPP and 3.1 y in the nuclear industry. Career radiation doses were determined from dosimetry records kept by the utility company and the U.S. Nuclear Regulatory Commission (NRC). For all exposed workers, the average career dose was 21 mSv and was higher for contractor (30 mSv) than utility (13 mSv) workers. Career doses were also higher among those employed in the nuclear industry for greater than or equal to 15 y (111 mSv) and among workers classified as health physicists (56 mSv). Cumulative doses of greater than or equal to 50 mSv were received by 12% of the workers; the maximum career dose reported was 470 mSv. The availability of social security numbers for practically all employees facilitated record-linkage methods to determine mortality; 161 deaths were identified. On average the workers experienced mortality from all causes that was 15% less than that of the general population of the U.S., probably due to healthier members of the population being selected for employment. Our investigation demonstrates that historical information is available from which career doses could be constructed and that, in principle, it is feasible to conduct epidemiologic studies of nuclear power plant workers in the U.S. Although difficult, the approach taken could prove useful until such time as a comprehensive registry of U.S. radiation workers is established

Effects of Minimum and Maximum Doses of Furosemide on Fractional Shortening Parameter in Echocardiography of the New Zealand White Rabbit

Directory of Open Access Journals (Sweden)

Roham Vali, Mohammad Nasrollahzadeh Masouleh* and Siamak Mashhady Rafie1

2013-04-01

Full Text Available There is no data on the effect of maximum and minimum doses of furosemide on heart's work performance and amount of fractional shortening (FS in echocardiography of rabbit. This study was designed to validate probability of the mentionable effect. Twenty-four healthy female New Zealand white rabbits were divided into four equal groups. Maximum and minimum doses of furosemide were used for the first and second groups and the injection solution for the third and fourth groups was sodium chloride 0.9% which had the same calculated volumes of furosemide for the first two groups, respectively. The left ventricle FS in statutory times (0, 2, 5, 15, 30 minutes was determined by echocardiography. Measurements of Mean±SD, maximum and minimum amounts for FS values in all groups before injection and in statutory times were calculated. Statistical analysis revealed non-significant correlation between the means of FS. The results of this study showed that furosemide can be used as a diuretic agent for preparing a window approach in abdominal ultrasonography examination with no harmful effect on cardiac function.

Modelling maximum likelihood estimation of availability

International Nuclear Information System (INIS)

Waller, R.A.; Tietjen, G.L.; Rock, G.W.

1975-01-01

Suppose the performance of a nuclear powered electrical generating power plant is continuously monitored to record the sequence of failure and repairs during sustained operation. The purpose of this study is to assess one method of estimating the performance of the power plant when the measure of performance is availability. That is, we determine the probability that the plant is operational at time t. To study the availability of a power plant, we first assume statistical models for the variables, X and Y, which denote the time-to-failure and the time-to-repair variables, respectively. Once those statistical models are specified, the availability, A(t), can be expressed as a function of some or all of their parameters. Usually those parameters are unknown in practice and so A(t) is unknown. This paper discusses the maximum likelihood estimator of A(t) when the time-to-failure model for X is an exponential density with parameter, lambda, and the time-to-repair model for Y is an exponential density with parameter, theta. Under the assumption of exponential models for X and Y, it follows that the instantaneous availability at time t is A(t)=lambda/(lambda+theta)+theta/(lambda+theta)exp[-[(1/lambda)+(1/theta)]t] with t>0. Also, the steady-state availability is A(infinity)=lambda/(lambda+theta). We use the observations from n failure-repair cycles of the power plant, say X 1 , X 2 , ..., Xsub(n), Y 1 , Y 2 , ..., Ysub(n) to present the maximum likelihood estimators of A(t) and A(infinity). The exact sampling distributions for those estimators and some statistical properties are discussed before a simulation model is used to determine 95% simulation intervals for A(t). The methodology is applied to two examples which approximate the operating history of two nuclear power plants. (author)

Structure and magnetic properties of GdxY1−xFeO3 obtained by mechanosynthesis

International Nuclear Information System (INIS)

Bolarín-Miró, A.M.; Sánchez-De Jesús, F.; Cortés-Escobedo, C.A.; Valenzuela, R.; Ammar, S.

2014-01-01

Highlights: • Orthohombic GDxY1-xFeO3 was obtained by mechanosynthesis after 5 h of milling. • Mechanosynthesized GdxY1-xFeO3 show weak ferromagnetic behavior. • Mechanosynthesis promotes unexpected magnetic properties in GdxY1-xFeO3. • The maximum magnetization that was reached 7.7 emu/g for Gdo.75Y0.25FeO3. • For Gd0.5Y0.5FeO3, the magnetization decreases down to 2.1 emu/g. -- Abstract: Solid solutions of yttrium–gadolinium orthoferrites Gd x Y 1−x FeO 3 (0 ⩽ x ⩽ 1) were prepared by high-energy ball milling. The aim of this work was to study the influence of the synthesis parameters on the crystal structure and the magnetic behavior of these solid solutions. The precursors, Fe 2 O 3 , Y 2 O 3 and Gd 2 O 3 , mixed in a stoichiometric ratio to obtain these orthoferrites, were milled for different times (up to 5 h). X-ray diffraction and Rietveld refinement were used to elucidate the phase transformation as a function of the milling time. Results showed the complete formation of orthoferrite with an orthorhombic structure (S.G. Pbnm) without any annealing after 5 h of milling for all of the compositions. The effect of the synthesis process and the x value on the crystal structure and the magnetic properties were also studied. All of the synthesized powders demonstrated weak ferromagnetic behavior. In particular, an increase in the maximum magnetization for all the compositions was found, with a maximum that reached 7.7 emu/g for Gd 0.75 Y 0.25 FeO 3 . For Gd 0.5 Y 0.5 FeO 3 , the magnetization decreases down to 2.1 emu/g. A small contamination of metallic Fe was confirmed through electron spin resonance experiments

Uncertainty analysis for an updated dose assessment for a US nuclear test site: Bikini Atoll

International Nuclear Information System (INIS)

Bogen, K.T.; Conrado, C.L.; Robison, W.L.

1995-11-01

A detailed analysis of uncertainty and interindividual variability in estimated doses was conducted for a rehabilitation scenario for Bikini Island at Bikini Atoll, in which the top 40 cm of soil would be removed in the housing and village area, and the rest of the island is treated with potassium fertilizer, prior to an assumed resettlement date of 1999. Predicted doses were considered for the following fallout-related exposure pathways: ingested Cesium-137 and Strontium-90, external gamma exposure, and inhalation and ingestion of Americium-241 + Plutonium-239+240. Two dietary scenarios were considered: (1) imported foods are available (IA), and (2) imported foods are unavailable (only local foods are consumed) (IUA). Corresponding calculations of uncertainty in estimated population-average dose showed that after ∼5 y of residence on Bikini, the upper and lower 95% confidence limits with respect to uncertainty in this dose are estimated to be approximately 2-fold higher and lower than its population-average value, respectively (under both IA and IUA assumptions). Corresponding calculations of interindividual variability in the expected value of dose with respect to uncertainty showed that after ∼5 y of residence on Bikini, the upper and lower 95% confidence limits with respect to interindividual variability in this dose are estimated to be approximately 2-fold higher and lower than its expected value, respectively (under both IA and IUA assumptions). For reference, the expected values of population-average dose at age 70 were estimated to be 1.6 and 5.2 cSv under the IA and IUA dietary assumptions, respectively. Assuming that 200 Bikini resettlers would be exposed to local foods (under both IA and IUA assumptions), the maximum 1-y dose received by any Bikini resident is most likely to be approximately 2 and 8 mSv under the IA and IUA assumptions, respectively

Radon Concentration And Dose Assessment In Well Water Samples From Karbala Governorate Of Iraq

Science.gov (United States)

Al-Alawy, I. T.; Hasan, A. A.

2018-05-01

There are numerous studies around the world about radon concentrations and their risks to the health of human beings. One of the most important social characteristics is the use of water wells for irrigation, which is a major source of water pollution with radon gas. In the present study, six well water samples have been collected from different locations in Karbala governorate to investigate radon concentration level using CR-39 technique. The maximum value 4.112±2.0Bq/L was in Al-Hurr (Al-Qarih Al-Easariah) region, and the lowest concentration of radon was in Hay Ramadan region which is 2.156±1.4Bq/L, with an average value 2.84±1.65Bq/L. The highest result of annual effective dose (AED) was in Al-Hurr (Al-Qarih Al-Easariah) region which is equal to 15.00±3.9μSv/y, while the minimum was recorded in Hay Ramadan 7.86±2.8μSv/y, with an average value 10.35±3.1μSv/y. The current results have shown that the radon concentrations in well water samples are lower than the recommended limit 11.1Bq/L and the annual effective dose in these samples are lower than the permissible international limit 1mSv/y.

Measurements Of Fingers Doses Of Staff Members In Nuclear Medicine Department

International Nuclear Information System (INIS)

AL LEHYANI, S.H.; SHOUSHA, H.A.; HASSAN, R.A.

2009-01-01

For some occupationally radiation exposed groups, the hands are more heavily exposed to ionizing radiation than the rest of the body. The Egyptian Atomic Energy Authority runs an extensive personal dosimetry service in Egypt, but finger doses have not been measured to a wide extent. In this study, the finger doses were measured for five different nuclear medicine staff occupational groups for which heavy irradiation of the hands was suspected. Finger doses were measured for nuclear medicine physicians, technologists, nurses and physicists. The nuclear medicine staff working with the radioactive materials wears two TLD dosimeters during the whole period, which lasted from 1 to 4 weeks. The staff performs their work on a regular basis throughout the month, and means annual doses were calculated for these groups. The doses to the fingers for the 99m Tc technologists and nurses of groups (2) and (3) were observed to be 30.24 ± 14.5 μSv/GBq (mean ± SD) and 30.37 ± 17.5 μSv/GBq, respectively. Similarly, the dose to the fingers for the 131 I technologists in group (5) was estimated to be 126.13 ± 38.2μSv/GBq. Finger doses for the physicians could not be calculated per unit of activity because they did not handle the radiopharmaceuticals directly but their doses were reported in millisieverts that accumulated in 1 week. The doses to the fingers of the physicist were 16.3±7.7 μSv/GBq. The maximum average finger dose in this study was found to be 2.8 mSv for the technologists handled therapeutic 131 I (group 5). It could be concluded that the maximum expected annual dose to the extremities appeared to be less than the annual limit (500 mSv/y).

Patient doses in digital cardiac imaging

International Nuclear Information System (INIS)

Huda, W.; Ogden, K.M.; Roskopf, M.L.; Phadke, K.

2001-01-01

In this pilot study, we obtained estimates of entrance skin doses and the corresponding effective doses to patients undergoing digital cardiac imaging procedures on a GE Advantx LC/LP Plus system. Data were obtained for six patients undergoing diagnostic examinations and six patients who had interventional procedures. For each patient examination, radiographic techniques for fluoroscopic and digital cine imaging were recorded, together with the irradiation geometry. The projection with the highest exposure resulted in an average skin dose of 0.64 ± 0.41 Gy (maximum of 1.6 Gy). The average patient skin doses taking into account overlapping projections was 1.1 ± 0.8 Gy (maximum of 3.0 Gy). The exposure area product (EAP) incident on the patient was converted into the energy imparted to the patient and the corresponding effective dose. The average patient effective dose was 28 ± 14 mSv (maximum 62 mSv), with the resultant average fatal cancer risk estimated to be of the order of 8x10 -3 . Average doses for interventional procedures in cardiac imaging are higher than those associated with diagnostic examinations by approximately 50%. (author)

Absorbed dose from a beta source as shown by thermoluminescence dosimetry

International Nuclear Information System (INIS)

Wintle, A.G.; Aitken, M.J.

1977-01-01

The depth-dose curve was obtained for a 90 Sr- 90 Y beta source using a fine grain TL phosphor to measure the observed dose, aluminium absorbers being interposed between the source and the detector; the curve went through a maximum at an absorber thickness of about 40 mg cm -2 . This curve was then used to predict the average dose rate to various thicknesses of calcium fluoride which has a similar absorption characteristic to aluminium; these values were compared with experimentally determined dose rates. This work was done in connection with thermoluminescence dating of flint and calcite in archaeology and geology. (author)

Intercomparison On Depth Dose Measurement

International Nuclear Information System (INIS)

Rohmah, N; Akhadi, M

1996-01-01

Intercomparation on personal dose evaluation system has been carried out between CSRSR-NAEA of Indonesia toward Standard Laboratory of JAERI (Japan) and ARL (Australia). The intercomparison was in 10 amm depth dose measurement , Hp (10), from the intercomparison result could be stated that personal depth dose measurement conducted by CSRSR was sufficiently good. Deviation of dose measurement result using personal dosemeter of TLD BG-1 type which were used by CSRSR in the intercomparison and routine photon personal dose monitoring was still in internationally agreed limit. Maximum deviation of reported doses by CSRSR compared to delivered doses for dosemeter irradiation by JAERI was -10.0 percent and by ARL was +29 percent. Maximum deviation permitted in personal dose monitoring is ± 50 percent

Regulatory Forum Opinion Piece*: Retrospective Evaluation of Doses in the 26-week Tg.rasH2 Mice Carcinogenicity Studies: Recommendation to Eliminate High Doses at Maximum Tolerated Dose in Future Studies. A Response to the Counterpoints.

Science.gov (United States)

Paranjpe, Madhav G; Denton, Melissa D; Vidmar, Tom J; Elbekai, Reem H

2016-01-01

We recently conducted a retrospective analysis of data collected from 29 Tg.rasH2 carcinogenicity studies conducted at our facility to determine how successful was the strategy of choosing the high dose of the 26-week studies based on an estimated maximum tolerated dose (MTD). As a result of our publication, 2 counterviews were expressed. Both counterviews illustrate very valid points in their interpretation of our data. In this article, we would like to highlight clarifications based on several points and issues they have raised in their papers, namely, the dose-level selection, determining if MTD was exceeded in 26-week studies, and a discussion on the number of dose groups to be used in the studies. © The Author(s) 2015.

Multicenter study on evaluation of the entrance skin dose by a direct measurement method in cardiac interventional procedures

International Nuclear Information System (INIS)

Kato, Mamoru; Chida, Koichi; Moritake, Takashi

2016-01-01

Deterministic effects have been reported in cardiac interventional procedures. To prevent radiation skin injuries in percutaneous coronary intervention (PCI), it is necessary to measure accurate patient entrance skin dose (ESD) and maximum skin absorbed dose (MSD). We measured the MSD on 62 patients in four facilities by using the Chest-RADIREC system. The correlation between MSD and fluoroscopic time, dose area product (DAP), and cumulative air kerma (AK) showed good results, with the correlation between MSD and AK being the strongest. The regression lines using MSD as an outcome value (y) and AK as predictor variables (x) was y=1.18x (R 2 =0.787). From the linear regression equation, MSD is estimated to be about 1.18 times that of AK in real time. The Japan diagnostic reference levels (DRLs) 2015 for IVR was established by the use of dose rates using acrylic plates (20 cm thick) at the interventional reference point. Preliminary reference levels proposed by International Atomic Energy Agency (IAEA) were provided using DAP. In this study, AK showed good correlation most of all. Hence we think that Japanese DRLs for IVR should reconsider by clinical patients' exposure dose such as AK. (author)

Pre-therapeutic dosimetry and biodistribution of 86Y-DOTA-Phe1-Tyr3-octreotide versus 111In-pentetreotide in patients with advanced neuroendocrine tumours

International Nuclear Information System (INIS)

Helisch, Andreas; Foerster, Gregor J.; Reber, Helmut; Buchholz, Hans-Georg; Bartenstein, Peter; Arnold, Rudolf; Goeke, Burkhard; Weber, Matthias M.; Wiedenmann, Bertram; Pauwels, Stanislas; Haus, Ulrike; Bouterfa, Hakim

2004-01-01

For the internal radiotherapy of neuroendocrine tumours, the somatostatin analogue DOTATOC labelled with 90 Y is frequently used [ 90 Y-DOTA-Phe 1 -Tyr 3 -octreotide (SMT487-OctreoTher)]. Radiation exposure to the kidneys is critical in this therapy as it may result in renal failure. The aim of this study was to compare cumulative organ and tumour doses based upon dosimetric data acquired with the chemically identical 86 Y-DOTA-Phe 1 -Tyr 3 -octreotide (considered as the gold standard) and the commercially available 111 In-pentetreotide. The cumulative organ and tumour doses for the therapeutic administration of 13.32 GBq 90 Y-DOTA-Phe 1 -Tyr 3 -octreotide (three cycles, each of 4.44 GBq) were estimated based on the MIRD concept (MIRDOSE 3.1 and IMEDOSE). Patients with a cumulative kidney dose exceeding 27 Gy had to be excluded from subsequent therapy with 90 Y-DOTA-Phe 1 -Tyr 3 -octreotide, in accordance with the directives of the German radiation protection authorities. The range of doses (mGy/MBq 90 Y-DOTA-Phe 1 -Tyr 3 -octreotide) for kidneys, spleen, liver and tumour masses was 0.6-2.8, 1.5-4.2, 0.3-1.3 and 2.1-29.5 ( 86 Y-DOTA-Phe 1 -Tyr 3 -octreotide), respectively, versus 1.3-3.0, 1.8-4.4, 0.2-0.8 and 1.4-19.7 ( 111 In-pentetreotide), with wide inter-subject variability. Despite renal protection with amino acid infusions, estimated cumulative kidney doses in two patients exceeded 27 Gy. Compared with 86 Y-DOTA-Phe 1 -Tyr 3 -octreotide, dosimetry with 111 In-pentetreotide overestimated doses to kidneys and spleen, whereas the radiation dose to the tumour-free liver was underestimated. However, both dosimetric approaches detected the two patients with an exceptionally high radiation burden to the kidneys that carried a potential risk of renal failure following radionuclide therapy. (orig.)

Pre-therapeutic dosimetry and biodistribution of 86Y-DOTA-Phe1-Tyr3-octreotide versus 111In-pentetreotide in patients with advanced neuroendocrine tumours.

Science.gov (United States)

Helisch, Andreas; Förster, Gregor J; Reber, Helmut; Buchholz, Hans-Georg; Arnold, Rudolf; Göke, Burkhard; Weber, Matthias M; Wiedenmann, Bertram; Pauwels, Stanislas; Haus, Ulrike; Bouterfa, Hakim; Bartenstein, Peter

2004-10-01

For the internal radiotherapy of neuroendocrine tumours, the somatostatin analogue DOTATOC labelled with 90Y is frequently used [90Y-DOTA-Phe1-Tyr3)-octreotide (SMT487-OctreoTher)]. Radiation exposure to the kidneys is critical in this therapy as it may result in renal failure. The aim of this study was to compare cumulative organ and tumour doses based upon dosimetric data acquired with the chemically identical 86Y-DOTA-Phe1-Tyr3-octreotide (considered as the gold standard) and the commercially available 111In-pentetreotide. The cumulative organ and tumour doses for the therapeutic administration of 13.32 GBq 90Y-DOTA-Phe1-Tyr3-octreotide (three cycles, each of 4.44 GBq) were estimated based on the MIRD concept (MIRDOSE 3.1 and IMEDOSE). Patients with a cumulative kidney dose exceeding 27 Gy had to be excluded from subsequent therapy with 90Y-DOTA-Phe1-Tyr3-octreotide, in accordance with the directives of the German radiation protection authorities. The range of doses (mGy/MBq 90Y-DOTA-Phe1-Tyr3-octreotide) for kidneys, spleen, liver and tumour masses was 0.6-2.8, 1.5-4.2, 0.3-1.3 and 2.1-29.5 (86Y-DOTA-Phe1-Tyr3-octreotide), respectively, versus 1.3-3.0, 1.8-4.4, 0.2-0.8 and 1.4-19.7 (111In-pentetreotide), with wide inter-subject variability. Despite renal protection with amino acid infusions, estimated cumulative kidney doses in two patients exceeded 27 Gy. Compared with 86Y-DOTA-Phe1-Tyr3-octreotide, dosimetry with 111In-pentetreotide overestimated doses to kidneys and spleen, whereas the radiation dose to the tumour-free liver was underestimated. However, both dosimetric approaches detected the two patients with an exceptionally high radiation burden to the kidneys that carried a potential risk of renal failure following radionuclide therapy.

Nanostructuring and high thermoelectric efficiency in p-type Ag(Pb{sub 1-y}Sn{sub y}){sub m}SbTe{sub 2{sub +m}}

Energy Technology Data Exchange (ETDEWEB)

Androulakis, J; Hsu, K F; Pcionek, R; Kanatzidis, M G [Department of Chemistry, Michigan Sate University, East Lansing, MI 48824-1793 (United States); Kong, H; Uher, C [Department of Physics, University of Michigan, Ann Arbor, MI 48109 (United States); D' Angelo, J J; Downey, A; Hogan, T [Electrical and Computer Engineering Department, Michigan State University, East Lansing, MI 48824-1226 (United States)

2006-05-02

The p-type Ag(Pb{sub 1-y}Sn{sub y}){sub m}SbTe{sub 2{sub +m}} materials shown in the figure demonstrate promising thermoelectric properties that are controlled with the parameters y and m. They can reach a maximum figure of merit of {proportional_to} 1.45 at 630 K. This surpasses the figure of merit of the present state-of-the-art p-type materials such as TAGS (1.2) and PbTe (0.8) at comparable temperatures. (Abstract Copyright [2006], Wiley Periodicals, Inc.)

Dose-response evaluation after Yttrium-90 resin microsphere radio-embolization of breast cancer liver metastases

International Nuclear Information System (INIS)

Gnesin, S.; Verdun, F.R.; Baechler, S.; Boubacker, A.; Adib, S.; Cherbuin, N.; Prior, J.O.; Bize, P.; Denys, A.

2015-01-01

Full text of publication follows. Aim: Yttrium-90 resin microsphere radio-embolization is a valuable therapeutic option in metastatic breast cancer patients with progressive disease refractory to chemotherapy. The goal of this study was to evaluate the dose-response relationship of liver metastasis based on a 3D voxelized 90 Y PET dosimetry. Materials and methods: we studied the dose-response relationship of twelve hepatic lesions in four selected patients with metastatic breast cancer who underwent 90 Y radio-embolization (Sirtex SIR-Spheres Pty Ltd.). The administered activity ranged from 1 to 1.3 GBq. Ten days before treatment, patients underwent a baseline 18 F-FDG PET/CT. The determination of the 90 Y-microsphere activity to administer for treatment was based on the BSA method refined with the partition model derived from a 99m Tc-MAA SPECT/CT performed a week prior to radio-embolization. Within 24 hours after treatment, 90 Y TOF PET/CT imaging was performed. A follow-up 18 F-FDG PET/CT was performed 1 month after the treatment to evaluate the response to radio-embolization. For each patient, 3D voxelized dose-maps were obtained from the post-treatment 90 Y TOF PET/CT. A volume of interest (VOI) was drawn for each selected hepatic lesion using the baseline 18 F-FDG PET/CT. To obtain dose-volume histogram (DVH) for each lesion, image co-registration and VOI masks were generated using the PMOD 3.4 software and then exported in Matlab for dose calculation. Furthermore, the average absorbed dose in lesions was corrected for PVE effects by multiplication for appropriate (phantom-based) recovery coefficients according to the lesion size. Early metabolic lesion response was assessed in terms of variation in the maximum standard uptake value (ΔSUVmax) between baseline and follow-up 18 F-FDG PET/CT. The average absorbed dose for each lesion was associated with the respective metabolic response. Results: for the 12 selected lesions, the average volume was 35 cm 3

Ambient neutron dose equivalent outside concrete vault rooms for 15 and 18 MV radiotherapy accelerators

International Nuclear Information System (INIS)

Martinez-ovalle, S. A.; Barquero, R.; Gomez-ros, J. M.; Lallena, A. M.

2012-01-01

In this work, the ambient dose equivalent, H*(10), due to neutrons outside three bunkers that house a 15- and a 18-MV Varian Clinac 2100C/D and a 15-MV Elekta Inor clinical linacs, has been calculated. The Monte Carlo code MCNPX (v. 2.5) has been used to simulate the neutron production and transport. The complete geometries including linacs and full installations have been built up according to the specifications of the manufacturers and the planes provided by the corresponding medical physical services of the hospitals where the three linacs operate. Two of these installations, those lodging the Varian linacs, have an entrance door to the bunker while the other one does not, although it has a maze with two bends. Various treatment orientations were simulated in order to establish plausible annual equivalent doses. Specifically anterior-posterior, posterior-anterior, left lateral, right lateral orientations and an additional one with the gantry rotated 30 deg. have been studied. Significant dose rates have been found only behind the walls and the door of the bunker, near the entrance and the console, with a maximum of 12 μSv h -1 . Dose rates per year have been calculated assuming a conservative workload for the three facilities. The higher dose rates in the corresponding control areas were 799 μSv y -1 , in the case of the facility which operates the 15-MV Clinac, 159 μSv y -1 , for that with the 15-MV Elekta, and 21 μSv y -1 for the facility housing the 18-MV Varian. A comparison with measurements performed in similar installations has been carried out and a reasonable agreement has been found. The results obtained indicate that the neutron contamination does not increase the doses above the legal limits and does not produce a significant enhancement of the dose equivalent calculated. When doses are below the detection limits provided by the measuring devices available today, MCNPX simulation provides an useful method to evaluate neutron dose equivalents

Skin dose variation: influence of energy

International Nuclear Information System (INIS)

Cheung, T.; Yu, P.K.N.; Butson, M.J.; Cancer Services, Wollongong, NSW

2004-01-01

Full text: This research aimed to quantitatively evaluate the differences in percentage dose of maximum for 6MV and 18MV x-ray beams within the first lcm of interactions. Thus provide quantitative information regarding the basal, dermal and subcutaneous dose differences achievable with these two types of high-energy x-ray beams. Percentage dose of maximum build up curves are measured for most clinical field sizes using 6MV and 18MV x-ray beams. Calculations are performed to produce quantitative results highlighting the percentage dose of maximum differences delivered to various depths within the skin and subcutaneous tissue region by these two beams Results have shown that basal cell layer doses are not significantly different for 6MV and 18Mv x-ray beams At depths beyond the surface and basal cell layer there is a measurable and significant difference in delivered dose. This variation increases to 20% of maximum and 22% of maximum at Imm and 1cm depths respectively. The percentage variations are larger for smaller field sizes where the photon in phantom component of the delivered dose is the most significant contributor to dose By producing graphs or tables of % dose differences in the build up region we can provide quantitative information to the oncologist for consideration (if skin and subcutaneous tissue doses are of importance) during the beam energy selection process for treatment. Copyright (2004) Australasian College of Physical Scientists and Engineers in Medicine

Dose mapping simulation using the MCNP code for the Syrian gamma irradiation facility and benchmarking

International Nuclear Information System (INIS)

Khattab, K.; Boush, M.; Alkassiri, H.

2013-01-01

Highlights: • The MCNP4C was used to calculate the gamma ray dose rate spatial distribution in for the SGIF. • Measurement of the gamma ray dose rate spatial distribution using the Chlorobenzene dosimeter was conducted as well. • Good agreements were noticed between the calculated and measured results. • The maximum relative differences were less than 7%, 4% and 4% in the x, y and z directions respectively. - Abstract: A three dimensional model for the Syrian gamma irradiation facility (SGIF) is developed in this paper to calculate the gamma ray dose rate spatial distribution in the irradiation room at the 60 Co source board using the MCNP-4C code. Measurement of the gamma ray dose rate spatial distribution using the Chlorobenzene dosimeter is conducted as well to compare the calculated and measured results. Good agreements are noticed between the calculated and measured results with maximum relative differences less than 7%, 4% and 4% in the x, y and z directions respectively. This agreement indicates that the established model is an accurate representation of the SGIF and can be used in the future to make the calculation design for a new irradiation facility

Dosimetric systems of high dose, dose rate and dose uniformity in food and medical products

International Nuclear Information System (INIS)

Vargas, J.; Vivanco, M.; Castro, E.

2014-08-01

In the Instituto Peruano de Energia Nuclear (IPEN) we use the chemical dosimetry Astm-E-1026 Fricke as a standard dosimetric system of reference and different routine dosimetric systems of high doses, according to the applied doses to obtain the desired effects in the treated products and the doses range determined for each type of dosimeter. Fricke dosimetry is a chemical dosimeter in aqueous solution indicating the absorbed dose by means an increase in absorbance at a specific wavelength. A calibrated spectrophotometer with controlled temperature is used to measure absorbance. The adsorbed dose range should cover from 20 to 400 Gy, the Fricke solution is extremely sensitive to organic impurities, to traces of metal ions, in preparing chemical products of reactive grade must be used and the water purity is very important. Using the referential standard dosimetric system Fricke, was determined to March 5, 2013, using the referential standard dosimetric system Astm-1026 Fricke, were irradiated in triplicate Fricke dosimeters, to 5 irradiation times (20; 30; 40; 50 and 60 seconds) and by linear regression, the dose rate of 5.400648 kGy /h was determined in the central point of the irradiation chamber (irradiator Gamma cell 220 Excel), applying the decay formula, was compared with the obtained results by manufacturers by means the same dosimetric system in the year of its manufacture, being this to the date 5.44691 kGy /h, with an error rate of 0.85. After considering that the dosimetric solution responds to the results, we proceeded to the irradiation of a sample of 200 g of cereal instant food, 2 dosimeters were placed at the lateral ends of the central position to maximum dose and 2 dosimeters in upper and lower ends as minimum dose, they were applied same irradiation times; for statistical analysis, the maximum dose rate was 6.1006 kGy /h and the minimum dose rate of 5.2185 kGy /h; with a dose uniformity of 1.16. In medical material of micro pulverized bone for

Main clinical, therapeutic and technical factors related to patient's maximum skin dose in interventional cardiology procedures

Science.gov (United States)

Journy, N; Sinno-Tellier, S; Maccia, C; Le Tertre, A; Pirard, P; Pagès, P; Eilstein, D; Donadieu, J; Bar, O

2012-01-01

Objective The study aimed to characterise the factors related to the X-ray dose delivered to the patient's skin during interventional cardiology procedures. Methods We studied 177 coronary angiographies (CAs) and/or percutaneous transluminal coronary angioplasties (PTCAs) carried out in a French clinic on the same radiography table. The clinical and therapeutic characteristics, and the technical parameters of the procedures, were collected. The dose area product (DAP) and the maximum skin dose (MSD) were measured by an ionisation chamber (Diamentor; Philips, Amsterdam, The Netherlands) and radiosensitive film (Gafchromic; International Specialty Products Advanced Materials Group, Wayne, NJ). Multivariate analyses were used to assess the effects of the factors of interest on dose. Results The mean MSD and DAP were respectively 389 mGy and 65 Gy cm−2 for CAs, and 916 mGy and 69 Gy cm−2 for PTCAs. For 8% of the procedures, the MSD exceeded 2 Gy. Although a linear relationship between the MSD and the DAP was observed for CAs (r=0.93), a simple extrapolation of such a model to PTCAs would lead to an inadequate assessment of the risk, especially for the highest dose values. For PTCAs, the body mass index, the therapeutic complexity, the fluoroscopy time and the number of cine frames were independent explanatory factors of the MSD, whoever the practitioner was. Moreover, the effect of technical factors such as collimation, cinematography settings and X-ray tube orientations on the DAP was shown. Conclusion Optimising the technical options for interventional procedures and training staff on radiation protection might notably reduce the dose and ultimately avoid patient skin lesions. PMID:22457404

Comparison of radiation doses between newborns and 6-y-old children undergoing head, chest and abdominal CT examinations-A phantom study

International Nuclear Information System (INIS)

Sugimoto, N.; Aoyama, T.; Koyama, S.; Yamauchi-Kawaura, C.; Fujii, K.

2013-01-01

Radiation doses in paediatric computed tomography (CT) were investigated for various types of recent CT scanners with newborn and 6-y-old phantoms in which silicon-photodiode dosemeters were implanted at various organ positions. In the head, chest and abdominal CT for the newborn phantom, doses for organs within the scan region were 21-40, 3-8 and 3-12 mGy, respectively. The corresponding doses for the child phantom were 20-37, 2-11 and 4-17 mGy, respectively. In the head, chest and abdominal CT, the effective doses were respectively 2.1-3.3, 2.0-6.0 and 2.2-10.0 mSv for the newborn, and 1.0-2.0, 1.2-6.6 and 2.9-11.8 mSv for the child. Radiation doses for the newborn were at the same levels as those for the child, excepting effective doses in head CT for the newborn, which were 1.8 times higher than those for the child. (authors)

Maximum distance between the Leader and the Laggard for three Brownian walkers

International Nuclear Information System (INIS)

Majumdar, Satya N; Bray, Alan J

2010-01-01

We consider three independent Brownian walkers moving on a line. The process terminates when the leftmost walker (the 'Leader') meets either of the other two walkers. For arbitrary values of the diffusion constants D 1 (the Leader), D 2 and D 3 of the three walkers, we compute the probability distribution P(m|y 2 , y 3 ) of the maximum distance m between the Leader and the current rightmost particle (the 'Laggard') during the process, where y 2 and y 3 are the initial distances between the Leader and the other two walkers. The result has, for large m, the form P(m|y 2 , y 3 ) ∼ A(y 2 , y 3 )m −δ , where δ = (2π − θ)/(π − θ) and θ= cos -1 (D 1 /√((D 1 +D 2 )(D 1 +D 3 ))). The amplitude A(y 2 , y 3 ) is also determined exactly

Determination of Radiation Absorbed Dose to Primary Liver Tumors and Normal Liver Tissue Using Post Radioembolization 90Y PET

Directory of Open Access Journals (Sweden)

Shyam Mohan Srinivas

2014-10-01

Full Text Available Background: Radioembolization with Yttrium-90 (90Y microspheres is becoming a more widely used transcatheter treatment for unresectable hepatocellular carcinoma (HCC. Using post-treatment 90Y PET/CT scans,the distribution of microspheres within the liver can be determined and quantitatively assessesed . We studied the radiation dose of 90Y delivered to liver and treated tumors.Methods: This retrospective study of 56 patients with HCC, including analysis of 98 liver tumors, measured and correlated the dose of radiation delivered to liver tumors and normal liver tissue using glass microspheres (TheraSpheres® to the frequency of complications with mRECIST. 90Y PET/CT and triphasic liver CT scans were used to contour treated tumor and normal liver regions and determine their respective activity concentrations. An absorbed dose factor was used to convert the measured activity concentration (Bq/mL to an absorbed dose (Gy.Results: The 98 studied tumors received a mean dose of 169 Gy (mode 90-120 Gy;range 0-570 Gy. Tumor response by mRECIST criteria was performed for 48 tumors that had follow up scans. There were 21 responders (mean dose 215 Gy and 27 nonresponders (mean dose 167 Gy. The association between mean tumor absorbed dose and response suggests a trend but did not reach statistical significance (p=0.099. Normal liver tissue received a mean dose of 67 Gy (mode 60-70 Gy; range 10-120 Gy. There was a statistically significant association between absorbed dose to normal liver and the presence of two or more severe complications (p=0.036.Conclusion: Our cohort of patients showed a possible dose response trend for the tumors. Collateral dose to normal liver is nontrivial and can have clinical implications. These methods help us understand whether patient adverse events, treatment success, or treatment failure can be attributed to the dose which the tumor or normal liver received.

Performance evaluation of domestic prototype dose area product meter SFT-1

International Nuclear Information System (INIS)

Lee, Ho Sun; Han, Seong Gyu; Roh, Young Roh; Lim, Hyun Jong; Kim, Jung Min; Kim, Jong Uk; Chae, Hyun Sik; Yoon, Yong Su

2016-01-01

The importance of radiation dose display of medical X-ray equipment was emphasized, while third edition of IEC(International Electrotechnical Commission) 60601 started to apply. The existing medical X-ray equipment selected a method for attaching the DAP(Dose Area Product) meter when the dose display. However, because the DAP meter was dependent on all of the income, And it did not yet produced in Korea. So, we received the support of Seoul R and BD Program(Grants No. C1152055) to produce DAP meter prototype of the Domestically technology. In this study, the performance of this prototype was evaluated by comparing the German company's product. Evaluation item was an electronic capture performance, radiation dose dependence, radiation quality dependence, energy transmittance, repeatability, light transmittance of 6 entries. And IEC 60580 was based on this evaluation. Evaluation results were electronic capture performance intrinsic error 9.5%, radiation dose dependence limits of variation 1%, repeatabilit y coefficient of variation 2%, energy transmittance 91% each assessment was passed. However radiation quality dependence limits of variation 29%, light transmittance 55% was less than acceptance criteria

Luminescence properties of LiSr2Y1-xLnxO4 (Ln=Eu,Tb,Tm) (0≤x≤1)

International Nuclear Information System (INIS)

Kubota, S.; Suzuyama, Y.; Yamane, H.; Shimada, M.

1998-01-01

Investigations of the luminescence properties of LiSr 2 Y 1-x Eu x O 4 , LiSr 2 Y 1-x Tb x O 4 and LiSr 2 Y 1-x Tm x O 4 (0≤x≤1) at room temperature are reported. These samples were synthesized by a solid state reaction. The excitation spectra of Tb 3+ emission in LiSr 2 Y 1-x Tb x O 4 (0≤x≤1) consist of broad bands corresponding to a transition between the 4f 8 and 4f 7 5d 1 states of Tb 3+ . The maximum intensity is situated at about 318 nm. This is at a much longer wavelength than those of other Tb 3+ doped phosphors. This is explained by a large offset of the adiabatic potential curve of the 4f 7 5d 1 state. (orig.)

Phase 1 Dose Escalation Study of Accelerated Radiation Therapy With Concurrent Chemotherapy for Locally Advanced Lung Cancer

Energy Technology Data Exchange (ETDEWEB)

Kelsey, Chris R., E-mail: christopher.kelsey@duke.edu [Department of Radiation Oncology, Duke University Medical Center, Durham, North Carolina (United States); Das, Shiva [Department of Radiation Oncology, University of North Carolina School of Medicine, Chapel Hill, North Carolina (United States); Gu, Lin [Department of Biostatistics and Bioinformatics, Duke University Medical Center, Durham, North Carolina (United States); Dunphy, Frank R.; Ready, Neal E. [Division of Medical Oncology, Department of Medicine, Duke University Medical Center, Durham, North Carolina (United States); Marks, Lawrence B. [Department of Radiation Oncology, University of North Carolina School of Medicine, Chapel Hill, North Carolina (United States)

2015-12-01

Purpose: To determine the maximum tolerated dose of radiation therapy (RT) given in an accelerated fashion with concurrent chemotherapy using intensity modulated RT. Methods and Materials: Patients with locally advanced lung cancer (non-small cell and small cell) with good performance status and minimal weight loss received concurrent cisplatin and etoposide with RT. Intensity modulated RT with daily image guidance was used to facilitate esophageal avoidance and delivered using 6 fractions per week (twice daily on Fridays with a 6-hour interval). The dose was escalated from 58 Gy to a planned maximum dose of 74 Gy in 4 Gy increments in a standard 3 + 3 trial design. Dose-limiting toxicity (DLT) was defined as acute grade 3-5 nonhematologic toxicity attributed to RT. Results: A total of 24 patients were enrolled, filling all dose cohorts, all completing RT and chemotherapy as prescribed. Dose-limiting toxicity occurred in 1 patient at 58 Gy (grade 3 esophagitis) and 1 patient at 70 Gy (grade 3 esophageal fistula). Both patients with DLTs had large tumors (12 cm and 10 cm, respectively) adjacent to the esophagus. Three additional patients were enrolled at both dose cohorts without further DLT. In the final 74-Gy cohort, no DLTs were observed (0 of 6). Conclusions: Dose escalation and acceleration to 74 Gy with intensity modulated RT and concurrent chemotherapy was tolerable, with a low rate of grade ≥3 acute esophageal reactions.

SU-G-201-14: Is Maximum Skin Dose a Reliable Metric for Accelerated Partial Breast Irradiation with Brachytherapy?

International Nuclear Information System (INIS)

Park, S; Ragab, O; Patel, S; Demanes, J; Kamrava, M; Kim, Y

2016-01-01

Purpose: To evaluate the reliability of the maximum point dose (Dmax) to the skin surface as a dosimetric constraint, we investigated the correlation between Dmax at the skin surface and dose metrics at various definitions of skin thickness. Methods: 42 patients treated with APBI using a Strut Adjusted Volume Implant (SAVI) applicator between 2010 and 2014 were retrospectively reviewed. Target (PTV-EVAL) and organs at risk (OARs: skin, lung, and ribs) were delineated on a CT following NSABP B-39 guidelines. Six skin structures were contoured: a rind 3cm external to the body surface and 1, 2, 3, 4, and 5mm thick rinds deep to the body surface. Inverse planning simulated annealing optimization was used to deliver 32–34Gy in 8-10 fractions to the target while minimizing OAR doses. Dmax, D0.1cc, D1.0cc, and D2.0cc to the various skin structures were calculated. Linear regressions between the metrics were evaluated using the coefficient of determination (R"2). Results: The average±SD PTV-EVAL volume and cavity-to-skin distances were 71.1±28.5cc and 6.9±5.0mm. The target V90 and V95 were 97.3±2.3% and 95.1±3.2%. The Dmax to the skin structures were 78.7±10.2% (skin surface), 82.2±10.7% (skin-1mm), 89.4±12.6% (skin-2mm), 97.9±15.4% (skin-3mm), 114.1±32.5% (skin-4mm), and 157.0±85.3% (skin-5mm). Linear regression analysis showed D1.0cc and D2.0cc to the skin 1mm and Dmax to the skin-4mm and 5mm were poorly correlated with other metrics (R"2=0.413±0.204). Dmax to the skin surface was well correlated (R"2=0.910±0.047) and D1.0cc to the skin-3mm was strongly correlated with all subsurface skin layers (R"2=0.935±0.050). Conclusion: Dmax to the skin surface is a relevant metric for breast skin dose. Contouring discontinuities in the skin with a 1mm subsurface rind and the active dwells in the skin 4 and 5mm introduced significant variations in skin DVH. D0.1cc, D1.0cc, and D2.0cc to a 3mm skin rind are more robust metrics in breast brachytherapy.

Influence of radiation-dose pattern from inhaled beta--gamma-emitting radionuclides on canine peripheral lymphocytes

International Nuclear Information System (INIS)

Jones, R.K.; Boecker, B.B.; Pickrell, J.A.; Hobbs, C.H.; McClellan, R.O.

1976-01-01

As part of studies assess the biological hazards associated with inhaled radionuclides, periodic hematologic evaluations were performed on beagle dogs given a single nose-only exposure to aerosols of beta--gamma-emitting isotopes. The physical form and specific radionuclides selected produced radiation-dose patterns representative of those which might be encountered in the event of human accidental exposures. Dogs received graded lung burdens of either 90 Y, 91 Y, 144 Ce, or 90 Sr, each in fused clay. Differences in the effective half-lives of these radionuclides resulted in a spectrum of cumulative radiation doses to lung delivered at a variety of dose rates. Since the form in which the radionuclides were inhaled was relatively insoluble, the lung and intrathoracic tissues represented the primary recipient of the dose. Regardless of the effective half-life of radionuclide retention, a dose-related depression of peripheral lymphocytes was observed at various times after inhalation exposure. The time at which maximum depression and subsequent recovery occurred, however, was most directly related to the effective half-life of the radionuclide. Of special interest was the persistence of lymphopenia through 2 1 / 2 years after exposure to 144 Ce and 90 Sr in fused clay where, other than tracheobronchial lymph nodes, the lymphoid tissue received very little radiation dose. The possible mechanisms responsible for lymphocyte depression from these various radiation-dose patterns are discussed

Human cytogenetic dosimetry: a dose-response relationship for alpha particle radiation from 241Am

International Nuclear Information System (INIS)

DuFrain, R.J.; Littlefield, L.G.; Joiner, E.E.; Frome, E.L.

1979-01-01

Cytogenetic dosimetry estimates to guide treatment of persons internally contaminated with transuranic elements have not previously been possible because appropriate in vitro dose-response curves specifically for alpha particle irradiation of human lymphocytes do not exist. Using well-controlled cytogenetic methods for human lymphocyte culture, an experimentally derived dose-response curve for 241 Am alpha particle (5.49 and 5.44 MeV) radiation of G 0 lymphocytes was generated. Cells were exposed to 43.8, 87.7, 175.3 or 350.6 nCi/ml 241 Am for 1.7 hr giving doses of 0.85, 1.71, 3.42 or 6.84 rad. Based on dicentric chromosome yield, the linear dose-response equation is Y = 4.90(+-0.42) x 10 -2 X, with Y given as dicentrics per cell and X as dose in rads. The study also shows that the two-break asymmetrical exchanges in cells damaged by alpha particle radiation are overdispersed when compared to a Poisson distribution. An example is presented to show how the derived dose-response equation can be used to estimate the radiation dose for a person internally contaminated with an actinide. An experimentally derived RBE value of 118 at 0.85 rad is calculated for the efficiency of 241 Am alpha particle induction of dicentric chromosomes in human G 0 lymphocytes as compared with the efficiency of 60 Co gamma radiation. The maximum theoretical value for the RBE for cytogenetic damage from alpha irradiation was determined to be 278 at 0.1 rad or less which is in marked contrast to previously reported RBE values of approx. 20. (author)

Radiation dose in dental radiology

International Nuclear Information System (INIS)

Cohnen, M.; Kemper, J.; Moedder, U.; Moebes, O.; Pawelzik, J.

2002-01-01

The aim of this study was to compare radiation exposure in panoramic radiography (PR), dental CT, and digital volume tomography (DVT). An anthropomorphic Alderson-Rando phantom and two anatomical head phantoms with thermoluminescent dosimeters fixed at appropriate locations were exposed as in a dental examination. In PR and DVT, standard parameters were used while variables in CT included mA, pitch, and rotation time. Image noise was assessed in dental CT and DVT. Radiation doses to the skin and internal organs within the primary beam and resulting from scatter radiation were measured and expressed as maximum doses in mGy. For PR, DVT, and CT, these maximum doses were 0.65, 4.2, and 23 mGy. In dose-reduced CT protocols, radiation doses ranged from 10.9 to 6.1 mGy. Effective doses calculated on this basis showed values below 0.1 mSv for PR, DVT, and dose-reduced CT. Image noise was similar in DVT and low-dose CT. As radiation exposure and image noise of DVT is similar to low-dose CT, this imaging technique cannot be recommended as a general alternative to replace PR in dental radiology. (orig.)

Possible involvement of neuropeptide Y Y1 receptors in antidepressant like effect of agmatine in rats.

Science.gov (United States)

Kotagale, Nandkishor R; Paliwal, Nikhilesh P; Aglawe, Manish M; Umekar, Milind J; Taksande, Brijesh G

2013-09-01

Agmatine and neuropeptide Y (NPY) are widely distributed in central nervous system and critically involved in modulation of depressive behavior in experimental animals. However their mutual interaction, if any, in regulation of depression remain largely unexplored. In the present study we explored the possible interaction between agmatine and neuropeptide Y in regulation of depression like behavior in forced swim test. We found that acute intracerebroventricular (i.c.v.) administration of agmatine (20-40μg/rat), NPY (5 and 10μg/rat) and NPY Y1 receptor agonist, [Leu(31), Pro(34)]-NPY (0.4 and 0.8ng/rat) dose dependently decreased immobility time in forced swim test indicating their antidepressant like effects. In combination studies, the antidepressant like effect of agmatine (10μg/rat) was significantly potentiated by NPY (1 and 5μg/rat, icv) or [Leu(31), Pro(34)]-NPY (0.2 and 0.4ng/rat, icv) pretreatment. Conversely, pretreatment of animals with NPY Y1 receptor antagonist, BIBP3226 (0.1ng/rat, i.c.v.) completely blocked the antidepressant like effect of agmatine (20-40μg/rat) and its synergistic effect with NPY (1μg/rat, icv) or [Leu(31), Pro(34)]-NPY (0.2ng/rat, icv). The results of the present study showed that, agmatine exerts antidepressant like effects via NPYergic system possibly mediated by the NPY Y1 receptor subtypes and suggest that interaction between agmatine and neuropeptide Y may be relevant to generate the therapeutic strategies for the treatment of depression. Copyright © 2013 Elsevier Inc. All rights reserved.

Methods for Estimation of Radiation Risk in Epidemiological Studies Accounting for Classical and Berkson Errors in Doses

KAUST Repository

Kukush, Alexander

2011-01-16

With a binary response Y, the dose-response model under consideration is logistic in flavor with pr(Y=1 | D) = R (1+R)(-1), R = λ(0) + EAR D, where λ(0) is the baseline incidence rate and EAR is the excess absolute risk per gray. The calculated thyroid dose of a person i is expressed as Dimes=fiQi(mes)/Mi(mes). Here, Qi(mes) is the measured content of radioiodine in the thyroid gland of person i at time t(mes), Mi(mes) is the estimate of the thyroid mass, and f(i) is the normalizing multiplier. The Q(i) and M(i) are measured with multiplicative errors Vi(Q) and ViM, so that Qi(mes)=Qi(tr)Vi(Q) (this is classical measurement error model) and Mi(tr)=Mi(mes)Vi(M) (this is Berkson measurement error model). Here, Qi(tr) is the true content of radioactivity in the thyroid gland, and Mi(tr) is the true value of the thyroid mass. The error in f(i) is much smaller than the errors in ( Qi(mes), Mi(mes)) and ignored in the analysis. By means of Parametric Full Maximum Likelihood and Regression Calibration (under the assumption that the data set of true doses has lognormal distribution), Nonparametric Full Maximum Likelihood, Nonparametric Regression Calibration, and by properly tuned SIMEX method we study the influence of measurement errors in thyroid dose on the estimates of λ(0) and EAR. The simulation study is presented based on a real sample from the epidemiological studies. The doses were reconstructed in the framework of the Ukrainian-American project on the investigation of Post-Chernobyl thyroid cancers in Ukraine, and the underlying subpolulation was artificially enlarged in order to increase the statistical power. The true risk parameters were given by the values to earlier epidemiological studies, and then the binary response was simulated according to the dose-response model.

Methods for estimation of radiation risk in epidemiological studies accounting for classical and Berkson errors in doses.

Science.gov (United States)

Kukush, Alexander; Shklyar, Sergiy; Masiuk, Sergii; Likhtarov, Illya; Kovgan, Lina; Carroll, Raymond J; Bouville, Andre

2011-02-16

With a binary response Y, the dose-response model under consideration is logistic in flavor with pr(Y=1 | D) = R (1+R)(-1), R = λ(0) + EAR D, where λ(0) is the baseline incidence rate and EAR is the excess absolute risk per gray. The calculated thyroid dose of a person i is expressed as Dimes=fiQi(mes)/Mi(mes). Here, Qi(mes) is the measured content of radioiodine in the thyroid gland of person i at time t(mes), Mi(mes) is the estimate of the thyroid mass, and f(i) is the normalizing multiplier. The Q(i) and M(i) are measured with multiplicative errors Vi(Q) and ViM, so that Qi(mes)=Qi(tr)Vi(Q) (this is classical measurement error model) and Mi(tr)=Mi(mes)Vi(M) (this is Berkson measurement error model). Here, Qi(tr) is the true content of radioactivity in the thyroid gland, and Mi(tr) is the true value of the thyroid mass. The error in f(i) is much smaller than the errors in ( Qi(mes), Mi(mes)) and ignored in the analysis. By means of Parametric Full Maximum Likelihood and Regression Calibration (under the assumption that the data set of true doses has lognormal distribution), Nonparametric Full Maximum Likelihood, Nonparametric Regression Calibration, and by properly tuned SIMEX method we study the influence of measurement errors in thyroid dose on the estimates of λ(0) and EAR. The simulation study is presented based on a real sample from the epidemiological studies. The doses were reconstructed in the framework of the Ukrainian-American project on the investigation of Post-Chernobyl thyroid cancers in Ukraine, and the underlying subpolulation was artificially enlarged in order to increase the statistical power. The true risk parameters were given by the values to earlier epidemiological studies, and then the binary response was simulated according to the dose-response model.

Structural and intrinsic Josephson properties of Bi{sub 2}Sr{sub 2}Ca{sub 1−y}Y{sub y}Cu{sub 2}O{sub 8+δ} single crystal

Energy Technology Data Exchange (ETDEWEB)

Yamaki, K., E-mail: kyamaki@cc.utsunomiya-u.ac.jp; Murata, K.; Irie, A.

2016-10-15

Highlights: • Single crystals of yttrium-doped BSCCO (BSCYCO) were grown by a self-flux method. • T{sub c} and c-axis lattice constant of BSCYCO were controlled by the substitution of Y. • A multibranch structure was observed up to y = 0.10 (Bi{sub 2}Sr{sub 2}Ca{sub 1−y}Y{sub y}Cu{sub 2}O{sub 8+δ}). • The BSCYCO mesa has higher maximum voltage compared with nondoped BSCCO. - Abstract: In this study, Bi{sub 2}Sr{sub 2}Ca{sub 1−y}Y{sub y}Cu{sub 2}O{sub 8+δ} (BSCYCO) single crystals with yttrium doping content of y = 0–0.30 were synthesized by a self-flux method. The critical temperature and c-axis lattice constant of BSCYCO were controlled by the substitution of yttrium at the calcium site. A 290 × 90 × 0.4 µm{sup 3} mesa structure was fabricated using photolithography and argon-ion milling. A multibranch structure in current–voltage characteristics was successfully observed for mesas of BSCYCO (y = 0–0.10). The critical current of intrinsic Josephson junctions (IJJs) in BSCYCO mesas was systematically investigated.

An updated dose assessment for a U.S. Nuclear Test Site - Bikini Atoll

International Nuclear Information System (INIS)

Robison, W.L.; Bogen, K.T.; Conrado, C.L.

1995-10-01

On March 1, 1954, a nuclear weapon test, code-named BRAVO, conducted at Bikini Atoll in the northern Marshall Islands contaminated the major residence island. There has been a continuing effort since 1977 to refine dose assessments for resettlement options at Bikini Atoll. Here we provide a radiological dose assessment for the main residence island, Bikini, using extensive radionuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island as part of our continuing research and monitoring program that began in 1975. The unique composition of coral soil greatly alters the relative contribution of cesium-137 ( 137 Cs) and strontium-90 ( 90 Sr) to the total estimated dose relative to expectations based on North American and European soils. Without counter measures, cesium-137 produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The doses are calculated assuming a resettlement date of 1999. The estimated maximum annual effective dose for current island conditions is 4.0 mSv when imported foods, which are now an established part of the diet, are available. The corresponding 30-, 50-, and 70-y integral effective doses are 9.1 cSv, 13 cSv, and 15 cSv, respectively. A corresponding uncertainty analysis showed that after about 5 y of residence, the 95% confidence limits on population-average dose would be ±35% of its expected value. We have evaluated various countermeasures to reduce 137 Cs in food crops. Treatment with potassium reduces the uptake of 137 Cs into food crops, and therefore the ingestion dose, to about 5% of pretreatment levels and has essentially no negative environmental consequences

Utilization of a novel electrochemical {sup 90}Sr/{sup 90}Y generator for the preparation of {sup 90}Y-labeled RGD peptide dimer in clinically relevant dose

Energy Technology Data Exchange (ETDEWEB)

Chakraborty, Sudipta; Chakravarty, Rubel; Pillai, Maroor Raghavan Ambikalmajan; Dash, Ashutosh [Bhabha Atomic Research Centre, Mumbai (India). Radiopharmaceuticals Div.; Sarma, Haladhar Dev [Bhabha Atomic Research Centre, Mumbai (India). Radiation Biology and Health Sciences Div.

2014-09-01

The work reported in this paper provides a systematic study towards the development of an optimized strategy for preparation of a clinically relevant dose of {sup 90}Y-labeled dimeric RGD peptide derivative, DOTA-E[c(RGDfK)]{sub 2} [DOTA-(RGD){sub 2}] for in vivo targeted therapy utilizing {sup 90}Y obtained from a novel electrochemical {sup 90}Sr/{sup 90}Y generator. The performance of the generator was evaluated to ensure its suitability for providing {sup 90}Y in adequate quantity and purity required for formulation of clinically relevant dose for PRRT. {sup 90}Y-DOTA-(RGD){sub 2} was synthesized in high yield (86.2 ± 2.5%) and radiochemical purity (98.4 ± 0.5%) using clinically relevant dose (∝ 3.8 GBq) of {sup 90}Y. In vitro stability studies revealed that the radiolabeled conjugate retained its radiochemical purity in normal saline and human serum. Preliminary biodistribution studies carried out in C57/BL6 mice bearing melanoma tumors showed that the preparation exhibited significant tumor uptake (5.30 ± 0.78% of injected activity at 30 min post-injection) with good tumor to background ratio. The optimized radiolabeling protocol seems to be an attractive strategy which is largely viewed as a springboard to realize scope of developing {sup 90}Y labeled cyclic RGD peptides for targeted therapy of tumors over-expressing integrin-α{sub ν}β{sub 3} receptors. (orig.)

IDEAL-CRT: A Phase 1/2 Trial of Isotoxic Dose-Escalated Radiation Therapy and Concurrent Chemotherapy in Patients With Stage II/III Non-Small Cell Lung Cancer

Energy Technology Data Exchange (ETDEWEB)

Landau, David B., E-mail: david.landau@kcl.ac.uk [Guy' s & St. Thomas' NHS Trust, King' s College London, London (United Kingdom); Hughes, Laura [Cancer Research UK and UCL Cancer Trials Centre, London (United Kingdom); Baker, Angela [Clatterbridge Cancer Centre, Bebington (United Kingdom); Bates, Andrew T. [Southampton General Hospital, Southampton (United Kingdom); Bayne, Michael C. [Poole Hospital, Poole (United Kingdom); Counsell, Nicholas [Cancer Research UK and UCL Cancer Trials Centre, London (United Kingdom); Garcia-Alonso, Angel [North Wales Cancer Centre, Rhyl (United Kingdom); Harden, Susan V. [Addenbrookes Hospital, Cambridge (United Kingdom); Hicks, Jonathan D. [Beatson West of Scotland Cancer Centre, Glasgow (United Kingdom); Hughes, Simon R. [Guy' s & St. Thomas' NHS Trust, King' s College London, London (United Kingdom); Illsley, Marianne C. [Royal Surrey County Hospital, Guilford (United Kingdom); Khan, Iftekhar [Cancer Research UK and UCL Cancer Trials Centre, London (United Kingdom); Laurence, Virginia [Poole Hospital, Poole (United Kingdom); Malik, Zafar; Mayles, Helen; Mayles, William Philip M. [Clatterbridge Cancer Centre, Bebington (United Kingdom); Miles, Elizabeth [Mount Vernon Hospital, Middlesex (United Kingdom); Mohammed, Nazia [Beatson West of Scotland Cancer Centre, Glasgow (United Kingdom); Ngai, Yenting [Cancer Research UK and UCL Cancer Trials Centre, London (United Kingdom); Parsons, Emma [Mount Vernon Hospital, Middlesex (United Kingdom); and others

2016-08-01

Purpose: To report toxicity and early survival data for IDEAL-CRT, a trial of dose-escalated concurrent chemoradiotherapy (CRT) for non-small cell lung cancer. Patients and Methods: Patients received tumor doses of 63 to 73 Gy in 30 once-daily fractions over 6 weeks with 2 concurrent cycles of cisplatin and vinorelbine. They were assigned to 1 of 2 groups according to esophageal dose. In group 1, tumor doses were determined by an experimental constraint on maximum esophageal dose, which was escalated following a 6 + 6 design from 65 Gy through 68 Gy to 71 Gy, allowing an esophageal maximum tolerated dose to be determined from early and late toxicities. Tumor doses for group 2 patients were determined by other tissue constraints, often lung. Overall survival, progression-free survival, tumor response, and toxicity were evaluated for both groups combined. Results: Eight centers recruited 84 patients: 13, 12, and 10, respectively, in the 65-Gy, 68-Gy, and 71-Gy cohorts of group 1; and 49 in group 2. The mean prescribed tumor dose was 67.7 Gy. Five grade 3 esophagitis and 3 grade 3 pneumonitis events were observed across both groups. After 1 fatal esophageal perforation in the 71-Gy cohort, 68 Gy was declared the esophageal maximum tolerated dose. With a median follow-up of 35 months, median overall survival was 36.9 months, and overall survival and progression-free survival were 87.8% and 72.0%, respectively, at 1 year and 68.0% and 48.5% at 2 years. Conclusions: IDEAL-CRT achieved significant treatment intensification with acceptable toxicity and promising survival. The isotoxic design allowed the esophageal maximum tolerated dose to be identified from relatively few patients.

Occupational dose assessment in interventional cardiology in Serbia

International Nuclear Information System (INIS)

Kaljevic, J.; Ciraj-Bjelac, O.; Stankovic, J.; Arandjic, D.; Bozovic, P.; Antic, V.

2016-01-01

The objective of this work is to assess the occupational dose in interventional cardiology in a large hospital in Belgrade, Serbia. A double-dosimetry method was applied for the estimation of whole-body dose, using thermoluminescent dosemeters, calibrated in terms of the personal dose equivalent H p (10). Besides the double-dosimetry method, eye dose was also estimated by means of measuring ambient dose equivalent, H*(10), and doses per procedure were reported. Doses were assessed for 13 physicians, 6 nurses and 10 radiographers, for 2 consequent years. The maximum annual effective dose assessed was 4.3, 2.1 and 1.3 mSv for physicians, nurses and radiographers, respectively. The maximum doses recorded by the dosemeter worn at the collar level (over the apron) were 16.8, 11.9 and 4.5 mSv, respectively. This value was used for the eye lens dose assessment. Estimated doses are in accordance with or higher than annual dose limits for the occupational exposure. (authors)

Influence of variations in dose and dose rates on biological effects of inhaled beta-emitting radionuclides

International Nuclear Information System (INIS)

McClellan, R.O.; Benjamin, S.A.; Boecker, B.B.; Hahn, F.F.; Hobbs, C.H.; Jones, R.K.; Lundgren, D.L.

1976-01-01

The biological effects of inhaled β-emitting radionuclides, 90 Y, 91 Y, 144 Ce and 90 Sr, are being investigated in beagle dogs that received single acute exposures at 12 to 14 months of age. The aerosols studied have included 91 YC1 3 , 144 CeC1 3 , 90 SrC1 2 , and 90 Y, 91 Y, 144 Ce or 90 Sr in aluminosilicate particles. Thus, 91 YCl 3 , 144 CeCl 3 and the aluminosilicate containing radionuclide particles all resulted in significant exposures to lung; 91 YC1 3 , 144 CeC1 3 an 90 SrC1 2 resulted in significant exposures to bone; 91 YC1 3 and 144 CeC1 3 resulted in significant exposures to liver. The higher initial doserate exposures have been more effective than low dose-rate exposures on a per-rad basis in producing early effects. To date ( 144 CeO 2 , it was observed that, on a μCi initial lung burden per kilogram body weight basis, mice did not develop pulmonary tumours whereas beagle dogs did. To fid out the reason for this observation mice have been repeatedly exposed by inhalation to 144 CeO 2 to maintain lung burdens of 144 Ce that resulted in radiation dose rates similar to that observed in beagle dogs. Several of the repeatedly exposed mice developed malignant pulmonary tumours. Thus, with similar dose rates and cumulative doses to the lung, mice and dogs responded in a similar manner to chronic β radiation

Application of ICRP recommendations relevant to internal dose

International Nuclear Information System (INIS)

Cowser, K.E.; Snyder, W.S.; Struxness, E.G.

1969-01-01

The intent of this paper is to review several of the basic concepts of radiation protection (with emphasis on internal dose) currently recommended by the International Commission on radiological Protection (ICRP), to summarize the assumptions and methods used in the calculation of internal dose, and to illustrate by example the practical application of the pertinent guidelines. Two broad subject areas are considered: (1) standards of radiation protection and (2) bases of internal dose estimation. Topics discussed within the framework of radiation protection standards include maximum permissible dose, categories of radiation exposure, maximum permissible dose commitment, simultaneous internal and external exposure, multiple organ exposure, and size of the exposed group. Discussion of internal dose estimation is limited to selected items that include the body burden of radionuclides and the calculation of absorbed dose, the dose equivalent, the derivation of maximum permissible concentration (MPC), the relationship of stable element intake to the MPC, and short term and chronic exposure situations. (author)

Application of ICRP recommendations relevant to internal dose

Energy Technology Data Exchange (ETDEWEB)

Cowser, K E; Snyder, W S; Struxness, E G [Health Physics Division, Oak Ridge National Laboratory, Oak Ridge, TN (United States)

1969-07-01

The intent of this paper is to review several of the basic concepts of radiation protection (with emphasis on internal dose) currently recommended by the International Commission on radiological Protection (ICRP), to summarize the assumptions and methods used in the calculation of internal dose, and to illustrate by example the practical application of the pertinent guidelines. Two broad subject areas are considered: (1) standards of radiation protection and (2) bases of internal dose estimation. Topics discussed within the framework of radiation protection standards include maximum permissible dose, categories of radiation exposure, maximum permissible dose commitment, simultaneous internal and external exposure, multiple organ exposure, and size of the exposed group. Discussion of internal dose estimation is limited to selected items that include the body burden of radionuclides and the calculation of absorbed dose, the dose equivalent, the derivation of maximum permissible concentration (MPC), the relationship of stable element intake to the MPC, and short term and chronic exposure situations. (author)

Indoor gamma dose measurements in Gudalore (India) using TLD

International Nuclear Information System (INIS)

Sivakumar, R.; Selvasekarapandian, S.; Mugunthamanikandan, N.; Raghunath, V.M.

2002-01-01

Indoor gamma radiation dose rates were measured inside residential buildings in Gudalore using a CaSO 4 : Dy thermoluminescent dosimeter for 1 year . Significant seasonal variations are observed. The highest dose rate is observed during summer and the lowest in winter. The dose rates observed are between 77.9 and 229.3 nGy h -1 and may be attributed to the type of building materials used in the dwellings monitored. The calculated mean annual effective dose equivalent rates range between 477.6 μSv y -1 , for the inhabitants of mud houses to 1406.3 μSv y -1 , for those living in terrace houses made of cement and brick

Structure and magnetic properties of Gd{sub x}Y{sub 1−x}FeO{sub 3} obtained by mechanosynthesis

Energy Technology Data Exchange (ETDEWEB)

Bolarín-Miró, A.M. [Área Académica de Ciencias de la Tierra y Materiales, Universidad Autónoma del Estado de Hidalgo Mineral de la Reforma, Hidalgo 42184 (Mexico); Sánchez-De Jesús, F., E-mail: fsanchez@uaeh.edu.mx [Área Académica de Ciencias de la Tierra y Materiales, Universidad Autónoma del Estado de Hidalgo Mineral de la Reforma, Hidalgo 42184 (Mexico); Cortés-Escobedo, C.A. [Centro de Investigación e Innovación Tecnológica del IPN, Distrito Federal 02250 (Mexico); Valenzuela, R. [Depto. de Materiales Metálicos y Cerámicos, Instituto de Investigaciones en Materiales, Universidad Nacional Autónoma de México, México D.F. 04510 (Mexico); Ammar, S. [ITODYS, UMR 7086, Université de Paris-Diderot, 75250 Paris Cedex (France)

2014-02-15

Highlights: • Orthohombic GDxY1-xFeO3 was obtained by mechanosynthesis after 5 h of milling. • Mechanosynthesized GdxY1-xFeO3 show weak ferromagnetic behavior. • Mechanosynthesis promotes unexpected magnetic properties in GdxY1-xFeO3. • The maximum magnetization that was reached 7.7 emu/g for Gdo.75Y0.25FeO3. • For Gd0.5Y0.5FeO3, the magnetization decreases down to 2.1 emu/g. -- Abstract: Solid solutions of yttrium–gadolinium orthoferrites Gd{sub x}Y{sub 1−x}FeO{sub 3} (0 ⩽ x ⩽ 1) were prepared by high-energy ball milling. The aim of this work was to study the influence of the synthesis parameters on the crystal structure and the magnetic behavior of these solid solutions. The precursors, Fe{sub 2}O{sub 3}, Y{sub 2}O{sub 3} and Gd{sub 2}O{sub 3}, mixed in a stoichiometric ratio to obtain these orthoferrites, were milled for different times (up to 5 h). X-ray diffraction and Rietveld refinement were used to elucidate the phase transformation as a function of the milling time. Results showed the complete formation of orthoferrite with an orthorhombic structure (S.G. Pbnm) without any annealing after 5 h of milling for all of the compositions. The effect of the synthesis process and the x value on the crystal structure and the magnetic properties were also studied. All of the synthesized powders demonstrated weak ferromagnetic behavior. In particular, an increase in the maximum magnetization for all the compositions was found, with a maximum that reached 7.7 emu/g for Gd{sub 0.75}Y{sub 0.25}FeO{sub 3}. For Gd{sub 0.5}Y{sub 0.5}FeO{sub 3}, the magnetization decreases down to 2.1 emu/g. A small contamination of metallic Fe was confirmed through electron spin resonance experiments.

Absorbed dose calculation of the energy deposition close to bone, lung and soft tissue interfaces in molecular radiotherapy

International Nuclear Information System (INIS)

Fernandez, M.; Lassman, M.

2015-01-01

Full text of publication follows. Aim: for voxel-based dosimetry in molecular radiotherapy (MRT) based on tabulated voxel S-values these values are usually obtained only for soft tissue. In order to study the changes in the dose deposition patterns at interfaces between different materials we have performed Monte Carlo simulations. Methods: the deposited energy patterns were obtained using the Monte-Carlo radiation code MCNPX v2.7 for Lu 177 (medium-energy) and Y 90 (high-energy). The following interfaces were studied: soft tissue-bone and soft tissue-lungs. For this purpose a volume of soft tissue homogeneously filled with Lu 177 or Y 90 was simulated at the interface to 3 different volumes containing no activity: soft tissue, lungs and bone. The emission was considered to be isotropic. The dimensions were chosen to ensure that the energy deposited by all generated particles was scored. The materials were defined as recommended by ICPR46; the decay schemes of Eckerman and Endo were used. With these data the absorbed dose patterns normalized to the maximum absorbed dose in the source region (soft tissue) were calculated. Results: the absorbed dose fractions in the boundary with soft tissue, bone and lungs are 50%, 47% and 57%, respectively, for Lu 177 and 50%, 47% and 51% for Y 90 . The distances to the interface at which the absorbed fractions are at 0.1% are 1.0, 0.6 and 3.0 mm for Lu 177 and 7.0, 4.0 and 24 mm for Y 90 , for soft tissue, bone and lungs respectively. Conclusions: in MRT, the changes in the absorbed doses at interfaces between soft tissue and bone/lungs need to be considered for isotopes emitting high energy particles. (authors)

Measurement of dose speed absorbed in depth imparted by sources external secondary patterns of beta radiation. Part 1 Measurement of dose speed absorbed in the surface of soft fabric for isotopes of {sup 90}Sr/{sup 90}Y, {sup 147}Pm and {sup 204}TI; Medicion de rapidez de dosis absorbida en profundidad impartida por fuentes patrones secundarios de radiacion beta externos. Parte 1. Medicion de rapidez de dosis absorbida en la superficie de tejido blando para isotopos de {sup 90}Sr/{sup 90}Y, {sup 147}Pm y {sup 204}TI

Energy Technology Data Exchange (ETDEWEB)

Alvarez R, J T [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1993-01-15

The dose speed was measured absorbed for depth zero, (superficial) in soft equivalent fabric, for the secondary pattern{sup s} four sources of beta radiation, (Nr. 86): {sup 90}Sr/{sup 90}Y, (1850 MBq and 74 MBq respectively); {sup 147}Pm, (518 MBq) and {sup 204}TI, (18.5 MBq). The measurement is carried out to different distances of source-detecting separation, (11.0, 30.0 and 50.0 cm for the source of 1850 MBq, 30.0 cm for that of 74 MBq; 11.00 cm for the source of {sup 147}Pmand to contact for all the sources); maintaining the radiation sheaf aligned the one axis of symmetry of the detector, ({alpha} 0 degrees). The detector employed was a extrapolation chambers of variable electrodes and electrode fixed collector, (30 mm of diameter). In accordance with the principle of Bragg-Gray the volume of the chambers is varied and they register the variations of the current of collected ionization, correcting until for a maximum of thirteen correction factors that take into account the deviation to the suppositions that it establishes this principle. The certain values of the speed of superficial absorbed dose are in the following intervals: {sup 90}Sr/{sup 90}Y, (1850 MBq, 0.0, 11.0, 30.0 and 50.0 cm): 43.164 mGy S-t, 0.544 mGy s-1 ,0.075 mGy s{sup -1} and 0.027 mGy s{sup -1}, respectively, with a Global Analysis of the order of 1.17%, 1.17%, 1.14% and 1.66%, K J; {sup 90}Sr / {sup 90}Y, (74 MBq, 0.0 and 30 cm): 1.536 mGy s{sup -1} and 0.002 mGy s{sup -1}, with Global Analysis of 1.19.0% and 5.22%, (K = 1) respectively, for the {sup 147}Pm, (0.0 and 11.0 in the interval of: 0.36 {mu}Gy s{sup -1} and 0.43 {mu}Gy s{sup -1}, with one Global Analysis of 1 .42% and 4.28%, (K = 1), respectively; and finally for the {sup 204}TI, (0.0 cm) in the interval of 0.10 {mu}Gy s{sup -1} with a Global Analysis of 1.27%. He calculates of the Global Analysis one carries out of agreement with those recommendations of the BIPM. In all the cases of source-detecting arrangement with

Measurement of dose speed absorbed in depth imparted by sources external secondary patterns of beta radiation. Part 1 Measurement of dose speed absorbed in the surface of soft fabric for isotopes of {sup 90}Sr/{sup 90}Y, {sup 147}Pm and {sup 204}TI; Medicion de rapidez de dosis absorbida en profundidad impartida por fuentes patrones secundarios de radiacion beta externos. Parte 1. Medicion de rapidez de dosis absorbida en la superficie de tejido blando para isotopos de {sup 90}Sr/{sup 90}Y, {sup 147}Pm y {sup 204}TI

Energy Technology Data Exchange (ETDEWEB)

Alvarez R, J.T. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

1993-01-15

The dose speed was measured absorbed for depth zero, (superficial) in soft equivalent fabric, for the secondary pattern{sup s} four sources of beta radiation, (Nr. 86): {sup 90}Sr/{sup 90}Y, (1850 MBq and 74 MBq respectively); {sup 147}Pm, (518 MBq) and {sup 204}TI, (18.5 MBq). The measurement is carried out to different distances of source-detecting separation, (11.0, 30.0 and 50.0 cm for the source of 1850 MBq, 30.0 cm for that of 74 MBq; 11.00 cm for the source of {sup 147}Pmand to contact for all the sources); maintaining the radiation sheaf aligned the one axis of symmetry of the detector, ({alpha} 0 degrees). The detector employed was a extrapolation chambers of variable electrodes and electrode fixed collector, (30 mm of diameter). In accordance with the principle of Bragg-Gray the volume of the chambers is varied and they register the variations of the current of collected ionization, correcting until for a maximum of thirteen correction factors that take into account the deviation to the suppositions that it establishes this principle. The certain values of the speed of superficial absorbed dose are in the following intervals: {sup 90}Sr/{sup 90}Y, (1850 MBq, 0.0, 11.0, 30.0 and 50.0 cm): 43.164 mGy S-t, 0.544 mGy s-1 ,0.075 mGy s{sup -1} and 0.027 mGy s{sup -1}, respectively, with a Global Analysis of the order of 1.17%, 1.17%, 1.14% and 1.66%, K J; {sup 90}Sr / {sup 90}Y, (74 MBq, 0.0 and 30 cm): 1.536 mGy s{sup -1} and 0.002 mGy s{sup -1}, with Global Analysis of 1.19.0% and 5.22%, (K = 1) respectively, for the {sup 147}Pm, (0.0 and 11.0 in the interval of: 0.36 {mu}Gy s{sup -1} and 0.43 {mu}Gy s{sup -1}, with one Global Analysis of 1 .42% and 4.28%, (K = 1), respectively; and finally for the {sup 204}TI, (0.0 cm) in the interval of 0.10 {mu}Gy s{sup -1} with a Global Analysis of 1.27%. He calculates of the Global Analysis one carries out of agreement with those recommendations of the BIPM. In all the cases of source-detecting arrangement with

Safety, efficacy and pharmacokinetics of neratinib (HKI-272) in Japanese patients with advanced solid tumors: a Phase 1 dose-escalation study.

Science.gov (United States)

Ito, Yoshinori; Suenaga, Mitsukuni; Hatake, Kiyohiko; Takahashi, Shunji; Yokoyama, Masahiro; Onozawa, Yusuke; Yamazaki, Kentaro; Hironaka, Shuichi; Hashigami, Kiyoshi; Hasegawa, Hirotaka; Takenaka, Nobuko; Boku, Narikazu

2012-04-01

Neratinib (HKI-272), a potent, irreversible, small-molecule, orally administered, pan-ErbB inhibitor that blocks signal transduction via inhibition of three epidermal growth factor receptors [ErbB1, ErbB2 (Her2) and ErbB4], is being developed for the treatment of solid tumors, including breast cancer. This Phase 1 dose-escalation study assessed the safety, tolerability, maximum-tolerated dose, antitumor activity and pharmacokinetics of neratinib in Japanese patients with advanced solid tumors. Patients received neratinib 80, 160, 240 or 320 mg orally; each patient enrolled in only one dose cohort. Patients received a single dose in week 1, followed by daily continuous doses. Blood samples collected were on days 1 and 21 for pharmacokinetic analyses. Twenty-one patients were enrolled (3 breast cancer; 17 colorectal cancer; 1 gastric cancer). Neratinib-related adverse events (all grades) included diarrhea (20 patients), fatigue (14 patients), nausea and abdominal pain (9 patients each) and anorexia (8 patients). Grade ≥3 neratinib-related adverse events in two or more patients were diarrhea and anorexia (two patients each). Dose-limiting toxicities were diarrhea and anorexia (two patients, 320 mg dose). The maximum-tolerated dose and recommended dose was neratinib 240 mg once daily. Of 21 evaluable patients, 2 with breast cancer had partial response, 3 had stable disease ≥24 weeks, 7 had stable disease ≥16 weeks and 9 had progressive disease. Pharmacokinetic analyses indicated that neratinib exposures increased with dose. The safety, efficacy and pharmacokinetic profiles of neratinib are consistent with those reported for non-Japanese patients and warrant further investigation of neratinib in Japanese patients with solid tumors.

Risks and radiation doses due to residential radon in Germany

International Nuclear Information System (INIS)

Beck, T.R.

2017-01-01

The population-averaged risk rate and the annual average effective dose due to residential radon in Germany were calculated. The calculations were based on an epidemiological approach taking into account the age- and gender-specific lung cancer incidence rates for the German population and the excess relative risk of 0.16 per 100 Bq.m"-"3 for residential radon. In addition, the risk estimates adjusted for the smoking habits were determined. The population-averaged risk rate for the whole population was estimated with 4.1.10"-"5 y"-"1 (95% confidence interval (CI) 1.4.10"-"5 - 7.6.10"-"5 y"-"1). Residential radon causes a detriment per year of 3.3.10"-"5 y"-"1 (95% CI 1.1.10"-"5 - 6.0.10"-"5 y"-"1), which corresponds to an annual average effective dose of 0.6 mSv (95% CI 0.2-1.1 mSv). Annually, ∼3400 lung cancer incidences are attributed to residential radon. The results from the epidemiological approach exercised in this study are considerably lower than the effective dose, which would be obtained from the dose conversion coefficient calculated using biokinetic and dosimetric models. (author)

Electrical resistivity and thermopower of Y1-xPrxCo2 Compounds

International Nuclear Information System (INIS)

Uchima, K; Takaesu, Y; Teruya, A; Akamine, H; Kakihana, M; Tomori, K; Uejo, T; Nakamura, A; Hedo, M; Nakama, T; Yagasaki, K; Burkov, A T

2015-01-01

Electrical resistivity ρ and thermopower S of the pseudo-binary compounds of Y 1-x Pr x Co 2 have been measured in the temperature range between 2 and 300 K under magnetic fields up to 10 T, together with the pressure measurements of ρ and S in Y 0.4 Pr 0.6 Co 2 . The Curie temperature decreases with decreasing x, and vanishes at the critical composition x c ≈ 0.4, where the residual resistivity attains a maximum value. The Curie temperature and the residual resistivity of Y 0.4 Pr 0.6 Co 2 show the same pressure dependence as those of the heavy-rare-earth based compounds. These behaviors of ρ and S indicate the inhomogeneous distribution of the Co 3d magnetization. The magnetoresistance of the light-rare earth Y 1-x Pr x Co 2 system is negative in the whole range of x, except for x = 0 and 1, which is a characteristic behavior related with magnetic state and magnitude of the effective field acting on the Co 3d subsystem

EPR spectrum deconvolution and dose assessment of fossil tooth enamel using maximum likelihood common factor analysis

International Nuclear Information System (INIS)

Vanhaelewyn, G.; Callens, F.; Gruen, R.

2000-01-01

In order to determine the components which give rise to the EPR spectrum around g = 2 we have applied Maximum Likelihood Common Factor Analysis (MLCFA) on the EPR spectra of enamel sample 1126 which has previously been analysed by continuous wave and pulsed EPR as well as EPR microscopy. MLCFA yielded agreeing results on three sets of X-band spectra and the following components were identified: an orthorhombic component attributed to CO - 2 , an axial component CO 3- 3 , as well as four isotropic components, three of which could be attributed to SO - 2 , a tumbling CO - 2 and a central line of a dimethyl radical. The X-band results were confirmed by analysis of Q-band spectra where three additional isotropic lines were found, however, these three components could not be attributed to known radicals. The orthorhombic component was used to establish dose response curves for the assessment of the past radiation dose, D E . The results appear to be more reliable than those based on conventional peak-to-peak EPR intensity measurements or simple Gaussian deconvolution methods

An updated dose assessment for resettlement options at Bikini Atoll--a U.S. nuclear test site.

Science.gov (United States)

Robison, W L; Bogen, K T; Conrado, C L

1997-07-01

On 1 March 1954, a nuclear weapon test, code-named BRAVO, conducted at Bikini Atoll in the northern Marshall Islands contaminated the major residence island. There has been a continuing effort since 1977 to refine dose assessments for resettlement options at Bikini Atoll. Here we provide a radiological dose assessment for the main residence island, Bikini, using extensive radionuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island as part of our continuing research and monitoring program that began in 1978. The unique composition of coral soil greatly alters the relative contribution of 137Cs and 90Sr to the total estimated dose relative to expectations based on North American and European soils. Without counter measures, 137Cs produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The doses are calculated assuming a resettlement date of 1999. The estimated maximum annual effective dose for current island conditions is 4.0 mSv when imported foods, which are now an established part of the diet, are available. The 30-, 50-, and 70-y integral effective doses are 91 mSv, 130 mSv, and 150 mSv, respectively. A detailed uncertainty analysis for these dose estimates is presented in a companion paper in this issue. We have evaluated various countermeasures to reduce 137Cs in food crops. Treatment with potassium reduces the uptake of 137Cs into food crops, and therefore the ingestion dose, to about 5% of pretreatment levels and has essentially no negative environmental consequences. We have calculated the dose for the rehabilitation scenario where the top 40 cm of soil is removed in the housing and village area, and the rest of the island is treated with potassium fertilizer; the maximum annual effective dose is 0.41 mSv and the 30-, 50-, and 70-y

Pre-therapeutic dosimetry and biodistribution of {sup 86}Y-DOTA-Phe{sup 1}-Tyr{sup 3}-octreotide versus {sup 111}In-pentetreotide in patients with advanced neuroendocrine tumours

Energy Technology Data Exchange (ETDEWEB)

Helisch, Andreas; Foerster, Gregor J.; Reber, Helmut; Buchholz, Hans-Georg; Bartenstein, Peter [University of Mainz, Department of Nuclear Medicine, Mainz (Germany); Arnold, Rudolf [Philips University, Division of Gastroenterology and Endocrinology, Department of Internal Medicine, Marburg (Germany); Goeke, Burkhard [Ludwig-Maximilians-University, Department of Internal Medicine II, Klinikum Grosshadern, Munich (Germany); Weber, Matthias M. [University of Mainz, Division of Endocrinology and Metabolism, Department of Internal Medicine, Mainz (Germany); Wiedenmann, Bertram [Campus Virchow Clinic, Department of Hepatology and Gastroenterology, Charite Medical School, Berlin (Germany); Pauwels, Stanislas [Catholic University of Louvain, Center of Nuclear Medicine, Brussels (Belgium); Haus, Ulrike [Novartis Pharmaceuticals, Nuremberg (Germany); Bouterfa, Hakim [Novartis Pharmaceuticals, Basel (Switzerland)

2004-10-01

For the internal radiotherapy of neuroendocrine tumours, the somatostatin analogue DOTATOC labelled with {sup 90}Y is frequently used [{sup 90}Y-DOTA-Phe{sup 1}-Tyr{sup 3}-octreotide (SMT487-OctreoTher)]. Radiation exposure to the kidneys is critical in this therapy as it may result in renal failure. The aim of this study was to compare cumulative organ and tumour doses based upon dosimetric data acquired with the chemically identical {sup 86}Y-DOTA-Phe{sup 1}-Tyr{sup 3}-octreotide (considered as the gold standard) and the commercially available {sup 111}In-pentetreotide. The cumulative organ and tumour doses for the therapeutic administration of 13.32 GBq {sup 90}Y-DOTA-Phe{sup 1}-Tyr{sup 3}-octreotide (three cycles, each of 4.44 GBq) were estimated based on the MIRD concept (MIRDOSE 3.1 and IMEDOSE). Patients with a cumulative kidney dose exceeding 27 Gy had to be excluded from subsequent therapy with {sup 90}Y-DOTA-Phe{sup 1}-Tyr{sup 3}-octreotide, in accordance with the directives of the German radiation protection authorities. The range of doses (mGy/MBq {sup 90}Y-DOTA-Phe{sup 1}-Tyr{sup 3}-octreotide) for kidneys, spleen, liver and tumour masses was 0.6-2.8, 1.5-4.2, 0.3-1.3 and 2.1-29.5 ({sup 86}Y-DOTA-Phe{sup 1}-Tyr{sup 3}-octreotide), respectively, versus 1.3-3.0, 1.8-4.4, 0.2-0.8 and 1.4-19.7 ({sup 111}In-pentetreotide), with wide inter-subject variability. Despite renal protection with amino acid infusions, estimated cumulative kidney doses in two patients exceeded 27 Gy. Compared with {sup 86}Y-DOTA-Phe{sup 1}-Tyr{sup 3}-octreotide, dosimetry with {sup 111}In-pentetreotide overestimated doses to kidneys and spleen, whereas the radiation dose to the tumour-free liver was underestimated. However, both dosimetric approaches detected the two patients with an exceptionally high radiation burden to the kidneys that carried a potential risk of renal failure following radionuclide therapy. (orig.)

Ultra-low-dose CT imaging of the thorax: decreasing the radiation dose by one order of magnitude

International Nuclear Information System (INIS)

Lambert, Lukas; Banerjee, Rohan; Votruba, Jiri; El-Lababidi, Nabil; Zeman, Jiri

2016-01-01

Computed tomography (CT) is an indispensable tool for imaging of the thorax and there is virtually no alternative without associated radiation burden. The authors demonstrate ultra-low-dose CT of the thorax in three interesting cases. In an 18-y-old girl with rheumatoid arthritis, CT of the thorax identified alveolitis in the posterior costophrenic angles (radiation dose = 0.2 mSv). Its resolution was demonstrated on a follow-up scan (4.2 mSv) performed elsewhere. In an 11-y-old girl, CT (0.1 mSv) showed changes of the right collar bone consistent with chronic recurrent multifocal osteomyelitis. CT (0.1 mSv) of a 9-y-old girl with mucopolysaccharidosis revealed altogether three hamartomas, peribronchial infiltrate, and spine deformity. In some indications, the radiation dose from CT of the thorax can approach that of several plain radiographs. This may help the pediatrician in deciding whether 'gentle' ultra-low-dose CT instead of observation or follow-up radiographs will alleviate the uncertainty of the diagnosis with little harm to the child. (author)

Indoor gamma dose measurements in Gudalore (India) using TLD

Energy Technology Data Exchange (ETDEWEB)

Sivakumar, R.; Selvasekarapandian, S. E-mail: spandian@bharathi.ernet.in; Mugunthamanikandan, N.; Raghunath, V.M

2002-06-01

Indoor gamma radiation dose rates were measured inside residential buildings in Gudalore using a CaSO{sub 4} : Dy thermoluminescent dosimeter for 1 year . Significant seasonal variations are observed. The highest dose rate is observed during summer and the lowest in winter. The dose rates observed are between 77.9 and 229.3 nGy h{sup -1} and may be attributed to the type of building materials used in the dwellings monitored. The calculated mean annual effective dose equivalent rates range between 477.6 {mu}Sv y{sup -1}, for the inhabitants of mud houses to 1406.3 {mu}Sv y{sup -1}, for those living in terrace houses made of cement and brick.

Dose-to-medium vs. dose-to-water: Dosimetric evaluation of dose reporting modes in Acuros XB for prostate, lung and breast cancer

Directory of Open Access Journals (Sweden)

Suresh Rana

2014-12-01

Full Text Available Purpose: Acuros XB (AXB dose calculation algorithm is available for external beam photon dose calculations in Eclipse treatment planning system (TPS. The AXB can report the absorbed dose in two modes: dose-to-water (Dw and dose-to-medium (Dm. The main purpose of this study was to compare the dosimetric results of the AXB_Dm with that of AXB_Dw on real patient treatment plans. Methods: Four groups of patients (prostate cancer, stereotactic body radiation therapy (SBRT lung cancer, left breast cancer, and right breast cancer were selected for this study, and each group consisted of 5 cases. The treatment plans of all cases were generated in the Eclipse TPS. For each case, treatment plans were computed using AXB_Dw and AXB_Dm for identical beam arrangements. Dosimetric evaluation was done by comparing various dosimetric parameters in the AXB_Dw plans with that of AXB_Dm plans for the corresponding patient case. Results: For the prostate cancer, the mean planning target volume (PTV dose in the AXB_Dw plans was higher by up to 1.0%, but the mean PTV dose was within ±0.3% for the SBRT lung cancer. The analysis of organs at risk (OAR results in the prostate cancer showed that AXB_Dw plans consistently produced higher values for the bladder and femoral heads but not for the rectum. In the case of SBRT lung cancer, a clear trend was seen for the heart mean dose and spinal cord maximum dose, with AXB_Dw plans producing higher values than the AXB_Dm plans. However, the difference in the lung doses between the AXB_Dm and AXB_Dw plans did not always produce a clear trend, with difference ranged from -1.4% to 2.9%. For both the left and right breast cancer, the AXB_Dm plans produced higher maximum dose to the PTV for all cases. The evaluation of the maximum dose to the skin showed higher values in the AXB_Dm plans for all 5 left breast cancer cases, whereas only 2 cases had higher maximum dose to the skin in the AXB_Dm plans for the right breast cancer

Monte Carlo simulation of radiation transport and dose deposition from locally released gold nanoparticles labeled with 111In, 177Lu or 90Y incorporated into tissue implantable depots

Science.gov (United States)

Lai, Priscilla; Cai, Zhongli; Pignol, Jean-Philippe; Lechtman, Eli; Mashouf, Shahram; Lu, Yijie; Winnik, Mitchell A.; Jaffray, David A.; Reilly, Raymond M.

2017-11-01

Permanent seed implantation (PSI) brachytherapy is a highly conformal form of radiation therapy but is challenged with dose inhomogeneity due to its utilization of low energy radiation sources. Gold nanoparticles (AuNP) conjugated with electron emitting radionuclides have recently been developed as a novel form of brachytherapy and can aid in homogenizing dose through physical distribution of radiolabeled AuNP when injected intratumorally (IT) in suspension. However, the distribution is unpredictable and precise placement of many injections would be difficult. Previously, we reported the design of a nanoparticle depot (NPD) that can be implanted using PSI techniques and which facilitates controlled release of AuNP. We report here the 3D dose distribution resulting from a NPD incorporating AuNP labeled with electron emitters (90Y, 177Lu, 111In) of different energies using Monte Carlo based voxel level dosimetry. The MCNP5 Monte Carlo radiation transport code was used to assess differences in dose distribution from simulated NPD and conventional brachytherapy sources, positioned in breast tissue simulating material. We further compare these dose distributions in mice bearing subcutaneous human breast cancer xenografts implanted with 177Lu-AuNP NPD, or injected IT with 177Lu-AuNP in suspension. The radioactivity distributions were derived from registered SPECT/CT images and time-dependent dose was estimated. Results demonstrated that the dose distribution from NPD reduced the maximum dose 3-fold when compared to conventional seeds. For simulated NPD, as well as NPD implanted in vivo, 90Y delivered the most homogeneous dose distribution. The tumor radioactivity in mice IT injected with 177Lu-AuNP redistributed while radioactivity in the NPD remained confined to the implant site. The dose distribution from radiolabeled AuNP NPD were predictable and concentric in contrast to IT injected radiolabeled AuNP, which provided irregular and temporally variant dose distributions

Maximum likelihood analysis of bioassay data from long-term follow-up of two refractory PuO2 inhalation cases.

Science.gov (United States)

Avtandilashvili, Maia; Brey, Richard; James, Anthony C

2012-07-01

The U.S. Transuranium and Uranium Registries' tissue donors 0202 and 0407 are the two most highly exposed of the 18 registrants who were involved in the 1965 plutonium fire accident at a defense nuclear facility. Material released during the fire was well characterized as "high fired" refractory plutonium dioxide with 0.32-μm mass median diameter. The extensive bioassay data from long-term follow-up of these two cases were used to evaluate the applicability of the Human Respiratory Tract Model presented by International Commission on Radiological Protection in Publication 66 and its revision proposed by Gregoratto et al. in order to account for the observed long-term retention of insoluble material in the lungs. The maximum likelihood method was used to calculate the point estimates of intake and tissue doses and to examine the effect of different lung clearance, blood absorption, and systemic models on the goodness-of-fit and estimated dose values. With appropriate adjustments, Gregoratto et al. particle transport model coupled with the customized blood absorption parameters yielded a credible fit to the bioassay data for both cases and predicted the Case 0202 liver and skeletal activities measured postmortem. PuO2 particles produced by the plutonium fire are extremely insoluble. About 1% of this material is absorbed from the respiratory tract relatively rapidly, at a rate of about 1 to 2 d (half-time about 8 to 16 h). The remainder (99%) is absorbed extremely slowly, at a rate of about 5 × 10(-6) d (half-time about 400 y). When considering this situation, it appears that doses to other body organs are negligible in comparison to those to tissues of the respiratory tract. About 96% of the total committed weighted dose equivalent is contributed by the lungs. Doses absorbed by these workers' lungs were high: 3.2 Gy to AI and 6.5 Gy to LNTH for Case 0202 (18 y post-intake) and 3.2 Gy to AI and 55.5 Gy to LNTH for Case 0407 (43 y post-intake). This evaluation

On Positive Solutions for the Rational Difference Equation Systems x n+1 = A/x n y n (2), and y n+1 = By n /x n-1 y n-1.

Science.gov (United States)

Ma, Hui-Li; Feng, Hui

2014-01-01

Our aim in this paper is to investigate the behavior of positive solutions for the following systems of rational difference equations: x n+1 = A/x n y n (2), and y n+1 = By n /x n-1 y n-1, n = 0,1,…, where x -1, x 0, y -1, and y 0 are positive real numbers and A and B are positive constants.

Baseline studies of terrestrial outdoor gamma dose rate levels in Nigeria

International Nuclear Information System (INIS)

Farai, I.P.; Jibiri, N.N.

2000-01-01

The outdoor γ radiation exposure dose rates due to the radioactivity concentration of 40 K, 238 U and 232 Th in the soil across different environments in Nigeria have been carried out using the low-cost method of in situ γ ray spectrometry. Measurements were made in 18 cities, spread across the three major zones of the country. The radioactivity concentrations of these radionuclides in the soil were used to determine their γ radiation absorbed dose rates in the air. The range of average total dose rate due to the three radionuclides in the Eastern zone is between 0.025 and 0.081 μGy.h -1 with an average of 0.040 ± 0.006 μGy.h -1 , 0.041 and 0.214 μGy.h -1 with a mean of 0.089 ± 0.014 μGy.h -1 for the Western zone and between 0.066 and 0.222 μGy.h -1 with a mean of 0.102 ± 0.032 μGy.h -1 for the Northern zone. The average annual outdoor effective dose equivalents of 51 ± 8 μSv.y -1 , 114 ± 18 μSv.y -1 and 130 ± 41 μSv.y -1 have been estimated for the Eastern, Western and Northern zones, respectively. The average annual effective dose equivalent for the country has been estimated to be 98 ± 15 μSv.y -1 and the collective effective dose equivalent as 9.7 x 103 man.Sv.y -1 . Measurements have been taken as representing the baseline values of natural radioactivity as no artificial radionuclide was detected at any of the sites surveyed. (author)

Fluorine-ion conductivity of different technological forms of solid electrolytes R{sub 1–y}M{sub y}F{sub 3–y} (LaF{sub 3} Type ) (M = Ca, Sr, Ba; R Are Rare Earth Elements)

Energy Technology Data Exchange (ETDEWEB)

Sorokin, N. I., E-mail: nsorokin1@yandex.ru; Sobolev, B. P. [Russian Academy of Sciences, Shubnikov Institute of Crystallography (Russian Federation)

2016-05-15

We have investigated the conductivity of some representatives of different technological forms of fluoride-conducting solid electrolytes R{sub 1–y}M{sub y}F{sub 3–y} (M = Ca, Sr, Ba; R are rare earth elements) with an LaF{sub 3} structure: single crystals, cold- and hot-pressing ceramics based on a charge prepared in different ways (mechanochemical synthesis, solid-phase synthesis, and fragmentation of single crystals), polycrystalline alloys, etc. It is shown (by impedance spectroscopy), that different technological forms of identical chemical composition (R, M, y) exhibit different electrical characteristics. The maximum conductivity is observed for the single-crystal form of R{sub 1–y}M{sub y}F{sub 3–y} tysonite phases, which provides (in contrast to other technological forms) the formation of true volume ion-conducting characteristics.

Absorbed doses to the main parts of eyeball due to use 90Sr + 90Y ophthalmic applicator

International Nuclear Information System (INIS)

Chen Lishu

1993-05-01

The ophthalmic radiotherapy dosimetry and some affecting factors are introduced. The distributions of absorbed doses to the main parts of a fresh eyeball such as the cornea, sclera, lens and anterior chamber, during the radiotherapy by using a 90 Sr + 90 Y ophthalmic applicator are presented. An tissue-equivalent extrapolation ionization chamber was used in the dose measurement. The reasonable doses during ophthalmic radiotherapy for different depths have been obtained. Therefore, the absorbed dose to the lens, the most sensitive organ, can be given. These data are useful for radiation protection in ophthalmic radiotherapy

Quadrivalent meningococcal (MenACWY-TT) conjugate vaccine or a fourth dose of H. influenzae-N. meningitidis C/Y conjugate vaccine (HibMenCY-TT) is immunogenic in toddlers who previously received three doses of HibMenCY-TT in infancy.

Science.gov (United States)

Leonardi, Michael; Latiolais, Thomas; Sarpong, Kwabena; Simon, Michael; Twiggs, Jerry; Lei, Paul; Rinderknecht, Stephen; Blatter, Mark; Bianco, Veronique; Baine, Yaela; Friedland, Leonard R; Miller, Jacqueline M

2015-02-11

Immunogenicity and safety of a single dose of MenACWY-TT or a fourth dose of HibMenCY-TT were evaluated in the second year of life in HibMenCY-TT-primed toddlers. Healthy infants were randomized (5:1) and primed at 2, 4 and 6 months of age with HibMenCY-TT and diphtheria-tetanus-acellular pertussis-hepatitis B-inactivated poliovirus (DTaP-HBV-IPV) vaccine; or Hib-TT and DTaP-HBV-IPV (control). Recipients of HibMenCY-TT+DTaP-HBV-IPV were re-randomized (2:2:1) to receive MenACWY-TT at 12-15 months and DTaP at 15-18 months; MenACWY-TT co-administered with DTaP at 15-18 months; or HibMenCY-TT at 12-15 months and DTaP at 15-18 months. Controls received DTaP only at 15-18 months due to Hib conjugate vaccine shortage. Serum bactericidal activity using human complement (hSBA) and safety were assessed one month after meningococcal vaccination. After vaccination with MenACWY-TT at 12-15 months or MenACWY-TT+DTaP at 15-18 months, all subjects previously primed for serogroups C/Y had hSBA ≥1:8 for these serogroups. At least 96.1% also had hSBA ≥1:8 for serogroups A/W. All subjects in the HibMenCY-TT group had hSBA ≥1:8 for serogroups C/Y. All pre-defined statistical criteria for meningococcal immunogenicity were satisfied. All vaccination regimens had acceptable safety profiles. Children primed with three doses of HibMenCY-TT who then received a single dose of MenACWY-TT or a fourth dose of HibMenCY-TT had robust increases in hSBA titers for serogroups C/Y. These data provide support that MenACWY-TT, given with or without the fourth scheduled dose of DTaP could be administered as an alternative to a fourth dose of HibMenCY-TT in the second year of life. This study (110870/110871) is registered at www.clinicaltrials.gov NCT00614614. Copyright © 2014 The Authors. Published by Elsevier Ltd.. All rights reserved.

Stereotactic Body Radiation Therapy Boost After Concurrent Chemoradiation for Locally Advanced Non-Small Cell Lung Cancer: A Phase 1 Dose Escalation Study

Energy Technology Data Exchange (ETDEWEB)

Hepel, Jaroslaw T., E-mail: jhepel@lifespan.org [Department of Radiation Oncology, Rhode Island Hospital, Brown University, Providence, Rhode Island (United States); Department of Radiation Oncology, Tufts Medical Center, Tufts University, Boston, Massachusetts (United States); Leonard, Kara Lynne [Department of Radiation Oncology, Rhode Island Hospital, Brown University, Providence, Rhode Island (United States); Department of Radiation Oncology, Tufts Medical Center, Tufts University, Boston, Massachusetts (United States); Safran, Howard [Division of Medical Oncology, Rhode Island Hospital, Brown University, Providence, Rhode Island (United States); Division of Medical Oncology, Miriam Hospital, Brown University, Providence, Rhode Island (United States); Ng, Thomas [Division of Thoracic Surgery, Rhode Island Hospital, Brown University, Providence, Rhode Island (United States); Taber, Angela [Division of Medical Oncology, Miriam Hospital, Brown University, Providence, Rhode Island (United States); Khurshid, Humera; Birnbaum, Ariel [Division of Medical Oncology, Rhode Island Hospital, Brown University, Providence, Rhode Island (United States); Wazer, David E.; DiPetrillo, Thomas [Department of Radiation Oncology, Rhode Island Hospital, Brown University, Providence, Rhode Island (United States); Department of Radiation Oncology, Tufts Medical Center, Tufts University, Boston, Massachusetts (United States)

2016-12-01

Purpose: Stereotactic body radiation therapy (SBRT) boost to primary and nodal disease after chemoradiation has potential to improve outcomes for advanced non-small cell lung cancer (NSCLC). A dose escalation study was initiated to evaluate the maximum tolerated dose (MTD). Methods and Materials: Eligible patients received chemoradiation to a dose of 50.4 Gy in 28 fractions and had primary and nodal volumes appropriate for SBRT boost (<120 cc and <60 cc, respectively). SBRT was delivered in 2 fractions after chemoradiation. Dose was escalated from 16 to 28 Gy in 2 Gy/fraction increments, resulting in 4 dose cohorts. MTD was defined when ≥2 of 6 patients per cohort experienced any treatment-related grade 3 to 5 toxicity within 4 weeks of treatment or the maximum dose was reached. Late toxicity, disease control, and survival were also evaluated. Results: Twelve patients (3 per dose level) underwent treatment. All treatment plans met predetermined dose-volume constraints. The mean age was 64 years. Most patients had stage III disease (92%) and were medically inoperable (92%). The maximum dose level was reached with no grade 3 to 5 acute toxicities. At a median follow-up time of 16 months, 1-year local-regional control (LRC) was 78%. LRC was 50% at <24 Gy and 100% at ≥24 Gy (P=.02). Overall survival at 1 year was 67%. Late toxicity (grade 3-5) was seen in only 1 patient who experienced fatal bronchopulmonary hemorrhage (grade 5). There were no predetermined dose constraints for the proximal bronchial-vascular tree (PBV) in this study. This patient's 4-cc PBV dose was substantially higher than that received by other patients in all 4 cohorts and was associated with the toxicity observed: 20.3 Gy (P<.05) and 73.5 Gy (P=.07) for SBRT boost and total treatment, respectively. Conclusions: SBRT boost to both primary and nodal disease after chemoradiation is feasible and well tolerated. Local control rates are encouraging, especially at doses ≥24�

Indicators of image quality and doses in mammography; Indicadores de calidad de imagen y dosis en mamografia

Energy Technology Data Exchange (ETDEWEB)

Gaona, E.; Franco E, J.G. [UAM-X, Calz. del Hueso 1100, 04960 Mexico D.F. (Mexico); Azorin N, J.; Diaz G, J.A.I. [CICATA-IPN, 11500 Mexico D.F. (Mexico); Arreola, M. [Shands Hospital at UF, PO Box 100374, Gainesville FL 32610-0374 (United States)

2007-07-01

Full text: The purpose of the study was to determine the values of the image quality indicators and their relationship with the dose in mammography of screen-film that they allowed the detection of a bigger number of objects in the images obtained with the mannequin (phantom) authorized of the ACR/FDA. The study was carried out in four mammography services in a period of 12 months. The indicators of the image quality are the half optic density (DOM), contrast (differences of densities), the number of observed objects in the images and the dose for image. The minimum acceptable values by the ACR/FDA are a half optical density of 1.4, contrast of 0.4 and the one numbers minimum of objects observed in the image of the mannequin of mammography of 10 (4 fibers, 3 groups of calcifications and 3 masses), with a maximum dose by image of 3 mGy. The found results are half optical density of 1.9, contrast of 0.56 and the average number of objects observed in the images of 12, with a dose in the interval of 1.6 mGy to 2.4 mGy. The doses were measured by thermoluminescent dosimetry and ionization chamber. Once carried out the analysis of the tendencies of the indicators of image quality and their distributions is found that for a p < 0.05, the bigger number of objects observed in the images is in the interval from 1.8 to 1.9 of DOM. When comparing both mammography system, the system screen-film has a lower variability in the distribution of objects associated to a DOM. (Author)

Calibration setting numbers for dose calibrators for the PET isotopes "5"2Mn, "6"4Cu, "7"6Br, "8"6Y, "8"9Zr, "1"2"4I

International Nuclear Information System (INIS)

Wooten, A. Lake; Lewis, Benjamin C.; Szatkowski, Daniel J.; Sultan, Deborah H.; Abdin, Kinda I.; Voller, Thomas F.; Liu, Yongjian; Lapi, Suzanne E.

2016-01-01

For PET radionuclides, the radioactivity of a sample can be conveniently measured by a dose calibrator. These devices depend on a “calibration setting number”, but many recommended settings from manuals were interpolated based on standard sources of other radionuclide(s). We conducted HPGe gamma-ray spectroscopy, resulting in a reference for determining settings in two types of vessels containing one of several PET radionuclides. Our results reiterate the notion that in-house, experimental calibrations are recommended for different radionuclides and vessels. - Highlights: • Dose calibrators measure radioactivity by ionization of gas from emitted radiation. • Accuracy of dose calibrators depends on “calibration setting numbers” for isotopes. • Many manufacturer settings are interpolated from emissions of other radionuclides. • As a high-precision reference, HPGe gamma-ray spectroscopy was conducted. • New calibrations were found for PET isotopes "5"2Mn, "6"4Cu, "7"6Br, "8"6Y, "8"9Zr, and "1"2"4I.

Dose commitments due to radioactive releases from nuclear power plant sites: Methodology and data base. Supplement 1

Energy Technology Data Exchange (ETDEWEB)

Baker, D.A. [Pacific Northwest National Lab., Richland, WA (United States)

1996-06-01

This manual describes a dose assessment system used to estimate the population or collective dose commitments received via both airborne and waterborne pathways by persons living within a 2- to 80-kilometer region of a commercial operating power reactor for a specific year of effluent releases. Computer programs, data files, and utility routines are included which can be used in conjunction with an IBM or compatible personal computer to produce the required dose commitments and their statistical distributions. In addition, maximum individual airborne and waterborne dose commitments are estimated and compared to 10 CFR Part 50, Appendix 1, design objectives. This supplement is the last report in the NUREG/CR-2850 series.

Dose commitments due to radioactive releases from nuclear power plant sites: Methodology and data base. Supplement 1

International Nuclear Information System (INIS)

Baker, D.A.

1996-06-01

This manual describes a dose assessment system used to estimate the population or collective dose commitments received via both airborne and waterborne pathways by persons living within a 2- to 80-kilometer region of a commercial operating power reactor for a specific year of effluent releases. Computer programs, data files, and utility routines are included which can be used in conjunction with an IBM or compatible personal computer to produce the required dose commitments and their statistical distributions. In addition, maximum individual airborne and waterborne dose commitments are estimated and compared to 10 CFR Part 50, Appendix 1, design objectives. This supplement is the last report in the NUREG/CR-2850 series

Long-lived impurities of 90Y-labeled microspheres, TheraSphere and SIR-spheres, and the impact on patient dose and waste management.

Science.gov (United States)

Metyko, John; Williford, John M; Erwin, William; Poston, John; Jimenez, Sandra

2012-11-01

Yittrium-90 microsphere brachytherapy procedures have increased in number due to their efficacy in treating some unresectable metastatic liver tumors. The discovery of long-lived impurities in two microsphere products, first reported between 2006 and 2007, has resulted in some radiation safety concerns. Since then, microsphere production processes have been refined, which reportedly lead to a reduction in detectable by-products. In this study unused vials of TheraSphere and SIR-Spheres, manufactured in early January 2011, were analyzed to identify and quantify the low-level radioactive impurities. Absorbed dose calculations were performed to assess the potential increased dose to the patient due to long-lived impurities. Results showed that while the SIR-Spheres vials contained no detectable impurities (contrary to other published results in the literature), the TheraSphere vials contained 17 radionuclides in one sample and 15 in the other. The dominant impurities were Y and Y, with specific activities ranging from 0.99 ± 3.40 × 10 kBq mg to 6.30 ± 0.40 kBq mg at vendor assay date. Other impurities were on the order of Bq mg. Based on Medical Internal Radiation Dose (MIRD) liver and lung dose estimates, the long-lived impurities would be expected to increase an administered dose by less than 0.1% from the prescribed dose.

Immunogenicity of fractional doses of tetravalent a/c/y/w135 meningococcal polysaccharide vaccine: results from a randomized non-inferiority controlled trial in Uganda.

Directory of Open Access Journals (Sweden)

Philippe J Guerin

Full Text Available Neisseria meningitidis serogroup A is the main causative pathogen of meningitis epidemics in sub-Saharan Africa. In recent years, serogroup W135 has also been the cause of epidemics. Mass vaccination campaigns with polysaccharide vaccines are key elements in controlling these epidemics. Facing global vaccine shortage, we explored the use of fractional doses of a licensed A/C/Y/W135 polysaccharide meningococcal vaccine.We conducted a randomized, non-inferiority trial in 750 healthy volunteers 2-19 years old in Mbarara, Uganda, to compare the immune response of the full dose of the vaccine versus fractional doses (1/5 or 1/10. Safety and tolerability data were collected for all subjects during the 4 weeks following the injection. Pre- and post-vaccination sera were analyzed by measuring serum bactericidal activity (SBA with baby rabbit complement. A responder was defined as a subject with a > or =4-fold increase in SBA against a target strain from each serogroup and SBA titer > or =128. For serogroup W135, 94% and 97% of the vaccinees in the 1/5- and 1/10-dose arms, respectively, were responders, versus 94% in the full-dose arm; for serogroup A, 92% and 88% were responders, respectively, versus 95%. Non-inferiority was demonstrated between the full dose and both fractional doses in SBA seroresponse against serogroups W135 and Y, in total population analysis. Non-inferiority was shown between the full and 1/5 doses for serogroup A in the population non-immune prior to vaccination. Non-inferiority was not shown for any of the fractionate doses for serogroup C. Safety and tolerability data were favourable, as observed in other studies.While the advent of conjugate A vaccine is anticipated to largely contribute to control serogroup A outbreaks in Africa, the scale-up of its production will not cover the entire "Meningitis Belt" target population for at least the next 3 to 5 years. In view of the current shortage of meningococcal vaccines for Africa

Time and dose-related changes in the thickness of pig skin after irradiation with single doses of 90Sr/90Y β-rays

International Nuclear Information System (INIS)

Rezvani, M.; Hamlet, R.; Hopewell, J.W.; Sieber, V.K.

1994-01-01

Time-related changes in pig skin thickness have been evaluated using a non-invasive ultrasound technique after exposure to a range of single doses of 90 Sr/ 90 Yr β-rays. The reduction in relative skin thickness developed in two distinct phases: the first was between 12 and 20 weeks postirradiation. No further changes were then seen until 52 weeks postirradiation when a second phase of skin thinning was observed. This was complete after 76 weeks and no further changes in relative skin thickness were seen in the maximum follow up period of 129 weeks. The timings of these phases of damage were independent of the radiation dose, however, the severity of both phases of radiation-induced skin thinning were dose related. (Author)

The usefulness of metal markers for CTV-based dose prescription in high-dose-rate interstitial brachytherapy

International Nuclear Information System (INIS)

Yoshida, Ken; Mitomo, Masanori; Nose, Takayuki; Koizumi, Masahiko; Nishiyama, Kinji; Yoshida, Mineo

2002-01-01

than the maximum normal tissue doses. The doses of 2 markers for (1 patient) for OAR (the urethra) were higher than the maximum normal tissue dose. Seven markers OAR (the mandible) were not visualized because of metal crowns. If the Paris system (reference dose is prescribed to an isodose surface of 85% of the basal dose) had been used, 16 patients had been ''underdosed'' and 4 patients (the rectum+the urethra: 2; the urethra: 1; the large vessel: 1) ''overdosed''. Dose non-uniformity ratio (DNR) and maximum diameter of hyperdose sleeve were 0.31±0.08 and 4-49 mm (median: 7 mm) in CTV-based dose prescription. A statistically significant difference was seen between CTV-based dose prescription and Paris system {0.28±0.08 and 3-99 mm (median: 6 mm)} (p<0.002, 0.0002). Two of 42 patients treated with higher than the tumoricidal dose had local recurrence, while 4 of 7 underdosed patients had local recurrence. A significant difference was found between them (p<0.0001). Metal markers were useful to prescribe the tumoricidal dose to CTV and to regulated the doses for OAR. Local control rate of the patients treated with higher than the tumoricidal dose was significantly better. Miss-implantation of metal markers was a problem that should be resolved. (author)

Assessment of maximum tolerated dose of a new herbal drug, Semelil (ANGIPARSTM in patients with diabetic foot ulcer: A Phase I clinical trial

Directory of Open Access Journals (Sweden)

Heshmat R

2008-04-01

Full Text Available Background and the purpose of the study: In many cases of diabetic foot ulcer (DFU management, wound healing is incomplete, and wound closure and epithelial junctional integrity are rarely achieved. Our aim was to evaluate the maximum tolerated dose (MTD and dose-limiting toxicity (DLT of Semelil (ANGIPARSTM, a new herbal compound for wound treatment in a Phase I clinical trial.Methods: In this open label study, six male diabetic patients with a mean age of 57±7.6 years were treated with escalating intravenous doses of Semelil, which started at 2 cc/day to 13.5 cc/day for 28 days. Patients were assessed with a full physical exam; variables which analyzed included age, past history of diabetes and its duration, blood pressure, body temperature, weight, characteristics of DFU, Na, K, liver function test, Complete Blood Count and Differential(CBC & diff, serum amylase, HbA1c, PT, PTT, proteinuria, hematuria, and side effects were recorded. All the measurements were taken at the beginning of treatment, the end of week 2 and week 4. We also evaluated Semelil's side effects at the end of weeks 4 and 8 after ending therapy.Results and major conclusions: Up to the drug dose of 10 cc/day foot ulcer dramatically improved. We did not observe any clinical or laboratory side effects at this or lower dose levels in diabetic patients. With daily dose of 13.5 cc of Semelil we observed phlebitis at the infusion site, which was the only side effect. Therefore, in this study we determined the MTD of Semelil at 10 cc/day, and the only DLT was phlebitis in injection vein. The recommended dose of Semelil I.V. administration for Phase II studies was 4 cc/day.

Methods of assessment of individual and collective doses to transport workers and members of the public during the transport of radioactive materials. Part of a coordinated programme on safe transport of radioactive material

International Nuclear Information System (INIS)

Vohra, K.G.

1983-12-01

A study in India, partially supported by an IAEA research contract, provided measurements of exposure to transport workers associated with the transport of radioisotopes for medical, industry and research purposes. A survey showed this to be the single most significant source of transport worker exposure in India. The largest exposures were found with transport workers at the Bombay airport through which these packages are ''funnelled''. The maximum occupational doses were found to be between 1.8 and 2.0 mSv/y assuming only four men handle all of the packages throughout the year. Furthermore, it was found that the surface transport of these materials in the Bombay area results in an estimated maximum annual collective dose to the public of only 0.1 man Sv/y. It was further noted that this collective dose results not from high radiation levels but from the high population density involved in the Bombay area. The model provides reasonable correlation with the measured data, but it was indicated that additional testing of the model needed to be performed. The data indicate a correlation between persons preparing the packages and persons handling the packages in transport. It was not possible to derive a simple empirical model based solely on Transport Index

An updated dose assesment for resettlement options at Bikini atoll - A US nuclear test site

International Nuclear Information System (INIS)

Robison, W.L.; Bogen, K.T.; Conrado, C.L.

1997-01-01

There has been a continuing effort since 1977 to refine dose assessments for resettlement options at Bikini Atoll. Here we provide a radiological dose assessment for the main residence island, Bikini, using extensive radio nuclide concentration data derived from analysis of food crops, ground water, cistern water, fish and other marine species, animals, air, and soil collected at Bikini Island as part of our continuing research and monitoring program that began in 1978. The unique composition of coral soil greatly alters the relative contribution of 137 Cs and 90 Sr to the total estimated dose relative to expectations based on North American and European soils. Without counter measures, 137 Cs produces 96% of the estimated dose for returning residents, mostly through uptake from the soil to terrestrial food crops but also from external gamma exposure. The doses are calculated assuming a resettlement date of 1999. The estimated maximum annual effective dose for current island conditions is 4.0 mSv when imported foods, which are now an established part of the diet, are available. The 30-, 50-, and 70-y integral effective doses are 91 mSv, 130 mSv, and 150 mSv, respectively. A detailed uncertainty analysis for these dose estimates is presented in a companion paper in this issue. We have evaluated various countermeasures to reduce 137 Cs in food crops. Treatment with potassium reduces the uptake of 137 Cs into food crops, and therefore the ingestion dose, to about 5 % of pretreatment levels and has essentially no negative environmental consequences. We have calculated the dose for the rehabilitation scenario where the top 40 cm of soil is removed in the housing and village area, and the rest of the island is treated with potassium fertilizer; the maximum annual effective dose is 0.41 mSv and the 30-, 50-, and 70-y integral effective doses are 9.8 mSv, 14 mSv, and 16 mSv, respectively. 44 refs., 3 figs., 11 tabs

Central nervous system neuropeptide Y signaling via the Y1 receptor partially dissociates feeding behavior from lipoprotein metabolism in lean rats.

Science.gov (United States)

Rojas, Jennifer M; Stafford, John M; Saadat, Sanaz; Printz, Richard L; Beck-Sickinger, Annette G; Niswender, Kevin D

2012-12-15

Elevated plasma triglyceride (TG) levels contribute to an atherogenic dyslipidemia that is associated with obesity, diabetes, and metabolic syndrome. Numerous models of obesity are characterized by increased central nervous system (CNS) neuropeptide Y (NPY) tone that contributes to excess food intake and obesity. Previously, we demonstrated that intracerebroventricular (icv) administration of NPY in lean fasted rats also elevates hepatic production of very low-density lipoprotein (VLDL)-TG. Thus, we hypothesize that elevated CNS NPY action contributes to not only the pathogenesis of obesity but also dyslipidemia. Here, we sought to determine whether the effects of NPY on feeding and/or obesity are dissociable from effects on hepatic VLDL-TG secretion. Pair-fed, icv NPY-treated, chow-fed Long-Evans rats develop hypertriglyceridemia in the absence of increased food intake and body fat accumulation compared with vehicle-treated controls. We then modulated CNS NPY signaling by icv injection of selective NPY receptor agonists and found that Y1, Y2, Y4, and Y5 receptor agonists all induced hyperphagia in lean, ad libitum chow-fed Long-Evans rats, with the Y2 receptor agonist having the most pronounced effect. Next, we found that at equipotent doses for food intake NPY Y1 receptor agonist had the most robust effect on VLDL-TG secretion, a Y2 receptor agonist had a modest effect, and no effect was observed for Y4 and Y5 receptor agonists. These findings, using selective agonists, suggest the possibility that the effect of CNS NPY signaling on hepatic VLDL-TG secretion may be relatively dissociable from effects on feeding behavior via the Y1 receptor.

Adult exposure to tributyltin affects hypothalamic neuropeptide Y, Y1 receptor distribution, and circulating leptin in mice.

Science.gov (United States)

Bo, E; Farinetti, A; Marraudino, M; Sterchele, D; Eva, C; Gotti, S; Panzica, G

2016-07-01

Tributyltin (TBT), a pesticide used in antifouling paints, is toxic for aquatic invertebrates. In vertebrates, TBT may act in obesogen- inducing adipogenetic gene transcription for adipocyte differentiation. In a previous study, we demonstrated that acute administration of TBT induces c-fos expression in the arcuate nucleus. Therefore, in this study, we tested the hypothesis that adult exposure to TBT may alter a part of the nervous pathways controlling animal food intake. In particular, we investigated the expression of neuropeptide Y (NPY) immunoreactivity. This neuropeptide forms neural circuits dedicated to food assumption and its action is mediated by Y1 receptors that are widely expressed in the hypothalamic nuclei responsible for the regulation of food intake and energy homeostasis. To this purpose, TBT was orally administered at a dose of 0.025 mg/kg/day/body weight to adult animals [male and female C57BL/6 (Y1-LacZ transgenic mice] for 4 weeks. No differences were found in body weight and fat deposition, but we observed a significant increase in feed efficiency in TBT-treated male mice and a significant decrease in circulating leptin in both sexes. Computerized quantitative analysis of NPY immunoreactivity and Y1-related β-galactosidase activity demonstrated a statistically significant reduction in NPY and Y1 transgene expression in the hypothalamic circuit controlling food intake of treated male mice in comparison with controls. In conclusion, the present results indicate that adult exposure to TBT is profoundly interfering with the nervous circuits involved in the stimulation of food intake. © 2016 American Society of Andrology and European Academy of Andrology.

Final Report for the Testing of the Y-12 Criticality Accident Alarm System Detectors at the Godiva IV Burst Reactor (IER-443)

Energy Technology Data Exchange (ETDEWEB)

Scorby, John C. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hickman, David [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Hudson, Becka [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Beller, Tim [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Goda, Joetta [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Haught, Chris [Y-12 National Security Complex, Oak Ridge, TN (United States); Woodrow, Christopher [Y-12 National Security Complex, Oak Ridge, TN (United States); Ward, Dann [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Wilson, Chris [Atomic Weapons Establishment (AWE), Berkshire (United Kingdom); Clark, Leo [Atomic Weapons Establishment (AWE), Berkshire (United Kingdom)

2018-01-05

This report documents the experimental conditions and final results for the performance testing of the Y-12 Criticality Accident Alarm System (CAAS) detectors at the Godiva IV Burst Reactor at the National Criticality Experimental Research Center (NCERC) at the Nevada National Security Site (NNSS). The testing followed a previously issued test plan and was conducted during the week of July 17, 2017, with completion on Thursday July 20. The test subjected CAAS detectors supplied by Y-12 to very intense and short duration mixed neutron and gamma radiation fields to establish compliance to maximum radiation and minimum pulse width requirements. ANSI/ANS- 8.3.1997 states that the “system shall be sufficiently robust as to actuate an alarm signal when exposed to the maximum radiation expected”, which has been defined at Y-12, in Documented Safety Analyses (DSAs), to be a dose rate of 10 Rad/s. ANSI/ANS-8.3.1997 further states that “alarm actuation shall occur as a result of a minimum duration transient” which may be assumed to be 1 msec. The pulse widths and dose rates provided by each burst during the test exceeded those requirements. The CAAS detectors all provided an immediate alarm signal and remained operable after the bursts establishing compliance to the requirements and fitness for re-deployment at Y-12.

SU-F-T-113: Inherent Functional Dependence of Spinal Cord Doses of Variable Irradiated Volumes in Spine SBRT

Energy Technology Data Exchange (ETDEWEB)

Ma, L; Braunstein, S; Chiu, J [University of California San Francisco, San Francisco, CA (United States); Sahgal, A [Sunnybrook Health Sciences Center, University of Toronto, Toronto, Ontario (Canada)

2016-06-15

Purpose: Spinal cord tolerance for SBRT has been recommended for the maximum point dose level or at irradiated volumes such as 0.35 mL or 10% of contoured volumes. In this study, we investigated an inherent functional relationship that associates these dose surrogates for irradiated spinal cord volumes of up to 3.0 mL. Methods: A hidden variable termed as Effective Dose Radius (EDR) was formulated based on a dose fall-off model to correlate dose at irradiated spinal cord volumes ranging from 0 mL (point maximum) to 3.0 mL. A cohort of 15 spine SBRT cases was randomly selected to derive an EDR-parameterized formula. The mean prescription dose for the studied cases was 21.0±8.0 Gy (range, 10–40Gy) delivered in 3±1 fractions with target volumes of 39.1 ± 70.6 mL. Linear regression and variance analysis were performed for the fitting parameters of variable EDR values. Results: No direct correlation was found between the dose at maximum point and doses at variable spinal cord volumes. For example, Pearson R{sup 2} = 0.643 and R{sup 2}= 0.491 were obtained when correlating the point maximum dose with the spinal cord dose at 1 mL and 3 mL, respectively. However, near perfect correlation (R{sup 2} ≥0.99) was obtained when corresponding parameterized EDRs. Specifically, Pearson R{sup 2}= 0.996 and R{sup 2} = 0.990 were obtained when correlating EDR (maximum point dose) with EDR (dose at 1 mL) and EDR(dose at 3 mL), respectively. As a result, high confidence level look-up tables were established to correlate spinal cord doses at the maximum point to any finite irradiated volumes. Conclusion: An inherent functional relationship was demonstrated for spine SBRT. Such a relationship unifies dose surrogates at variable cord volumes and proves that a single dose surrogate (e.g. point maximum dose) is mathematically sufficient in constraining the overall spinal cord dose tolerance for SBRT.

Influence of the Target Vessel on the Location and Area of Maximum Skin Dose during Percutaneous Coronary Intervention

International Nuclear Information System (INIS)

Chida, K.; Fuda, K.; Kagaya, Y.; Saito, H.; Takai, Y.; Kohzuki, M.; Takahash i, S.; Yamada, S.; Zuguchi, M.

2007-01-01

Background: A number of cases involving radiation-associated patient skin injury attributable to percutaneous coronary intervention (PCI) have been reported. Knowledge of the location and area of the patient's maximum skin dose (MSD) in PCI is necessary to reduce the risk of skin injury. Purpose: To determine the location and area of the MSD in PCI, and separately analyze the effects of different target vessels. Material and Methods: 197 consecutive PCI procedures were studied, and the location and area of the MSD were calculated by a skin-dose mapping software program: Caregraph. The target vessels of the PCI procedures were divided into four groups based on the American Heart Association (AHA) classification. Results: The sites of the MSD for AHA no.1-3, AHA no.4, and AHA no.11-15 were located mainly on the right back skin, the lower right or center back skin, and the upper back skin areas, respectively, whereas the MSD sites for the AHA no. 5-10 PCI were widely spread. The MSD area for the AHA no. 4 PCI was larger than that for the AHA no. 11-15 PCI (P<0.0001). Conclusion: Although the radiation associated with PCI can be widely spread and variable, we observed a tendency regarding the location and area of the MSD when we separately analyzed the data for different target vessels. We recommend the use of a smaller radiation field size and the elimination of overlapping fields during PCI

Kinetics of the early adaptive response and adaptation threshold dose; Cinetica de la respuesta adaptativa temprana y dosis umbral de adaptacion

Energy Technology Data Exchange (ETDEWEB)

Mendiola C, M.T.; Morales R, P. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2003-07-01

The expression kinetics of the adaptive response (RA) in mouse leukocytes in vivo and the minimum dose of gamma radiation that induces it was determined. The mice were exposed 0.005 or 0.02 Gy of {sup 137} Cs like adaptation and 1h later to the challenge dose (1.0 Gy), another group was only exposed at 1.0 Gy and the damage is evaluated in the DNA with the rehearsal it makes. The treatment with 0. 005 Gy didn't induce RA and 0. 02 Gy causes a similar effect to the one obtained with 0.01 Gy. The RA was show from an interval of 0.5 h being obtained the maximum expression with 5.0 h. The threshold dose to induce the RA is 0.01 Gy and in 5.0 h the biggest quantity in molecules is presented presumably that are related with the protection of the DNA. (Author) =.

Absorbed dose profiles for 32P, 90Y, 188Re, 177Lu, 51Cr, 153Sm and 169Er: radionuclides used in radiosynoviortheses treatment

International Nuclear Information System (INIS)

Torres, M.; Ayra, E.; Albuerne, O.; Delgado, M.

2008-01-01

The remarkable advances in the design and synthesis of radiopharmaceuticals has created the opportunity of generating new agents for the treatment of radiosynoviortheses (RSV) which exhibit a minimum leakage from the synovial joint reducing, this way, the non desired absorbed doses to non target organs such as liver, spleen, kidney. Nowadays, the variety of beta emitters used in RSV ranges between 0.34 MeV - 0.33 mm penetration in tissue ( 169 Er) and 2.27 MeV - 3.6 mm penetration in tissue ( 90 Y). The half life of these isotopes goes from 2.3 hours ( 165 Dy) to 27.8 days ( 51 Cr). The selection criterion on which radionuclide should be used, in modern clinics, depends on which joints are to be treated. Thus, the smaller the joint, the lowest should be the energy of the beta emitted and the penetration in soft tissue of these particles. This leads to the use of fixed radionuclides and doses for each kind of joint. In the Isotopes Centre, we've been carrying on studies for the development of radiopharmaceuticals for the radiosynoviortheses treatment and focused our attention in the following radionuclides: 32 P, 90 Y, 188 Re, 177 Lu, 51 Cr, 153 Sm and 169 Er. The main objective of this paper was to obtain the absorbed dose profiles for radionuclides of frequent or potential use in radiosynoviortheses. These profiles reveal the absorbed dose imparted per unit activity of injected radionuclide (Gy/h*MBq) in the synovial membrane and the articular cartilage. The researched radionuclides were those previously mentioned. Also were calculated the therapeutic range of each radionuclides in synovial tissue. The therapeutic range is defined as the deepness at which the absorbed dose equals the 10 % of the maximum dose deposited in the synovial surface. This range determines the synovial thickness that can be sufficiently irradiated and thus successfully treated. The synovial membrane model consisted on a cylinder with the source uniformly distributed in its volume. This

PRODUTIVIDADE DE CAPIM-MOMBAÇA (Panicum maximum, COM DIFERENTES DOSES DE BIOFERTILIZANTE / MOMBAÇA GRASS PRODUCTIVITY (Panicum maximum, WITH DIFFERENT DOSES OF BIOFERTILIZER

Directory of Open Access Journals (Sweden)

A. Simonetti

2016-03-01

Full Text Available O presente estudo teve por objetivo verificar a influência da aplicação do dejeto de bovino leiteiro tratados em biodigestores anaeróbios, na forma de biofertilizante, sobre a produtividade da capim Mombaça, em condições de sequeiro.  O trabalho foi conduzido no Instituto de Biotecnologia – IBIOTEC, pertencente à UNIARA, Araraquara – SP. Para obtenção do biofertilizante, foi feita a diluição dos dejetos em água e armazenado em um biodigestor modelo indiano de fibra de vidro com capacidade útil de 1000 L, instalado no referido instituto. As fertilizações foram feitas a lanço após cada rebaixamento das parcelas. O delineamento utilizado foi em blocos casualizados, com quatro tratamentos e quatro repetições, com diferentes doses do biofertilizante, sendo: 0; 50m³; 100m³ e 200m³/ha-1.  As variáveis avaliadas foram: altura, produção por hectare (matéria seca e matéria verde, e qualidade bromatológica. Foram observados que os tratamentos que receberam a maior dosagem de biofertilizante, apresentaram maiores valores para produtividade Matéria Seca, Matéria Verde e teor de proteína. Conclui-se que a aplicação de biofertilizante é benéfico ao sistema de pastagem, porém suas doses devem ser estudadas e a sua resposta na produção pode obtidas a longo prazo.

Final report of evaluation of dose and measurement of radon concentration

International Nuclear Information System (INIS)

1998-03-01

A mean annual exposure to radon daughters in indoor air was estimated on the basis of measurement of radon concentration in indoor air in Japan from fiscal 1992 to 1996. Doses were estimated by UNSCEAR method. The representative values in this report show the mean values in whole Japan. Each dose in the local area was different reflecting the different concentration of radon daughters. However, the same parameters were used in each area. When mean annual dose of radon daughters was estimated, we used 15.5 Bq m -3 mean annual exposure to radon daughters in indoor air, 5 Bq m -3 that in outdoor air, 0.4 the equilibrium factor indoor, 0.6 the equilibrium factor outdoor and 0.9 of P. The model of UNSCEAR based on these above values gave 0.46 mSv y -1 mean annual dose of radon daughters which were consisted of from 0.38 mSv y -1 in Kanto district to 0.52 mSv y -1 Kyushu, Okinawa district. (S.Y.)

Final report of evaluation of dose and measurement of radon concentration

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-03-01

A mean annual exposure to radon daughters in indoor air was estimated on the basis of measurement of radon concentration in indoor air in Japan from fiscal 1992 to 1996. Doses were estimated by UNSCEAR method. The representative values in this report show the mean values in whole Japan. Each dose in the local area was different reflecting the different concentration of radon daughters. However, the same parameters were used in each area. When mean annual dose of radon daughters was estimated, we used 15.5 Bq m{sup -3} mean annual exposure to radon daughters in indoor air, 5 Bq m{sup -3} that in outdoor air, 0.4 the equilibrium factor indoor, 0.6 the equilibrium factor outdoor and 0.9 of P. The model of UNSCEAR based on these above values gave 0.46 mSv y{sup -1} mean annual dose of radon daughters which were consisted of from 0.38 mSv y{sup -1} in Kanto district to 0.52 mSv y{sup -1} Kyushu, Okinawa district. (S.Y.)

Receptor-mediated radionuclide therapy with 90Y-DOTATOC in association with amino acid infusion: a phase I study

International Nuclear Information System (INIS)

Bodei, Lisa; Zoboli, Stefania; Grana, Chiara; Bartolomei, Mirco; Rocca, Paola; Caracciolo, Maurizio; Chinol, Marco; Paganelli, Giovanni; Cremonesi, Marta; Maecke, Helmut R.

2003-01-01

The aim of this study was to determine the maximum tolerated dose of 90 Y-DOTATOC per cycle administered in association with amino acid solution as kidney protection in patients with somatostatin receptor-positive tumours. Forty patients in eight groups received two cycles of 90 Y-DOTATOC, with activity increased by 0.37 GBq per group, starting at 2.96 and terminating at 5.55 GBq. All patients received lysine ± arginine infusion immediately before and after therapy. Forty-eight percent developed acute grade I-II gastrointestinal toxicity (nausea and vomiting) after amino acid infusion whereas no acute adverse reactions occurred after 90 Y-DOTATOC injection up to 5.55 GBq/cycle. Grade III haematological toxicity occurred in three of seven (43%) patients receiving 5.18 GBq, which was defined as the maximum tolerable activity per cycle. Objective therapeutic responses occurred. Five GBq per cycle is the recommended dosage of 90 Y-DOTATOC when amino acids are given to protect the kidneys. Although no patients developed acute kidney toxicity, delayed kidney toxicity remains a major concern, limiting the cumulative dose to 25 Gy. The way forward with this treatment would seem to be to identify more effective renal protective agents, in order to be able to increase the cumulative injectable activity and hence tumour dose. (orig.)

Maximum likelihood as a common computational framework in tomotherapy

International Nuclear Information System (INIS)

Olivera, G.H.; Shepard, D.M.; Reckwerdt, P.J.; Ruchala, K.; Zachman, J.; Fitchard, E.E.; Mackie, T.R.

1998-01-01

Tomotherapy is a dose delivery technique using helical or axial intensity modulated beams. One of the strengths of the tomotherapy concept is that it can incorporate a number of processes into a single piece of equipment. These processes include treatment optimization planning, dose reconstruction and kilovoltage/megavoltage image reconstruction. A common computational technique that could be used for all of these processes would be very appealing. The maximum likelihood estimator, originally developed for emission tomography, can serve as a useful tool in imaging and radiotherapy. We believe that this approach can play an important role in the processes of optimization planning, dose reconstruction and kilovoltage and/or megavoltage image reconstruction. These processes involve computations that require comparable physical methods. They are also based on equivalent assumptions, and they have similar mathematical solutions. As a result, the maximum likelihood approach is able to provide a common framework for all three of these computational problems. We will demonstrate how maximum likelihood methods can be applied to optimization planning, dose reconstruction and megavoltage image reconstruction in tomotherapy. Results for planning optimization, dose reconstruction and megavoltage image reconstruction will be presented. Strengths and weaknesses of the methodology are analysed. Future directions for this work are also suggested. (author)

47 CFR 1.1507 - Rulemaking on maximum rates for attorney fees.

Science.gov (United States)

2010-10-01

... 47 Telecommunication 1 2010-10-01 2010-10-01 false Rulemaking on maximum rates for attorney fees... § 1.1507 Rulemaking on maximum rates for attorney fees. (a) If warranted by an increase in the cost of... types of proceedings), the Commission may adopt regulations providing that attorney fees may be awarded...

Dose estimates in Japan following the Chernobyl reactor accident

International Nuclear Information System (INIS)

Togawa, Orihiko; Homma, Toshimitsu; Iijima, Toshinori; Midorikawa, Yuji.

1988-02-01

Estimates have been made of the maximum individual doses and the collective doses in Japan following the Chernobyl reactor accident. Based on the measured data of ground deposition and radionuclide concentrations in air, raw milk, milk on sale and leafy vegetables, the doses from some significant radionuclides were calculated for 5 typical exposure pathways; cloudshine, groundshine, inhalation, ingestion of milk and leafy vegetables. The maximum effective dose equivalents for hypothetical individuals were calculated to be 1.8 mrem for adults, 3.7 mrem for children and 6.0 mrem for infants. The collective effective dose equivalent in Japan was estimated to be 5.8 x 10 4 man · rem; 0.50 mrem of the average dose per capita. (author)

Determination of Radon Level in Drinking Water in Mehriz Villages and Evaluation the Annual Effective Absorbed Dose

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Mohammad Malakootian

2015-03-01

Results: Radon concentrations of samples ranged from 0.187 BqL-1 to 14.8 BqL-1.These results were related to samples No.12 and 9 and also to aqueducts of Tang-e-chenar and Malekabad village respectively. Based on the amount of radon in the sample, the lowest annual effective absorbed dose through drinking water or breathing(In an environment where water was used was 0.0005msv/y and the maximum amount was 0.04msv/y. Conclusion: Apart from samples No.9 and 16 that were elated to the aqueduct of Malekabad village and a private well in Dare Miankoohvillagehaving48 persons as total population, Radon concentrations of other samples used by people of Mehriz villages as drinking water was low and less than permitted limit set by the Environmental Protection Agency of United States of America.

Radiation-induced rib fracture after stereotactic body radiotherapy with a total dose of 54-56 Gy given in 9-7 fractions for patients with peripheral lung tumor: impact of maximum dose and fraction size.

Science.gov (United States)

Aoki, Masahiko; Sato, Mariko; Hirose, Katsumi; Akimoto, Hiroyoshi; Kawaguchi, Hideo; Hatayama, Yoshiomi; Ono, Shuichi; Takai, Yoshihiro

2015-04-22

Radiation-induced rib fracture after stereotactic body radiotherapy (SBRT) for lung cancer has been recently reported. However, incidence of radiation-induced rib fracture after SBRT using moderate fraction sizes with a long-term follow-up time are not clarified. We examined incidence and risk factors of radiation-induced rib fracture after SBRT using moderate fraction sizes for the patients with peripherally located lung tumor. During 2003-2008, 41 patients with 42 lung tumors were treated with SBRT to 54-56 Gy in 9-7 fractions. The endpoint in the study was radiation-induced rib fracture detected by CT scan after the treatment. All ribs where the irradiated doses were more than 80% of prescribed dose were selected and contoured to build the dose-volume histograms (DVHs). Comparisons of the several factors obtained from the DVHs and the probabilities of rib fracture calculated by Kaplan-Meier method were performed in the study. Median follow-up time was 68 months. Among 75 contoured ribs, 23 rib fractures were observed in 34% of the patients during 16-48 months after SBRT, however, no patients complained of chest wall pain. The 4-year probabilities of rib fracture for maximum dose of ribs (Dmax) more than and less than 54 Gy were 47.7% and 12.9% (p = 0.0184), and for fraction size of 6, 7 and 8 Gy were 19.5%, 31.2% and 55.7% (p = 0.0458), respectively. Other factors, such as D2cc, mean dose of ribs, V10-55, age, sex, and planning target volume were not significantly different. The doses and fractionations used in this study resulted in no clinically significant rib fractures for this population, but that higher Dmax and dose per fraction treatments resulted in an increase in asymptomatic grade 1 rib fractures.

Measurements of the Cosmic Rays Dose at Different Altitudes of Iran

International Nuclear Information System (INIS)

Faghihi, R.; Mehdizadeh, S.; Jafarizadeh, M.; Sina, S.; Zehtabian, M.; Taheri, M.

2012-01-01

The amount of cosmic rays varies widely with the altitude, latitude and longitude in each region. In this study, the radiation doses due to the cosmic rays were estimated in two steps: in the first step, the neutron and gamma components of the radiation dose were measured for a roundtrip flight on 3 flight routes (Shiraz-Asaluye, Asaluye-Rasht and Shiraz-Mashhad) using a gamma-tracer photon detector and a Thyac 190 N, neutron detector. The minimum values of the measured gamma and neutron doses of 0.15 and 0.04μSv were measured on the Asaluyeh-Shiraz route at the lowest altitude of 19000 ft, while for Rasht-Asaluyeh route at an altitude of 35000 ft those values were found to be 2.52 and 1.09 mSv, respectively. In the second step, a number of air crew members were equipped with thermoluminescence dosimeters (TLD cards) for evaluating the gamma dose and polycarbonate dosimeters (SSNTD) for assessing the neutron dose for one year. The measured value of the annual effective dose received by the crew ranged between 0.5 mSv/y and 1.16 mSv/y, with an average of 0.9 mSv/y for the gamma component and between 0.37 mSv/y and 0.77 mSv/y with an average of 0.61 mSv/y for the neutron component. The results of this investigation are comparable with the investigations that have been conducted in other countries. For instance in UK, the reported annual effective dose of air crew is about 2 mSv, and in Canada, it is estimated to be between 1 to 5 mSv, depending on the flight situations (such as the latitude and longitude of the cities, the flight altitude, etc).

New view on In{sub x}Ga{sub 1-x}N{sub y}As{sub 1-y}alloys

Energy Technology Data Exchange (ETDEWEB)

Elyukhin, Vyacheslav A. [Departamento de Ingenieria Electrica, Centro de Investigacion y de Estudios Avanzados del Instituto Politecnico Nacional, Avenida Instituto Politecnico Nacional 2508, 07360, Mexico (Mexico)

2015-12-15

Semiconductors with isoelectronic centers are actively studied to fabricate arrays of identical single photon emitters. Self-assembling of 4N10In and 1N4In clusters in GaAs-rich In{sub x}Ga{sub 1-x}N{sub y}As{sub 1-y} is represented. All or almost all In atoms are in 4N10In clusters from 0 to 800 C in In{sub x}Ga{sub 1-x}N{sub y}As{sub 1-y} with x = 1 x 10{sup -4}, y = 1 x 10{sup -4} and x = 1 x 10{sup -5}, y = 1 x 10{sup -5}. All or almost all nitrogen atoms are in 1N4In clusters if x = 0.01, y = 1 x 10{sup -4} and x = 1 x 10{sup -3}, y = 1 x 10{sup -6}. There are both types of clusters in alloys with x = 5 x 10{sup -5}, y = 5 x 10{sup -7}; x = 2 x 10{sup -4}, y = 2 x 10{sup -6}; x = 1 x 10{sup -4}, y = 1 x 10{sup -5} and x = 2 x 10{sup -3}, y = 2 x 10{sup -4} and portions of nitrogen atoms in clusters depend on the composition and temperature. Thus, In{sub x}Ga{sub 1-x}N{sub y}As{sub 1-y} are promising semiconductors to obtain arrays of identical isoelectronic clusters with the desirable density. (copyright 2015 WILEY-VCH Verlag GmbH and Co. KGaA, Weinheim)

Impact of the activity calculation method used in transarterial radioembolization: a dosimetric comparison between 90Y-SIRSphere and 90Y-TheraSphere therapy.

Science.gov (United States)

Jha, Ashish K; Mithun, Sneha; Purandare, Nilendu C; Shah, Sneha A; Agrawal, Archi; Kulkarni, Suyash S; Shetty, Nitin; Rangarajan, Venkatesh

2016-09-01

Transarterial radioembolization is used to treat primary and secondary liver malignancies. Two commercially available drugs are utilized for the purpose. The aim of our study is to compare the radiation dose delivered to the tumor by these drugs. This study included 86 patients (M : F - 7.6 : 1, median age=50.5 years), 46 patients were treated by Y-TheraSphere and 42 patients were treated by Y-SIRSphere. Activity administered in Y-TheraSphere and Y-SIRSphere was calculated using a modified partition model and a modified body surface area model, respectively. The radiation dose delivered by two drugs was calculated and compared in our study. Activity administered in Y-TheraSphere was significantly higher than that of Y-SIRSphere. Hence, the radiation dose delivered to the tumor by Y-SIRSphere was significantly lower (58.4%) than that of Y-TheraSphere (P=0.000). As the radiation dose delivered by Y-SIRSphere was lower than Y-TheraSphere, we believe that the formula for Y-SIRSphere activity calculation needs to be modified so that the optimal dose can be delivered to the tumor.

Uncertainty and variability in updated estimates of potential dose and risk at a US Nuclear Test Site - Bikini Atoll

International Nuclear Information System (INIS)

Bogen, K.T.; Conrado, C.L.; Robison, W.L.

1997-01-01

Uncertainty and interindividual variability were assessed in estimated doses for a rehabilitation scenario for Bikini Island at Bikini Atoll, in which the top 40 cm of soil would be removed in the housing and village area, and the rest of the island would be treated with potassium fertilizer, prior to an assumed resettlement date of 1999. Doses were estimated for ingested 137 Cs and 90 Sr, external gamma-exposure, and inhalation+ingestion of 241 Am + 239+240 Pu. Two dietary scenarios were considered: imported foods are available (IA); imported foods are unavailable with only local foods consumed (IUA). After ∼5 y of Bikini residence under either IA or IUA assumptions, upper and lower 95% confidence limits on interindividual variability in calculated dose were estimated to lie within a ∼threefold factor of its in population-average value; upper and lower 95% confidence limits on uncertainty in calculated dose were estimated to lie within a ∼twofold factor of its expected value. For reference, the expected values of population-average dose at age 70 y were estimated to be 16 and 52 mSv under IA and IUA dietary assumptions, respectively. Assuming that 200 Bikini resettlers would be exposed to local foods (under both IA and IUA assumptions), the maximum 1-y dose received by any Bikini resident is most likely to be approximately 2 and 8 mSv under the IA and IUA assumptions, respectively. Under the most likely dietary scenario, involving access to imported foods, this analysis indicates that it is most likely that no additional cancer fatalities (above those normally expected) would arise from the increased radiation exposures considered. 33 refs., 4 figs., 4 tabs

Determination of radon concentration in drinking water resources of villages nearby Lalehzar fault and evaluation the annual effective dose

International Nuclear Information System (INIS)

Mohammad Malakootian; Zahra Darabi Fard; Mojtaba Rahimi

2015-01-01

The radon concentration has been measured in 44 drinking water resources, in villages nearby Lalehzar fault in winter 2014. Some samples showed a higher concentration of radon surpassing limit set by EPA. Further, a sample was taken from water distribution networks for these sources of water. Soluble radon concentration was measured by RAD7 device. Range radon concentration was 26.88 and 0.74 BqL -1 respectively. The maximum and minimum annual effective dose for adults was estimated at 52.7 and 2.29 µSvY -1 , respectively. Reducing radon from water before use is recommended to improve public health. (author)

ESTIMATION OF EXPOSURE DOSES FOR THE SAFE MANAGEMENT OF NORM WASTE DISPOSAL.

Science.gov (United States)

Jeong, Jongtae; Ko, Nak Yul; Cho, Dong-Keun; Baik, Min Hoon; Yoon, Ki-Hoon

2018-03-16

Naturally occurring radioactive materials (NORM) wastes with different radiological characteristics are generated in several industries. The appropriate options for NORM waste management including disposal options should be discussed and established based on the act and regulation guidelines. Several studies calculated the exposure dose and mass of NORM waste to be disposed in landfill site by considering the activity concentration level and exposure dose. In 2012, the Korean government promulgated an act on the safety control of NORM around living environments to protect human health and the environment. For the successful implementation of this act, we suggest a reference design for a landfill for the disposal of NORM waste. Based on this reference landfill, we estimate the maximum exposure doses and the relative impact of each pathway to exposure dose for three scenarios: a reference scenario, an ingestion pathway exclusion scenario, and a low leach rate scenario. Also, we estimate the possible quantity of NORM waste disposal into a landfill as a function of the activity concentration level of U series, Th series and 40K and two kinds of exposure dose levels, 1 and 0.3 mSv/y. The results of this study can be used to support the establishment of technical bases of the management strategy for the safe disposal of NORM waste.

Nanocrystalline La1-xSrxCo1-yFe yO3 perovskites fabricated by the micro-emulsion route for high frequency response devices fabrications

KAUST Repository

Azhar Khan, Muhammad

2014-09-01

Nanocrystalline La1-xSrxCo1-yFe yO3 (x=0.00-0.60) perovskites were fabricated by a cheap economic route (i.e. micro-emulsion method) and characterized by thermogravimetric analysis (TGA), X-ray diffraction (XRD), fourier transform infrared (FTIR) spectroscopy, and scanning electron microscopy (SEM). TGA analysis showed ~35% weight loss. The crystallite size determined by XRD and SEM ranged from 30 to 80 nm and ~30 to 50 nm, respectively. The dielectric behavior was evaluated in the range of 1.0×106 Hz to 3.0×10 9 Hz at 298 K, the dielectric parameters resulting appreciably enhanced by co-doping with Sr and Fe. The maximum dielectric parameters (ε′=103.35, ε″=58.92 and tan δ=0.57) were observed for La0.4Sr0.6Co0.4Fe0.6O 3 at 15×106 Hz. Results suggest the potential use of these nanocrystalline perovskites in GHz-operated microwave devices. © 2014 Elsevier Ltd and Techna Group S.r.l.

SU-F-19A-01: APBI Brachytherapy Treatment Planning: The Impact of Heterogeneous Dose Calculations

International Nuclear Information System (INIS)

Loupot, S; Han, T; Salehpour, M; Gifford, K

2014-01-01

Purpose: To quantify the difference in dose to PTV-EVAL and OARs (skin and rib) as calculated by (TG43) and heterogeneous calculations (CCC). Methods: 25 patient plans (5 Contura and 20 SAVI) were selected for analysis. Clinical dose distributions were computed with a commercially available treatment planning algorithm (TG43-D-(w,w)) and then recomputed with a pre-clinical collapsed cone convolution algorithm (CCCD-( m,m)). PTV-EVAL coverage (V90%, V95%), and rib and skin maximum dose were compared via percent difference. Differences in dose to normal tissue (V150cc, V200cc of PTV-EVAL) were also compared. Changes in coverage and maximum dose to organs at risk are reported in percent change, (100*(TG43 − CCC) / TG43)), and changes in maximum dose to normal tissue are absolute change in cc (TG43 − CCC). Results: Mean differences in V90, V95, V150, and V200 for the SAVI cases were −0.2%, −0.4%, −0.03cc, and −0.14cc, respectively, with maximum differences of −0.78%, −1.7%, 1.28cc, and 1.01cc, respectively. Mean differences in the 0.1cc dose to the rib and skin were −1.4% and −0.22%, respectively, with maximum differences of −4.5% and 16%, respectively. Mean differences in V90, V95, V150, and V200 for the Contura cases were −1.2%, −2.1%, −1.8cc, and −0.59cc, respectively, with maximum differences of −2.0%, −3.16%, −2.9cc, and −0.76cc, respectively. Mean differences in the 0.1cc dose to the rib and skin were −2.6% and −3.9%, respectively, with maximum differences of −3.2% and −5.7%, respectively. Conclusion: The effects of translating clinical knowledge based on D-(w,w) to plans reported in D-(m,m) are minimal (2% or less) on average, but vary based on the type and placement of the device, source, and heterogeneity information

Dose assessments for SFR 1

International Nuclear Information System (INIS)

Bergstroem, Ulla; Avila, Rodolfo; Ekstroem, Per-Anders; Cruz, Idalmis de la

2008-05-01

Following a review by the Swedish regulatory authorities of the safety analysis of the SFR 1 disposal facility for low and intermediate level waste, SKB has prepared an updated safety analysis, SAR-08. This report presents estimations of annual doses to the most exposed groups from potential radionuclide releases from the SFR 1 repository for a number of calculation cases, selected using a systematic approach for identifying relevant scenarios for the safety analysis. The dose estimates can be used for demonstrating that the long term safety of the repository is in compliance with the regulatory requirements. In particular, the mean values of the annual doses can be used to estimate the expected risks to the most exposed individuals, which can then be compared with the regulatory risk criteria for human health. The conversion from doses to risks is performed in the main report. For one scenario however, where the effects of an earthquake taking place close to the repository are analysed, risk calculations are presented in this report. In addition, prediction of concentrations of radionuclides in environmental media, such as water and soil, are compared with concentration limits suggested by the Erica-project as a base for estimating potential effects on the environment. The assessment of the impact on non-human biota showed that the potential impact is negligible. Committed collective dose for an integration period of 10,000 years for releases occurring during the first thousand years after closure are also calculated. The collective dose commitment was estimated to be 8 manSv. The dose calculations were carried out for a period of 100,000 years, which was sufficient to observe peak doses in all scenarios considered. Releases to the landscape and to a well were considered. The peaks of the mean annual doses from releases to the landscape are associated with C-14 releases to a future lake around year 5,000 AD. In the case of releases to a well, the peak annual doses

Dose assessments for SFR 1

Energy Technology Data Exchange (ETDEWEB)

Bergstroem, Ulla (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)); Avila, Rodolfo; Ekstroem, Per-Anders; Cruz, Idalmis de la (Facilia AB, Bromma (Sweden))

2008-06-15

Following a review by the Swedish regulatory authorities of the safety analysis of the SFR 1 disposal facility for low and intermediate level waste, SKB has prepared an updated safety analysis, SAR-08. This report presents estimations of annual doses to the most exposed groups from potential radionuclide releases from the SFR 1 repository for a number of calculation cases, selected using a systematic approach for identifying relevant scenarios for the safety analysis. The dose estimates can be used for demonstrating that the long term safety of the repository is in compliance with the regulatory requirements. In particular, the mean values of the annual doses can be used to estimate the expected risks to the most exposed individuals, which can then be compared with the regulatory risk criteria for human health. The conversion from doses to risks is performed in the main report. For one scenario however, where the effects of an earthquake taking place close to the repository are analysed, risk calculations are presented in this report. In addition, prediction of concentrations of radionuclides in environmental media, such as water and soil, are compared with concentration limits suggested by the Erica-project as a base for estimating potential effects on the environment. The assessment of the impact on non-human biota showed that the potential impact is negligible. Committed collective dose for an integration period of 10,000 years for releases occurring during the first thousand years after closure are also calculated. The collective dose commitment was estimated to be 8 manSv. The dose calculations were carried out for a period of 100,000 years, which was sufficient to observe peak doses in all scenarios considered. Releases to the landscape and to a well were considered. The peaks of the mean annual doses from releases to the landscape are associated with C-14 releases to a future lake around year 5,000 AD. In the case of releases to a well, the peak annual doses

30 CFR 77.902-1 - Fail safe ground check circuits; maximum voltage.

Science.gov (United States)

2010-07-01

... voltage. 77.902-1 Section 77.902-1 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF... OF UNDERGROUND COAL MINES Low- and Medium-Voltage Alternating Current Circuits § 77.902-1 Fail safe ground check circuits; maximum voltage. The maximum voltage used for ground check circuits under § 77.902...

30 CFR 77.803-1 - Fail safe ground check circuits; maximum voltage.

Science.gov (United States)

2010-07-01

... voltage. 77.803-1 Section 77.803-1 Mineral Resources MINE SAFETY AND HEALTH ADMINISTRATION, DEPARTMENT OF... OF UNDERGROUND COAL MINES Surface High-Voltage Distribution § 77.803-1 Fail safe ground check circuits; maximum voltage. The maximum voltage used for ground check circuits under § 77.803 shall not...

Cambios en la estructura, la población y la composición de 19 accesiones de Panicum maximum sometidas a pastoreo CIAT-184 Changes in the structure, population and composition of 19 Panicum maximum accessions under grazing conditions

Directory of Open Access Journals (Sweden)

R Machado

2012-06-01

Full Text Available Este trabajo tuvo como objetivo caracterizar los cambios y la tendencia de indicadores relacionados con la estructura, la población y la composición en 19 accesiones de Panicum maximum cuando fueron sometidas a condiciones de pastoreo simulado. Las rotaciones se hicieron cada 32-40 días en el periodo lluvioso y 60-70 días en el poco lluvioso, con intensidad de pastoreo de 80-135 UGM/ha/día (los dos primeros años y 120-160 UGM/ha/día (tercer año. Se utilizó un diseño de bloques al azar con tres repeticiones. Aunque en todos los tratamientos disminuyó la relación vástagos vivos/vástagos muertos, este cociente fue superior a uno, por lo que el ritmo de sustitución de vástagos fue favorable. En el 84,2% de los tratamientos se incrementó el número de macollas con relación a el estatus inicial. El porcentaje de arvenses aumentó con las rotaciones, pero ninguno de los tratamientos alcanzó un estado de deterioro avanzado. En este indicador se destacaron los tipos gigantes CIH-13, SIH-697, CIH-3, CC-1146 y SIH-10, con valores que variaron entre 4,6 y 14,1%, así como los tipos medianos CIH-15 y Tardío pequeño, con 10 y 12,3%, respectivamente. Se concluye que el germoplasma evaluado mostró valores adecuados, en función de los indicadores relacionados con la estructura de la macolla, la población y el porcentaje de invasión de las especies arvenses, aunque se identificó un alto contraste entre los tipos gigantes y medianos y dentro de estos grupos. Se sugiere analizar el resto de los indicadores productivos y con ello determinar los tipos más sobresalientes, sobre la base de los resultados en todos los indicadores incluidos.The objective of this work was to characterize the changes and trend of indicators related to the structure, population and composition in 19 Panicum maximum accessions under simulated grazing conditions. The rotations took place every 32-40 days in the rainy season and 60-70 days in the dry season, with

External dose reconstruction in tooth enamel of Techa riverside residents

Energy Technology Data Exchange (ETDEWEB)

Shishkina, E.A.; Volchkova, A.Yu.; Krivoschapov, V.A.; Degteva, M.O. [Urals Research Center for Radiation Medicine, Chelyabinsk (Russian Federation); Timofeev, Y.S.; Zalyapin, V.I. [Southern Urals State University, Chelyabinsk (Russian Federation); Fattibene, P.; Della Monaca, S.; De Coste, V. [Istituto Superiore di Sanita e Istituto Nazionale di Fisica Nucleare, Rome (Italy); Wieser, A. [Helmholtz Zentrum Muenchen, German Research Centre for Environmental Health, Neuherberg (Germany); Ivanov, D.V. [M.N. Mikheev Institute of Metal Physics, Ural Division of the Russian Academy of Sciences, Ekaterinburg (Russian Federation); Ural Federal University, Yekaterinburg (Russian Federation); Anspaugh, L.R. [University of Utah, Salt Lake City, UT (United States)

2016-11-15

This study summarizes the 20-year efforts for dose reconstruction in tooth enamel of the Techa riverside residents exposed to ionizing radiation as a result of radionuclide releases into the river in 1949-1956. It represents the first combined analysis of all the data available on EPR dosimetry with teeth of permanent residents of the Techa riverside territory. Results of electron paramagnetic resonance (EPR) measurements of 302 teeth donated by 173 individuals living permanently in Techa riverside settlements over the period of 1950-1952 were analyzed. These people were residents of villages located at the free-flowing river stream or at the banks of stagnant reservoirs such as ponds or blind river forks. Cumulative absorbed doses measured using EPR are from several sources of exposure, viz., background radiation, internal exposure due to bone-seeking radionuclides ({sup 89}Sr, {sup 90}Sr/{sup 90}Y), internal exposure due to {sup 137}Cs/{sup 137m}Ba incorporated in soft tissues, and anthropogenic external exposure. The purpose of the present study was to evaluate the contribution of different sources of enamel exposure and to deduce external doses to be used for validation of the Techa River Dosimetry System (TRDS). Since various EPR methods were used, harmonization of these methods was critical. Overall, the mean cumulative background dose was found to be 63 ± 47 mGy; cumulative internal doses due to {sup 89}Sr and {sup 90}Sr/{sup 90}Y were within the range of 10-110 mGy; cumulative internal doses due to {sup 137}Cs/{sup 137m}Ba depend on the distance from the site of releases and varied from 1 mGy up to 90 mGy; mean external doses were maximum for settlements located at the banks of stagnant reservoirs (∝500 mGy); in contrast, external doses for settlements located along the free-flowing river stream did not exceed 160 mGy and decreased downstream with increasing distance from the site of release. External enamel doses calculated using the TRDS code and

Considerations on the establishment of maximum permissible exposure of man

International Nuclear Information System (INIS)

Jacobi, W.

1974-01-01

An attempt is made in the information lecture to give a quantitative analysis of the somatic radiation risk and to illustrate a concept to fix dose limiting values. Of primary importance is the limiting values. Of primary importance is the limiting value of the radiation exposure to the whole population. By consequential application of the risk concept, the following points are considered: 1) Definition of the risk for radiation late damages (cancer, leukemia); 2) relationship between radiation dose and thus caused radiation risk; 3) radiation risk and the dose limiting values at the time; 4) criteria for the maximum acceptable radiation risk; 5) limiting value which can be expected at the time. (HP/LH) [de

1. Dose reduction of occupational exposure in cardiac catheterization and angiography

Energy Technology Data Exchange (ETDEWEB)

Saito, Yoshimi [Kyushu Kosei Nenkin Hospital, Kitakyushu, Fukuoka (Japan); Matsumoto, Kunihiro; Fujihashi, Hiroshi; Umeda, Kazuhiro

2000-08-01

Occupational exposure to scattered radiation and protective equipment was assessed in 4 medical institutions in Kyushu, Japan. The areas where scattered radiation occurred, the scattered radiation dose in the operator's position, fluoroscopy time, the number of cinematography sessions, and annual number of patients were assessed, and the annual scattered radiation dose to the operator was estimated. Approximately 90% of scattered radiation was generated by the subject and the collimator. Measurement of scattered radiation during coronary arteriography yielded a dose of 255-1200 [{mu}Sv/hr.] during fluoroscopy and 3.8-26.7 [{mu}Sv/10 sec.] during radiography. The duration of fluoroscopy for ablation was much longer than during general examinations and PTCA, suggesting a possible contribution to occupational exposure. The data for the past 5 years show no marked change in total number of catheterizations, but the number of ablations has rapidly increased. Ablation requires specific skills, and thus it is frequently performed by only a few staff members, resulting in exposure being concentrated in a few specific persons. The estimated doses of scattered radiation to the eyes and thyroid gland, which are assumed to be the most highly exposed sites, were 116.2 [mSv/year] during fluoroscopy and 8.9 [mSv/year] during radiography, for a total of 125.1 [mSv/year]. This dose is very close to the maximum occupational exposure dose recommended by International Commission on Radiological Protection (ICRP), i.e., 150 [mSv/year]. A protective device that does not impose a burden on the operator or limit the functions of x-ray units was installed on top of the examining table as a measure to reduce the occupational dose. In an experiment using this device the scattered radiation dose during inguinal puncture decreased from 0.8 [mSv/hr.] to 0.02 [mSv/hr.], and the shielding rate was 2.5%. The dose was reduced 97.5%. The authors conclude that radiological personnel must make

Field size and dose distribution of electron beam

International Nuclear Information System (INIS)

Kang, Wee Saing

1980-01-01

The author concerns some relations between the field size and dose distribution of electron beams. The doses of electron beams are measured by either an ion chamber with an electrometer or by film for dosimetry. We analyzes qualitatively some relations; the energy of incident electron beams and depths of maximum dose, field sizes of electron beams and depth of maximum dose, field size and scatter factor, electron energy and scatter factor, collimator shape and scatter factor, electron energy and surface dose, field size and surface dose, field size and central axis depth dose, and field size and practical range. He meets with some results. They are that the field size of electron beam has influence on the depth of maximum dose, scatter factor, surface dose and central axis depth dose, scatter factor depends on the field size and energy of electron beam, and the shape of the collimator, and the depth of maximum dose and the surface dose depend on the energy of electron beam, but the practical range of electron beam is independent of field size

Whole-remnant and maximum-voxel SPECT/CT dosimetry in {sup 131}I-NaI treatments of differentiated thyroid cancer

Energy Technology Data Exchange (ETDEWEB)

Mínguez, Pablo, E-mail: pablo.minguezgabina@osakidetza.eus [Department of Medical Radiation Physics, Lund University, Lund 22185, Sweden and Department of Medical Physics, Gurutzeta/Cruces University Hospital, Barakaldo 48903 (Spain); Flux, Glenn [Joint Department of Physics, Royal Marsden NHS Foundation Trust and Institute of Cancer Research, Sutton SM2 5PT (United Kingdom); Genollá, José; Delgado, Alejandro; Rodeño, Emilia [Department of Nuclear Medicine, Gurutzeta/Cruces University Hospital, Barakaldo 48903 (Spain); Sjögreen Gleisner, Katarina [Department of Medical Radiation Physics, Lund University, Lund 22185 (Sweden)

2016-10-15

Purpose: To investigate the possible differences between SPECT/CT based whole-remnant and maximum-voxel dosimetry in patients receiving radio-iodine ablation treatment of differentiated thyroid cancer (DTC). Methods: Eighteen DTC patients were administered 1.11 GBq of {sup 131}I-NaI after near-total thyroidectomy and rhTSH stimulation. Two patients had two remnants, so in total dosimetry was performed for 20 sites. Three SPECT/CT scans were performed for each patient at 1, 2, and 3–7 days after administration. The activity, the remnant mass, and the maximum-voxel activity were determined from these images and from a recovery-coefficient curve derived from experimental phantom measurements. The cumulated activity was estimated using trapezoidal-exponential integration. Finally, the absorbed dose was calculated using S-values for unit-density spheres in whole-remnant dosimetry and S-values for voxels in maximum-voxel dosimetry. Results: The mean absorbed dose obtained from whole-remnant dosimetry was 40 Gy (range 2–176 Gy) and from maximum-voxel dosimetry 34 Gy (range 2–145 Gy). For any given patient, the activity concentrations for each of the three time-points were approximately the same for the two methods. The effective half-lives varied (R = 0.865), mainly due to discrepancies in estimation of the longer effective half-lives. On average, absorbed doses obtained from whole-remnant dosimetry were 1.2 ± 0.2 (1 SD) higher than for maximum-voxel dosimetry, mainly due to differences in the S-values. The method-related differences were however small in comparison to the wide range of absorbed doses obtained in patients. Conclusions: Simple and consistent procedures for SPECT/CT based whole-volume and maximum-voxel dosimetry have been described, both based on experimentally determined recovery coefficients. Generally the results from the two approaches are consistent, although there is a small, systematic difference in the absorbed dose due to differences in the

Time and dose-related changes in the thickness of pig skin after irradiation with single doses of [sup 90]Sr/[sup 90]Y [beta]-rays

Energy Technology Data Exchange (ETDEWEB)

Rezvani, M.; Hamlet, R.; Hopewell, J.W.; Sieber, V.K. (Churchill Hospital, Oxford (United Kingdom))

1994-04-01

Time-related changes in pig skin thickness have been evaluated using a non-invasive ultrasound technique after exposure to a range of single doses of [sup 90]Sr/[sup 90]Yr [beta]-rays. The reduction in relative skin thickness developed in two distinct phases: the first was between 12 and 20 weeks postirradiation. No further changes were then seen until 52 weeks postirradiation when a second phase of skin thinning was observed. This was complete after 76 weeks and no further changes in relative skin thickness were seen in the maximum follow up period of 129 weeks. The timings of these phases of damage were independent of the radiation dose, however, the severity of both phases of radiation-induced skin thinning were dose related. (Author).

A pioneer experience in Malaysia on In-house Radio-labelling of "1"3"1I-rituximab in the treatment of Non-Hodgkin's Lymphoma and a case report of high dose "1"3"1I-rituximab-BEAM conditioning autologous transplant

International Nuclear Information System (INIS)

Kuan, Jew Win; Law, Chiong Soon; Wong, Xiang Qi; Ko, Ching Tiong; Awang, Zool Hilmi; Chew, Lee Ping; Chang, Kian Meng

2016-01-01

Radioimmunotherapy is an established treatment modality in Non-Hodgkin's lymphoma. The only two commercially available radioimmunotherapies – "9"0Y-ibritumomab tiuxetan is expensive and "1"3"1I-tositumomab has been discontinued from commercial production. In resource limited environment, self-labelling "1"3"1I-rituximab might be the only viable practical option. We reported our pioneer experience in Malaysia on self-labelling "1"3"1I-rituximab, substituting autologous haematopoietic stem cell transplantation (HSCT) and a patient, the first reported case, received high dose "1"3"1I-rituximab (6000 MBq/163 mCi) combined with BEAM conditioning for autologous HSCT. - Highlights: • Usual dose: Day 0 (dosimetry) – 5 mCi, Day 7 (therapeutic) 0.75 Gy to whole body. • High dose: 6000 MBq (163 mCi) on Day − 18, BEAM conditioning starts on Day − 8. • Self-labelled "1"3"1I-rituximab is a viable treatment in resource limited environment. • "1"3"1I-rituximab may substitute autologous transplant. • High dose "1"3"1I-rituximab-BEAM is a feasible conditioning regime.

Radioimmunotherapy with Y-90-epratuzumab in patients with previously treated B-cell lymphoma. A fractionated dose-escalation study

International Nuclear Information System (INIS)

Linden, O.; Cavallin-Stahl, E.; Tennvall, J.; Hindorf, C.; Olsson, T.; Strand, S.E.; Stenberg, L.; Wingardh, K.

2002-01-01

Aim: Fractionated RIT may improve outcome by decreasing heterogeneity in absorbed dose and by increasing therapeutic window. The humanised anti-CD22 antibody, Epratuzumab, (Immunomedics, Inc., Morris Plains, NJ) can be given repeatedly with minimal risk of neutralising Ab (HAHA), making fractionated treatment with 90 Y-labelled epratuzumab possible. Materials and Methods: Patients with previously treated B-cell lymphoma received increasing number (2-4) of weekly infusions of 90 Y-epratuzumab. Patients received either 185 MBq/m 2 per infusion (group A), or, if they had a history of high-dose chemotherapy with stem-cell rescue, 92.5 MBq/m 2 per infusion (group B). The first infusion included 150 MBq of 111 Indium for scintigraphic verification of tumour targeting and dosimetry. 1.5 mg/kg epratuzumab was administered with each infusion. The treatment could be repeated once after 3 m. Results: Of 23 patients, 16 in group A and 6 in group B were evaluable for response. The RR in group A was 62% objective response (OR) and 25% CR/CRu. One patient in group B showed OR. OR was seen in aggressive and indolent lymphoma. Response was also long-lasting and event-free survival of patients showing CR/CRu was 14 to 25+ months. In group A all seven patient, receiving three infusions, showed less than grade 3 platelet and neutrophil toxicity, except for two patients suffering grade 3 neutropenia. Of five patients with 4 weekly infusions there were two patients with dose-limiting haematological toxicity (DLT), both recently treated with high dose cytosar before RIT. With criteria used the maximal tolerated dose was three infusions 185 MBq/m 2 . In group B no patient suffered DLT and one patient exhibited OR. Seven patients were retreated after 3 months with minor toxicity, but improvement in OR in two cases. No patient has developed HAHA. CD22 expression on tumour cells, as assessed by flow cytometry, is available in 18 of 22 patients. In group A, seven of eight patients with

Radiation dose assessment for 137Cs from fish in the Aegean Sea before and after the Chernobyl accident

International Nuclear Information System (INIS)

Danali-Cotsaki, S.; Liritzis, Y.

1988-01-01

The effective doses in fish from the Aegean Sea were calculated for the nuclide 137 Cs covering the period 1975-1982. The effective dose varies between 3x10 -5 and 10x10 -5 mSv y -1 for adults and 14x10 -5 to 56x10 -5 y -1 for children, while the cumulative effective dose for the period 1975-1982 equals to 40.86x10 -5 and 229.57x10 -5 for adults and children of 10 y old, resp. When compared to doses derived from the Chernobyl accident (May 1986) it was found that the additional dose incurred by Greek individuals in May 1986 was approximately equal to the cumulative dose of 8 y contribution period (1975-1982) for adults and to a year's contribution for children of 10 y old. (author) 9 refs.; 3 figs

Evaluación de la nitazoxanida en dosis única y por tres días en parasitosis intestinal Nitazoxanide vs albendazole against intestinal parasites in a single dose and for three days

Directory of Open Access Journals (Sweden)

Uri Belkind-Valdovinos

2004-08-01

Full Text Available OBJETIVO: Evaluar la utilidad de nitazoxanida en dosis habitual con esquema de tres días y en dosis única, para la erradicación masiva de parásitos intestinales en la población pediátrica, comparando su efecto con el del albendazol en dosis única. MATERIAL Y MÉTODOS: Se realizó un ensayo clínico aleatorizado, en tres comunidades rurales de la región central de México, durante el periodo 2001-2003, para incluir tres posibles alternativas de tratamiento en 786 sujetos de entre 5 y 11 años de edad, de los cuales 92 tuvieron un examen parasitológico positivo (15.1%. El grupo 1 incluyó 27 pacientes que recibieron 400 mg de albendazol en dosis única; el grupo 2 incluyó 34 pacientes a quienes se administró nitazoxanida en dosis de 15 mg/kg/día durante tres días consecutivos; y el grupo 3 incluyó 31 pacientes que recibieron 1.2 g de nitazoxanida en dosis única. Se evaluó diferencia de proporciones mediante prueba exacta de Fisher. RESULTADOS: No existieron diferencias estadísticamente significativas en la efectividad de los tres esquemas de tratamiento: (80.5% con albendazol, comparado con las dos alternativas adicionales de nitazoxanida (67.6% y 71%, respectivamente. Se observó una mayor prevalencia de efectos secundarios con nitazoxanida por kg /día (26.5% y en dosis única (32.2%, en comparación con la dosis única de albendazol (7.4%. CONCLUSIONES: Las evidencias en cuanto a la efectividad y elevada prevalencia de efectos secundarios de la nitazoxanida no justifican aún su utilización como quimiopreventivo masivo para el control de parasitosis intestinal en áreas endémicas. En países con elevada prevalencia de parasitosis intestinal las medidas de prevención primaria que continúan vigentes, y que deben priorizarse, están relacionadas con sanidad pública, introducción de agua potable y drenaje, cloración de agua y manejo adecuado de excretas de animales domésticos, así como educación para la salud.OBJETIVE: To

Occupational exposure of phosphate mine workers: airborne radioactivity measurements and dose assessment

International Nuclear Information System (INIS)

Khater, Ashraf E.; Hussein, M.A.; Hussein, Mohamed I.

2004-01-01

Under the Egyptian program for radiation safety and control, airborne radioactivity measurements and radiological dose assessment were conducted in some phosphate and uranium mines. Abu-Tartor mine is one of the biggest underground phosphate mines in Egypt. Airborne radioactivity, radon ( 222 Rn) and its short-lived decay products (progenies) and thoron ( 220 Rn), were measured in selected locations along the mine. The environmental gamma and workers dose equivalent rate (mSv/y) were measured inside and outside the mine using thermo-luminescence dosimeters (TLD). The results were presented and discussed. The calculated annual effective dose due to airborne radioactivity is the main source of occupational exposure and exceeding the maximum recommended level by ICRP-60 inside the mine tunnels. A number of recommendations are suggested to control the occupational exposures

Photo neutron dose equivalent rate in 15 MV X-ray beam from a Siemens Primus Linac

Directory of Open Access Journals (Sweden)

A Ghasemi

2015-01-01

Full Text Available Fast and thermal neutron fluence rates from a 15 MV X-ray beams of a Siemens Primus Linac were measured using bare and moderated BF 3 proportional counter inside the treatment room at different locations. Fluence rate values were converted to dose equivalent rate (DER utilizing conversion factors of American Association of Physicist in Medicine′s (AAPM report number 19. For thermal neutrons, maximum and minimum DERs were 3.46 × 10 -6 (3 m from isocenter in +Y direction, 0 × 0 field size and 8.36 × 10 -8 Sv/min (in maze, 40 × 40 field size, respectively. For fast neutrons, maximum DERs using 9" and 3" moderators were 1.6 × 10 -5 and 1.74 × 10 -5 Sv/min (2 m from isocenter in +Y direction, 0 × 0 field size, respectively. By changing the field size, the variation in thermal neutron DER was more than the fast neutron DER and the changes in fast neutron DER were not significant in the bunker except inside the radiation field. This study showed that at all points and distances, by decreasing field size of the beam, thermal and fast neutron DER increases and the number of thermal neutrons is more than fast neutrons.

Dosimetry studies with 32P source and correlation of skin and eye lens doses

International Nuclear Information System (INIS)

Kumar, Munish; Gaonkar, U.P.; Koul, D.K.; Datta, D.; Saxena, S.K.; Kumar, Yogendra; Dash, A.

2018-01-01

Beta particles are one of the major contributors toward skin and eye lens doses at facilities handling beta sources. These sources find applications in industry, pharmaceuticals as well as in brachytherapy applications. The beta particles having maximum (E max ) energy > 0.07 MeV are capable of delivering skin dose whereas beta particles having maximum (E max ) energy > 0.7 MeV may also contribute towards dose to eye lens. Studies are performed using 32 P beta source as its maximum beta energy (E max ) is such that for sources having (E max ) of 1.71 MeV or beyond, there can be substantial contribution towards dose to eye lens even the dose limit recommended for skin is followed

Radiation-induced rib fracture after stereotactic body radiotherapy with a total dose of 54–56 Gy given in 9–7 fractions for patients with peripheral lung tumor: impact of maximum dose and fraction size

International Nuclear Information System (INIS)

Aoki, Masahiko; Sato, Mariko; Hirose, Katsumi; Akimoto, Hiroyoshi; Kawaguchi, Hideo; Hatayama, Yoshiomi; Ono, Shuichi; Takai, Yoshihiro

2015-01-01

Radiation-induced rib fracture after stereotactic body radiotherapy (SBRT) for lung cancer has been recently reported. However, incidence of radiation-induced rib fracture after SBRT using moderate fraction sizes with a long-term follow-up time are not clarified. We examined incidence and risk factors of radiation-induced rib fracture after SBRT using moderate fraction sizes for the patients with peripherally located lung tumor. During 2003–2008, 41 patients with 42 lung tumors were treated with SBRT to 54–56 Gy in 9–7 fractions. The endpoint in the study was radiation-induced rib fracture detected by CT scan after the treatment. All ribs where the irradiated doses were more than 80% of prescribed dose were selected and contoured to build the dose-volume histograms (DVHs). Comparisons of the several factors obtained from the DVHs and the probabilities of rib fracture calculated by Kaplan-Meier method were performed in the study. Median follow-up time was 68 months. Among 75 contoured ribs, 23 rib fractures were observed in 34% of the patients during 16–48 months after SBRT, however, no patients complained of chest wall pain. The 4-year probabilities of rib fracture for maximum dose of ribs (Dmax) more than and less than 54 Gy were 47.7% and 12.9% (p = 0.0184), and for fraction size of 6, 7 and 8 Gy were 19.5%, 31.2% and 55.7% (p = 0.0458), respectively. Other factors, such as D2cc, mean dose of ribs, V10–55, age, sex, and planning target volume were not significantly different. The doses and fractionations used in this study resulted in no clinically significant rib fractures for this population, but that higher Dmax and dose per fraction treatments resulted in an increase in asymptomatic grade 1 rib fractures

Estimation of internal dose due to potassium-40 in dietary items over one decade around Kudankulam Nuclear Power Plant

International Nuclear Information System (INIS)

Selvi, B.S.; Rajan, P.S.; Vijayakumar, B.; Thomas, G.; Balamurugan, M.; Ravi, P.M.; Tripathi, R.M.

2014-01-01

The radioactivity measurement of food crops and dietary items were carried out as a part of base line data collection around Kudankulam Nuclear Power Plant from 2004 to 2013. The major natural radionuclide present in all dietary items is Potassium-40. Natural potassium comprises of three isotopes, 39 K (93.26%), 40 K (0.0117 %), and 41 K (6.73 %). 40 K radioactive has a radioactive half life of 1.248 x 10 9 y. In ∼89% transitions, it emits a β-particle with a maximum energy of 1.33 MeV and in 11% of transitions; it emits a gamma photon of 1.461 MeV. Being ubiquitous, 40 K gives radiation dose to all human beings. It is an important radionuclide in terms of the dose associated with naturally occurring radionuclides. The objective of this work is to investigate the natural radioactivity level of 40 K in some selected major food crops which are locally grown and evaluate the annual ingestion dose to the members of the public around Kudankulam

Synthesis and characterization of (Lu{sub 1−x−y}Y{sub x}Ce{sub y}){sub 2}SiO{sub 5} luminescent powders with fast decay time

Energy Technology Data Exchange (ETDEWEB)

Aburto-Crespo, M. [Programa de Posgrado en Física de Materiales CICESE-UNAM, Km. 107 Carretera Tij-Ens, Ensenada, B. C. 22860, México (Mexico); Hirata, G.A., E-mail: hirata@cnyn.unam.mx [Centro de Nanociencias y Nanotecnología-Universidad Nacional Autónoma de México, Km. 107 Carretera Tijuana-Ensenada, Ensenada, B. C. 22860, México (Mexico); McKittrick, J. [University of California at San Diego, La Jolla, CA 92093-0411 (United States)

2013-04-15

The structural and luminescent properties of blue-emitting (Lu{sub 1−x−y}Y{sub x}Ce{sub y}){sub 2}SiO{sub 5} (0.1≤x≤0.4, y=0.05, 0.005) phosphors prepared by combustion synthesis and post-annealed at 1200 °C for different annealing times are reported. X-ray diffraction analysis revealed the formation of a (Lu,Y){sub 2}SiO{sub 5} solid solution as a majority phase with small traces of a residual phase that was identified as Lu{sub 2}SiO{sub 7}. Under long-UV excitation, the powders yield a very bright blue-emission consisting of two bands with maximum emissions located at λ=405 nm and λ=440 nm, both corresponding to the Ce{sup 3+} allowed transitions {sup 2}D{sub 3/2}→{sup 2}F{sub 5/2} and {sup 2}D{sub 5/2}→{sup 2}F{sub 7/2}, respectively. Moreover, luminescence decay times of 38–45 ns were measured, which depend on the composition, making these powders excellent candidates for application as scintillators in medical imaging. -- Highlights: ► A facile technique to fabricate (Lu,Y)-oxyorthosilicate nanophosphors is presented. ► The structural and excellent luminescent properties including excitation, emission and short decay times are reported. ► The Ce-doped oxyorthosilicates nanophosphors present a fast decay time of the order of 38–45 ns.

Pantex Plant Cell 12-44-1 tritium release: Re-assessment of environmental doses for 1990 to 1992

International Nuclear Information System (INIS)

Snyder, S.F.; Hwang, S.T.

1994-03-01

A release of tritium gas occurred within Cell 12-44-1 at the Pantex Plant on May 17, 1989. The release was the result of a nuclear component containment failure. This document summarizes past assessments and characterization of the release. From 1990 to 1992, the average annual dose to the offsite maximally exposed individual (MEI), re-assessed using updated methods and data, ranged from 9E-6 to 2E-4 mrem/y. Doses at this level are well below the regulatory dose limit and support the discontinuation of the distinct calculation of the MEI doses from the cell's tritium releases in future Pantex Annual Site Environmental Reports. Additional information provides guidance for the evaluation of similar releases in the future. Improved Environmental Protection Department sampling plans and assessment goals will increase the value of the data collected during future incidents

Axitinib in combination with pembrolizumab in patients with advanced renal cell cancer: a non-randomised, open-label, dose-finding, and dose-expansion phase 1b trial.

Science.gov (United States)

Atkins, Michael B; Plimack, Elizabeth R; Puzanov, Igor; Fishman, Mayer N; McDermott, David F; Cho, Daniel C; Vaishampayan, Ulka; George, Saby; Olencki, Thomas E; Tarazi, Jamal C; Rosbrook, Brad; Fernandez, Kathrine C; Lechuga, Mariajose; Choueiri, Toni K

2018-03-01

Previous studies combining PD-1 checkpoint inhibitors with tyrosine kinase inhibitors of the VEGF pathway have been characterised by excess toxicity, precluding further development. We hypothesised that axitinib, a more selective VEGF inhibitor than others previously tested, could be combined safely with pembrolizumab (anti-PD-1) and yield antitumour activity in patients with treatment-naive advanced renal cell carcinoma. In this ongoing, open-label, phase 1b study, which was done at ten centres in the USA, we enrolled patients aged 18 years or older who had advanced renal cell carcinoma (predominantly clear cell subtype) with their primary tumour resected, and at least one measureable lesion, Eastern Cooperative Oncology Group performance status 0-1, controlled hypertension, and no previous systemic therapy for renal cell carcinoma. Eligible patients received axitinib plus pembrolizumab in a dose-finding phase to estimate the maximum tolerated dose, and additional patients were enrolled into a dose-expansion phase to further establish safety and determine preliminary efficacy. Axitinib 5 mg was administered orally twice per day with pembrolizumab 2 mg/kg given intravenously every 3 weeks. We assessed safety in all patients who received at least one dose of axitinib or pembrolizumab; antitumour activity was assessed in all patients who received study treatment and had an adequate baseline tumour assessment. The primary endpoint was investigator-assessed dose-limiting toxicity during the first two cycles (6 weeks) to estimate the maximum tolerated dose and recommended phase 2 dose. This study is registered with ClinicalTrials.gov, number NCT02133742. Between Sept 23, 2014, and March 25, 2015, we enrolled 11 patients with previously untreated advanced renal cell carcinoma to the dose-finding phase and between June 3, 2015, and Oct 13, 2015, we enrolled 41 patients to the dose-expansion phase. All 52 patients were analysed together. No unexpected toxicities were

The patient dose survey and dose reduction in diagnostic radiology

International Nuclear Information System (INIS)

Dang Thanh Luong; Duong Van Vinh; Ha Ngoc Thach

2000-01-01

This paper presented the results of the patient dose survey in some hospitals in Hanoi from 1995 to 1997. The main investigated types of the X-ray examination were: Chest PA, LAT; Skull PA/AP, LAT; Lumbar spine AP, LAT; and Pelvis AP. The fluctuation of the entrance surface doses (ESD) was too large, even in the same type of X-ray examination and X-ray facility. It was found that the ratio of maximum and minimum ESD were ranged from 1.5 to 18. The mean values of ESD for chest and skull were higher than CEC recommended values, while the mean values of lumbar spine and pelvis were smaller than that of CEC recommended values. The result of dose intercomparison was also reported. Some methods of dose reduction were applied for improving the patient dose in X-ray departments such as a high kV technique, high sensitive screen-film combination. (author)

Realistic retrospective dose assessments to members of the public around Spanish nuclear facilities

Energy Technology Data Exchange (ETDEWEB)

Jimenez, M.A., E-mail: majg@csn.es [Consejo de Seguridad Nuclear (CSN), Pedro Justo Dorado Dellmans 11, E-28040 Madrid (Spain); Martin-Valdepenas, J.M.; Garcia-Talavera, M.; Martin-Matarranz, J.L.; Salas, M.R.; Serrano, J.I.; Ramos, L.M. [Consejo de Seguridad Nuclear (CSN), Pedro Justo Dorado Dellmans 11, E-28040 Madrid (Spain)

2011-11-15

In the frame of an epidemiological study carried out in the influence areas around the Spanish nuclear facilities (ISCIII-CSN, 2009. Epidemiological Study of The Possible Effect of Ionizing Radiations Deriving from The Operation of Spanish Nuclear Fuel Cycle Facilities on The Health of The Population Living in Their Vicinity. Final report December 2009. Ministerio de Ciencia e Innovacion, Instituto de Salud Carlos III, Consejo de Seguridad Nuclear. Madrid. Available from: (http://www.csn.es/images/stories/actualidad{sub d}atos/especiales/epidemiologico/epidemiological{sub s}tudy.pdf)), annual effective doses to public have been assessed by the Spanish Nuclear Safety Council (CSN) for over 45 years using a retrospective realistic-dose methodology. These values are compared with data from natural radiation exposure. For the affected population, natural radiation effective doses are in average 2300 times higher than effective doses due to the operation of nuclear installations (nuclear power stations and fuel cycle facilities). When considering the impact on the whole Spanish population, effective doses attributable to nuclear facilities represent in average 3.5 x 10{sup -5} mSv/y, in contrast to 1.6 mSv/y from natural radiation or 1.3 mSv/y from medical exposures. - Highlights: > Most comprehensive dose assessment to public by nuclear facilities ever done in Spain. > Dose to public is dominated by liquid effluent pathways for the power stations. > Dose to public is dominated by Rn inhalation for milling and mining facilities. > Average annual doses to public in influence areas are negligible (10 {mu}Sv/y or less). > Doses from facilities average 3.5 x 10{sup -2} {mu}Sv/y per person onto whole Spanish population.

Realistic retrospective dose assessments to members of the public around Spanish nuclear facilities

International Nuclear Information System (INIS)

Jimenez, M.A.; Martin-Valdepenas, J.M.; Garcia-Talavera, M.; Martin-Matarranz, J.L.; Salas, M.R.; Serrano, J.I.; Ramos, L.M.

2011-01-01

In the frame of an epidemiological study carried out in the influence areas around the Spanish nuclear facilities (ISCIII-CSN, 2009. Epidemiological Study of The Possible Effect of Ionizing Radiations Deriving from The Operation of Spanish Nuclear Fuel Cycle Facilities on The Health of The Population Living in Their Vicinity. Final report December 2009. Ministerio de Ciencia e Innovacion, Instituto de Salud Carlos III, Consejo de Seguridad Nuclear. Madrid. Available from: (http://www.csn.es/images/stories/actualidad_datos/especiales/epidemiologico/epidemiological_study.pdf)), annual effective doses to public have been assessed by the Spanish Nuclear Safety Council (CSN) for over 45 years using a retrospective realistic-dose methodology. These values are compared with data from natural radiation exposure. For the affected population, natural radiation effective doses are in average 2300 times higher than effective doses due to the operation of nuclear installations (nuclear power stations and fuel cycle facilities). When considering the impact on the whole Spanish population, effective doses attributable to nuclear facilities represent in average 3.5 x 10 -5 mSv/y, in contrast to 1.6 mSv/y from natural radiation or 1.3 mSv/y from medical exposures. - Highlights: → Most comprehensive dose assessment to public by nuclear facilities ever done in Spain. → Dose to public is dominated by liquid effluent pathways for the power stations. → Dose to public is dominated by Rn inhalation for milling and mining facilities. → Average annual doses to public in influence areas are negligible (10 μSv/y or less). → Doses from facilities average 3.5 x 10 -2 μSv/y per person onto whole Spanish population.

Maximum tolerated dose evaluation of the AMPA modulator Org 26576 in healthy volunteers and depressed patients: a summary and method analysis of bridging research in support of phase II dose selection.

Science.gov (United States)

Nations, Kari R; Bursi, Roberta; Dogterom, Peter; Ereshefsky, Larry; Gertsik, Lev; Mant, Tim; Schipper, Jacques

2012-09-01

A key challenge to dose selection in early central nervous system (CNS) clinical drug development is that patient tolerability profiles often differ from those of healthy volunteers (HVs), yet HVs are the modal population for determining doses to be investigated in phase II trials. Without clear tolerability data from the target patient population, first efficacy trials may include doses that are either too high or too low, creating undue risk for study participants and the development program overall. Bridging trials address this challenge by carefully investigating safety and tolerability in the target population prior to full-scale proof-of-concept trials. Org 26576 is an alpha-amino-3-hydroxy-5-methylisoxazole-4-propionic acid (AMPA) receptor positive allosteric modulator that acts by modulating ionotropic AMPA-type glutamate receptors to enhance glutamatergic neurotransmission. In preparation for phase II efficacy trials in major depressive disorder (MDD), two separate phase I trials were conducted to evaluate safety, tolerability, and pharmacokinetics in HVs and in the target patient population. Both trials were randomized and placebo controlled, and included multiple rising-dose cohorts (HV range 100-400 mg bid; MDD range 100-600 mg bid). HVs (n = 36) and patients with MDD (n = 54) were dosed under similarly controlled conditions in an inpatient facility, HVs for up to 14 days and MDD patients for up to 28 days. Safety, tolerability, and pharmacokinetics were assessed frequently. Despite comparable pharmacokinetic profiles, the maximum tolerated dose (MTD) in depressed patients was 450 mg bid, twice the MTD established in HVs. No clinically relevant safety issues associated with Org 26576 were noted. This article presents safety, tolerability, and pharmacokinetic data from two different populations examined under similar dosing conditions. The important implications of such bridging work in phase II dose selection are discussed, as are study

Natural radioactivity in Brazilian bottled mineral waters and consequent doses

International Nuclear Information System (INIS)

Oliveira, J. de; Paci Mazzilli, B.; Costa, P. da; Akiko Tanigava, P.

2001-01-01

The natural activity concentration levels of 226 Ra, 228 Ra and 210 Pb were analyzed in 17 brands of bottled mineral waters commercially available in the Southeast region of Brazil. Concentrations up to 647 mBq x l -1 and 741 mBq x l -1 were observed for 226 Ra and 228 Ra, whereas 210 Pb concentrations reached 85 mBq x l -1 . Average committed effective doses of 1.3 x 10 -2 mSv x y -1 for 226 Ra, 3.4 x 10 -2 mSv x y -1 for 228 Ra and 9.4 x 10 -3 mSv x y -1 for 210 Pb were estimated for the ingestion of these waters. A collective dose of 90 manSv was evaluated, considering the annual production of the bottled mineral waters analyzed in this study. (author)

A Phase I Dose-Escalation Study (ISIDE-BT-1) of Accelerated IMRT With Temozolomide in Patients With Glioblastoma

International Nuclear Information System (INIS)

Morganti, Alessio G.; Balducci, Mario; Salvati, Maurizio; Esposito, Vincenzo; Romanelli, Pantaleo; Ferro, Marica; Calista, Franco; Digesu, Cinzia; Macchia, Gabriella; Ianiri, Massimo; Deodato, Francesco; Cilla, Savino; Piermattei, Angelo M.P.; Valentini, Vincenzo; Cellini, Numa; Cantore, Gian Paolo

2010-01-01

Purpose: To determine the maximum tolerated dose (MTD) of fractionated intensity-modulated radiotherapy (IMRT) with temozolomide (TMZ) in patients with glioblastoma. Methods and Materials: A Phase I clinical trial was performed. Eligible patients had surgically resected or biopsy-proven glioblastoma. Patients started TMZ (75 mg/day) during IMRT and continued for 1 year (150-200 mg/day, Days 1-5 every 28 days) or until disease progression. Clinical target volume 1 (CTV1) was the tumor bed ± enhancing lesion with a 10-mm margin; CTV2 was the area of perifocal edema with a 20-mm margin. Planning target volume 1 (PTV1) and PTV2 were defined as the corresponding CTV plus a 5-mm margin. IMRT was delivered in 25 fractions over 5 weeks. Only the dose for PTV1 was escalated (planned dose escalation: 60 Gy, 62.5 Gy, 65 Gy) while maintaining the dose for PTV2 (45 Gy, 1.8 Gy/fraction). Dose limiting toxicities (DLT) were defined as any treatment-related nonhematological adverse effects rated as Grade ≥3 or any hematological toxicity rated as ≥4 by Radiation Therapy Oncology Group (RTOG) criteria. Results: Nineteen consecutive glioblastoma were treated with step-and-shoot IMRT, planned with the inverse approach (dose to the PTV1: 7 patients, 60 Gy; 6 patients, 62.5 Gy; 6 patients, 65 Gy). Five coplanar beams were used to cover at least 95% of the target volume with the 95% isodose line. Median follow-up time was 23 months (range, 8-40 months). No patient experienced DLT. Grade 1-2 treatment-related neurologic and skin toxicity were common (11 and 19 patients, respectively). No Grade >2 late neurologic toxicities were noted. Conclusion: Accelerated IMRT to a dose of 65 Gy in 25 fractions is well tolerated with TMZ at a daily dose of 75 mg.

[Value of early application of different doses of amino acids in parenteral nutrition among preterm infants].

Science.gov (United States)

Liu, Zhi-Juan; Liu, Guo-Sheng; Chen, Yong-Ge; Zhang, Hui-Li; Wu, Xue-Fen

2015-01-01

To study the short-term response and tolerance of different doses of amino acids in parenteral nutrition among preterm infants. This study included 86 preterm infants who had a birth weight between 1 000 to 2 000 g and were admitted to the hospital within 24 hours of birth between March 2013 and June 2014. According to the early application of different doses of amino acids, they were randomized into low-dose group (n=29, 1.0 g/kg per day with an increase of 1.0 g/kg daily and a maximum of 3.5 g/kg per day), medium-dose group (n=28, 2.0 g/kg per day with an increase of 1.0 g/kg daily and a maximum of 3.7 g/kg per day), and high-dose group (n=29, 3.0 g/kg per day with an increase of 0.5-1.0 g/kg daily and a maximum of 4.0 g/kg per day). Other routine parenteral nutrition and enteral nutrition support were also applied. The maximum weight loss was lower and the growth rate of head circumference was greater in the high-dose group than in the low-dose group (Pnutrition, shorter duration of hospital stay, and less hospital cost than those in the low-dose group (P0.05). Parenteral administration of high-dose amino acids in preterm infants within 24 hours after birth can improve the short-term nutritional status of preterm infants, but there is a transient increase in BUN level.

Effective plague vaccination via oral delivery of plant cells expressing F1-V antigens in chloroplasts.

Science.gov (United States)

Arlen, Philip A; Singleton, Michael; Adamovicz, Jeffrey J; Ding, Yi; Davoodi-Semiromi, Abdolreza; Daniell, Henry

2008-08-01

The chloroplast bioreactor is an alternative to fermentation-based systems for production of vaccine antigens and biopharmaceuticals. We report here expression of the plague F1-V fusion antigen in chloroplasts. Site-specific transgene integration and homoplasmy were confirmed by PCR and Southern blotting. Mature leaves showed the highest level of transgene expression on the third day of continuous illumination, with a maximum level of 14.8% of the total soluble protein. Swiss Webster mice were primed with adjuvant-containing subcutaneous (s.c.) doses of F1-V and then boosted with either adjuvanted s.c. doses (s.c. F1-V mice) or unadjuvanted oral doses (oral F1-V mice). Oral F1-V mice had higher prechallenge serum immunoglobulin G1 (IgG1) titers than s.c. F1-V mice. The corresponding serum levels of antigen-specific IgG2a and IgA were 2 and 3 orders of magnitude lower, respectively. After vaccination, mice were exposed to an inhaled dose of 1.02 x 10(6) CFU of aerosolized Yersinia pestis CO92 (50% lethal dose, 6.8 x 10(4) CFU). All control animals died within 3 days. F1-V given s.c. (with adjuvant) protected 33% of the immunized mice, while 88% of the oral F1-V mice survived aerosolized Y. pestis challenge. A comparison of splenic Y. pestis CFU counts showed that there was a 7- to 10-log reduction in the mean bacterial burden in survivors. Taken together, these data indicate that oral booster doses effectively elicit protective immune responses in vivo. In addition, this is the first report of a plant-derived oral vaccine that protected animals from live Y. pestis challenge, bringing the likelihood of lower-cost vaccines closer to reality.

Phase I dose-finding study of S1 in combination with docetaxel and oxaliplatin (DOS) as first-line therapy in patients with advanced gastro-esophageal cancer

DEFF Research Database (Denmark)

Weber Vestermark, Lene; Jensen, H. A.; Schoennemann, K. R.

2015-01-01

-14) every 3 weeks for a maximum of 6 cycles followed by maintenance therapy with S-1 monotherapy (2 x 30 mg/m2/days 1-14) until progression. Toxicity was evaluated according to NCIC-CTC 4.0. DLT was defined as non-hematological toxicity grade > 3 or febrile neutropenia and evaluated after the first course...... was 67-years (49-75), median performance status was 1 (0-1). None of 3 patients at dose level 1 and 2 developed DLT. At dose level 3, 2/4 pts developed DLT (febrile neutropenia and febrile neutropenia with diarrhoea) and further inclusion at dose level 3 was halted. Five further patients at dose level 2...

Dose from radiological examinations

International Nuclear Information System (INIS)

Imamura, Keiko; Uji, Teruyuki; Sakuyama, Keiko; Fujikawa, Mitsuhiro; Fujii, Masamichi

1976-01-01

Relatively high gonad doses, several hundred to one thousand mR, have been observed in case of pelvis, hip-joint, coccyx, lower abdomen and lumber examination. Dose to the ovary is especially high in barium enema and I.V.P. examinations. About 12 per cent of the 4-ray examination are high-dose. The gonad dose is relatively high in examination of abdomen and lower extremities, in infants. The dose to the eyes is especially high, 1.0 to 2.5R per exposure, in temporal bone and nasal sinuses tomography. X-ray doses have been compared with dose limits recommended by ICRP and with the gonad dose from natural radiations. The gonad dose in lumbar examination, barium enema, I.V.P. etc. is as high as the maximum permissible dose per year recommended by ICRP. Several devices have been made for dose reduction in the daily examinations: (1) separating the radiation field from the gonad by one centimeter decreases the gonad dose about one-half. (2) using sensitive screens and films. In pelvimetry and in infant hip-joint examination, the most sensitive screen and film are used. In the I.V.P. examination of adult, use of MS screen in place of FS screen decreases the dose to one-third, in combination with careful setting of radiation field, (3) use of grid increases the dose about 50 percent and the lead rubber protection (0.1mm lead equivalent) decreases the gonad dose to one-thirtieth in the spinal column examination of infant, (4) A lead protector, 1mm thickness and 2.5cm in diameter, on the eyes decreases the dose to about one-eighth in the face and nead examinations. These simple and effective methods for dose reduction. Should be carried out in as many examinations as possible in addition to observing dose limits recommended by ICRP. (Evans, J.)

Safety and maximum tolerated dose of superselective intraarterial cerebral infusion of bevacizumab after osmotic blood-brain barrier disruption for recurrent malignant glioma. Clinical article.

Science.gov (United States)

Boockvar, John A; Tsiouris, Apostolos J; Hofstetter, Christoph P; Kovanlikaya, Ilhami; Fralin, Sherese; Kesavabhotla, Kartik; Seedial, Stephen M; Pannullo, Susan C; Schwartz, Theodore H; Stieg, Philip; Zimmerman, Robert D; Knopman, Jared; Scheff, Ronald J; Christos, Paul; Vallabhajosula, Shankar; Riina, Howard A

2011-03-01

The authors assessed the safety and maximum tolerated dose of superselective intraarterial cerebral infusion (SIACI) of bevacizumab after osmotic disruption of the blood-brain barrier (BBB) with mannitol in patients with recurrent malignant glioma. A total of 30 patients with recurrent malignant glioma were included in the current study. The authors report no dose-limiting toxicity from a single dose of SIACI of bevacizumab up to 15 mg/kg after osmotic BBB disruption with mannitol. Two groups of patients were studied; those without prior bevacizumab exposure (naïve patients; Group I) and those who had received previous intravenous bevacizumab (exposed patients; Group II). Radiographic changes demonstrated on MR imaging were assessed at 1 month postprocedure. In Group I patients, MR imaging at 1 month showed a median reduction in the area of tumor enhancement of 34.7%, a median reduction in the volume of tumor enhancement of 46.9%, a median MR perfusion (MRP) reduction of 32.14%, and a T2-weighted/FLAIR signal decrease in 9 (47.4%) of 19 patients. In Group II patients, MR imaging at 1 month showed a median reduction in the area of tumor enhancement of 15.2%, a median volume reduction of 8.3%, a median MRP reduction of 25.5%, and a T2-weighted FLAIR decrease in 0 (0%) of 11 patients. The authors conclude that SIACI of mannitol followed by bevacizumab (up to 15 mg/kg) for recurrent malignant glioma is safe and well tolerated. Magnetic resonance imaging shows that SIACI treatment with bevacizumab can lead to reduction in tumor area, volume, perfusion, and T2-weighted/FLAIR signal.

Prospective radiological dose assessment. Amersham plc (Amersham site) variation application December 1998

International Nuclear Information System (INIS)

Allott, R.

2001-01-01

Amersham plc (previously Nycomed-Amersham plc) submitted an application to the Environment Agency in December 1998 for a variation to their radioactive waste discharge authorisations granted under the Radioactive Substances Act 1993. The application requested a reduction in the discharge limits for certain radionuclides and no change for the remaining radionuclides. Amersham plc undertook a further review of their discharge requirements and submitted a new assessment for revised limits in January 2001. This report provides an assessment of the radiological implications of discharges at these revised limits requested by Amersham plc and the limits proposed by the Agency. It has been prepared by the National Compliance Assessment Service at the request of Thames Region to support their determination of the application. Four candidate critical groups were identified who could be exposed to discharges from the Amersham site: 1) Sewage workers at the Maple Lodge sewage works who might be exposed to external radiation from discharges contained within sewage and inadvertently inhale or ingest sewage. 2) Anglers on the Grand Union Canal who eat a small proportion of their annual catch of freshwater fish, who drink water abstracted solely from the River Colne and eat vegetables irrigated by water from the canal. 3) Persons living closest to site who eat locally produced food. 4) Dog walkers living near to site who eat locally produced food. For continuous discharges at the Agency's proposed annual limits, the highest dose of 160 μSv/y is predicted to be received by infants who live closest to the site and eat locally produced food. Therefore, this has been identified as the critical group. Children and adults living at the same location and eating locally produced food receive doses of 140 μSv/y and 130 μSv/y respectively. The critical group dose is less than the source constraint of 300 μSv/y. The dose is dominated by direct radiation from the site (110 μSv/y) and the

Radiation dose assessment for /sup 137/Cs from fish in the Aegean Sea before and after the Chernobyl accident

Energy Technology Data Exchange (ETDEWEB)

Danali-Cotsaki, S; Liritzis, Y

1988-02-15

The effective doses in fish from the Aegean Sea were calculated for the nuclide /sup 137/Cs covering the period 1975-1982. The effective dose varies between 3x10/sup -5/ and 10x10/sup -5/ mSv y/sup -1/ for adults and 14x10/sup -5/ to 56x10/sup -5/ y/sup -1/ for children, while the cumulative effective dose for the period 1975-1982 equals to 40.86x10/sup -5/ and 229.57x10/sup -5/ for adults and children of 10 y old, resp. When compared to doses derived from the Chernobyl accident (May 1986) it was found that the additional dose incurred by Greek individuals in May 1986 was approximately equal to the cumulative dose of 8 y contribution period (1975-1982) for adults and to a year's contribution for children of 10 y old. (author) 9 refs.; 3 figs.

Experience of micromultileaf collimator linear accelerator based single fraction stereotactic radiosurgery: Tumor dose inhomogeneity, conformity, and dose fall off

Energy Technology Data Exchange (ETDEWEB)

Hong, Linda X.; Garg, Madhur; Lasala, Patrick; Kim, Mimi; Mah, Dennis; Chen, Chin-Cheng; Yaparpalvi, Ravindra; Mynampati, Dinesh; Kuo, Hsiang-Chi; Guha, Chandan; Kalnicki, Shalom [Department of Radiation Oncology, Montefiore Medical Center and Albert Einstein College of Medicine, Bronx, New York 10461 (United States); Department of Neurosurgery, Montefiore Medical Center and Albert Einstein College of Medicine, Bronx, New York 10461 (United States); Department of Epidemiology and Population Health, Montefiore Medical Center and Albert Einstein College of Medicine, Bronx, New York 10461 (United States); Department of Radiation Oncology, Montefiore Medical Center and Albert Einstein College of Medicine, Bronx, New York 10461 (United States)

2011-03-15

Purpose: Sharp dose fall off outside a tumor is essential for high dose single fraction stereotactic radiosurgery (SRS) plans. This study explores the relationship among tumor dose inhomogeneity, conformity, and dose fall off in normal tissues for micromultileaf collimator (mMLC) linear accelerator (LINAC) based cranial SRS plans. Methods: Between January 2007 and July 2009, 65 patients with single cranial lesions were treated with LINAC-based SRS. Among them, tumors had maximum diameters {<=}20 mm: 31; between 20 and 30 mm: 21; and >30 mm: 13. All patients were treated with 6 MV photons on a Trilogy linear accelerator (Varian Medical Systems, Palo Alto, CA) with a tertiary m3 high-resolution mMLC (Brainlab, Feldkirchen, Germany), using either noncoplanar conformal fixed fields or dynamic conformal arcs. The authors also created retrospective study plans with identical beam arrangement as the treated plan but with different tumor dose inhomogeneity by varying the beam margins around the planning target volume (PTV). All retrospective study plans were normalized so that the minimum PTV dose was the prescription dose (PD). Isocenter dose, mean PTV dose, RTOG conformity index (CI), RTOG homogeneity index (HI), dose gradient index R{sub 50}-R{sub 100} (defined as the difference between equivalent sphere radius of 50% isodose volume and prescription isodose volume), and normal tissue volume (as a ratio to PTV volume) receiving 50% prescription dose (NTV{sub 50}) were calculated. Results: HI was inversely related to the beam margins around the PTV. CI had a ''V'' shaped relationship with HI, reaching a minimum when HI was approximately 1.3. Isocenter dose and mean PTV dose (as percentage of PD) increased linearly with HI. R{sub 50}-R{sub 100} and NTV{sub 50} initially declined with HI and then reached a plateau when HI was approximately 1.3. These trends also held when tumors were grouped according to their maximum diameters. The smallest tumor group

SU-E-T-154: Calculation of Tissue Dose Point Kernels Using GATE Monte Carlo Simulation Toolkit to Compare with Water Dose Point Kernel

Energy Technology Data Exchange (ETDEWEB)

Khazaee, M [shahid beheshti university, Tehran, Tehran (Iran, Islamic Republic of); Asl, A Kamali [Shahid Beheshti University, Tehran, Iran., Tehran, Tehran (Iran, Islamic Republic of); Geramifar, P [Shariati Hospital, Tehran, Iran., Tehran, Tehran (Iran, Islamic Republic of)

2015-06-15

Purpose: the objective of this study was to assess utilizing water dose point kernel (DPK)instead of tissue dose point kernels in convolution algorithms.to the best of our knowledge, in providing 3D distribution of absorbed dose from a 3D distribution of the activity, the human body is considered equivalent to water. as a Result tissue variations are not considered in patient specific dosimetry. Methods: In this study Gate v7.0 was used to calculate tissue dose point kernel. the beta emitter radionuclides which have taken into consideration in this simulation include Y-90, Lu-177 and P-32 which are commonly used in nuclear medicine. the comparison has been performed for dose point kernels of adipose, bone, breast, heart, intestine, kidney, liver, lung and spleen versus water dose point kernel. Results: In order to validate the simulation the Result of 90Y DPK in water were compared with published results of Papadimitroulas et al (Med. Phys., 2012). The results represented that the mean differences between water DPK and other soft tissues DPKs range between 0.6 % and 1.96% for 90Y, except for lung and bone, where the observed discrepancies are 6.3% and 12.19% respectively. The range of DPK difference for 32P is between 1.74% for breast and 18.85% for bone. For 177Lu, the highest difference belongs to bone which is equal to 16.91%. For other soft tissues the least discrepancy is observed in kidney with 1.68%. Conclusion: In all tissues except for lung and bone, the results of GATE for dose point kernel were comparable to water dose point kernel which demonstrates the appropriateness of applying water dose point kernel instead of soft tissues in the field of nuclear medicine.

SU-E-T-154: Calculation of Tissue Dose Point Kernels Using GATE Monte Carlo Simulation Toolkit to Compare with Water Dose Point Kernel

International Nuclear Information System (INIS)

Khazaee, M; Asl, A Kamali; Geramifar, P

2015-01-01

Purpose: the objective of this study was to assess utilizing water dose point kernel (DPK)instead of tissue dose point kernels in convolution algorithms.to the best of our knowledge, in providing 3D distribution of absorbed dose from a 3D distribution of the activity, the human body is considered equivalent to water. as a Result tissue variations are not considered in patient specific dosimetry. Methods: In this study Gate v7.0 was used to calculate tissue dose point kernel. the beta emitter radionuclides which have taken into consideration in this simulation include Y-90, Lu-177 and P-32 which are commonly used in nuclear medicine. the comparison has been performed for dose point kernels of adipose, bone, breast, heart, intestine, kidney, liver, lung and spleen versus water dose point kernel. Results: In order to validate the simulation the Result of 90Y DPK in water were compared with published results of Papadimitroulas et al (Med. Phys., 2012). The results represented that the mean differences between water DPK and other soft tissues DPKs range between 0.6 % and 1.96% for 90Y, except for lung and bone, where the observed discrepancies are 6.3% and 12.19% respectively. The range of DPK difference for 32P is between 1.74% for breast and 18.85% for bone. For 177Lu, the highest difference belongs to bone which is equal to 16.91%. For other soft tissues the least discrepancy is observed in kidney with 1.68%. Conclusion: In all tissues except for lung and bone, the results of GATE for dose point kernel were comparable to water dose point kernel which demonstrates the appropriateness of applying water dose point kernel instead of soft tissues in the field of nuclear medicine

SU-E-T-169: Characterization of Pacemaker/ICD Dose in SAVI HDR Brachytherapy

Energy Technology Data Exchange (ETDEWEB)

Kalavagunta, C; Lasio, G; Yi, B; Zhou, J; Lin, M [Univ. of Maryland School Of Medicine, Baltimore, MD (United States)

2015-06-15

Purpose: It is important to estimate dose to pacemaker (PM)/Implantable Cardioverter Defibrillator (ICD) before undertaking Accelerated Partial Breast Treatment using High Dose Rate (HDR) brachytherapy. Kim et al. have reported HDR PM/ICD dose using a single-source balloon applicator. To the authors knowledge, there have so far not been any published PM/ICD dosimetry literature for the Strut Adjusted Volume Implant (SAVI, Cianna Medical, Aliso Viejo, CA). This study aims to fill this gap by generating a dose look up table (LUT) to predict maximum dose to the PM/ICD in SAVI HDR brachytherapy. Methods: CT scans for 3D dosimetric planning were acquired for four SAVI applicators (6−1-mini, 6−1, 8−1 and 10−1) expanded to their maximum diameter in air. The CT datasets were imported into the Elekta Oncentra TPS for planning and each applicator was digitized in a multiplanar reconstruction window. A dose of 340 cGy was prescribed to the surface of a 1 cm expansion of the SAVI applicator cavity. Cartesian coordinates of the digitized applicator were determined in the treatment leading to the generation of a dose distribution and corresponding distance-dose prediction look up table (LUT) for distances from 2 to 15 cm (6-mini) and 2 to 20 cm (10–1).The deviation between the LUT doses and the dose to the cardiac device in a clinical case was evaluated. Results: Distance-dose look up table were compared to clinical SAVI plan and the discrepancy between the max dose predicted by the LUT and the clinical plan was found to be in the range (−0.44%, 0.74%) of the prescription dose. Conclusion: The distance-dose look up tables for SAVI applicators can be used to estimate the maximum dose to the ICD/PM, with a potential usefulness for quick assessment of dose to the cardiac device prior to applicator placement.

Application of a Novel Dose-Uncertainty Model for Dose-Uncertainty Analysis in Prostate Intensity-Modulated Radiotherapy

International Nuclear Information System (INIS)

Jin Hosang; Palta, Jatinder R.; Kim, You-Hyun; Kim, Siyong

2010-01-01

Purpose: To analyze dose uncertainty using a previously published dose-uncertainty model, and to assess potential dosimetric risks existing in prostate intensity-modulated radiotherapy (IMRT). Methods and Materials: The dose-uncertainty model provides a three-dimensional (3D) dose-uncertainty distribution in a given confidence level. For 8 retrospectively selected patients, dose-uncertainty maps were constructed using the dose-uncertainty model at the 95% CL. In addition to uncertainties inherent to the radiation treatment planning system, four scenarios of spatial errors were considered: machine only (S1), S1 + intrafraction, S1 + interfraction, and S1 + both intrafraction and interfraction errors. To evaluate the potential risks of the IMRT plans, three dose-uncertainty-based plan evaluation tools were introduced: confidence-weighted dose-volume histogram, confidence-weighted dose distribution, and dose-uncertainty-volume histogram. Results: Dose uncertainty caused by interfraction setup error was more significant than that of intrafraction motion error. The maximum dose uncertainty (95% confidence) of the clinical target volume (CTV) was smaller than 5% of the prescribed dose in all but two cases (13.9% and 10.2%). The dose uncertainty for 95% of the CTV volume ranged from 1.3% to 2.9% of the prescribed dose. Conclusions: The dose uncertainty in prostate IMRT could be evaluated using the dose-uncertainty model. Prostate IMRT plans satisfying the same plan objectives could generate a significantly different dose uncertainty because a complex interplay of many uncertainty sources. The uncertainty-based plan evaluation contributes to generating reliable and error-resistant treatment plans.

Y-27632 Increases Sensitivity of PANC-1 Cells to EGCG in Regulating Cell Proliferation and Migration.

Science.gov (United States)

Liu, Xing; Bi, Yongyi

2016-10-03

BACKGROUND The study aimed to investigate the inhibitory effect of (1R,4r)-4-((R)-1-aminoethyl)-N-(pyridin-4-yl) cyclohexanecarboxamide (Y-27632) and (-)-epigallocatechin-3-gallate (EGCG) on the proliferation and migration of PANC-1 cells. EGCG, found in green tea, has been previously shown to be one of the most abundant and powerful catechins in cancer prevention and treatment. Y-27632, a selective inhibitor of rho-associated protein kinase 1, is widely used in treating cardiovascular disease, inflammation, and cancer. MATERIAL AND METHODS PANC-1 cells, maintained in Dulbecco's Modified Eagle's Medium, were treated with dimethyl sulfoxide (control) as well as different concentrations (20, 40, 60, and 80 μg/mL) of EGCG for 48 h. In addition, PANC-1 cells were treated separately with 60 μg/mL EGCG, 20 μM Y-27632, and EGCG combined with Y-27632 (60 μg/mL EGCG + 20 μM Y-27632) for 48 h. The effect of EGCG and Y-27632 on the proliferation and migration of PANC-1 cells was evaluated using Cell Counting Kit-8 and transwell migration assays. The expression of peroxisome proliferator-activated receptor alpha (PPARα) and Caspase-3 mRNA was determined by Quantitative real-time polymerase chain reaction (RT-qPCR). RESULTS EGCG (20-80 μg/mL) inhibited cell viability in a dose-dependent manner. Y-27632 enhanced the sensitivity of PANC-1 cells to EGCG (by increasing the expression of PPARa and Caspase-3 mRNA) and suppressed cell proliferation. PANC-1 cell migration was inhibited by treatment with a combination of EGCG and Y-27632. CONCLUSIONS Y-27632 increases the sensitivity of PANC-1 cells to EGCG in regulating cell proliferation and migration, which is likely to be related to the expression of PPARa mRNA and Caspase-3 mRNA.

[Preparation and spectral characterization of CdS(y)Te(1-y) thin films].

Science.gov (United States)

Li, Wei; Feng, Liang-Huan; Wu, Li-Li; Zhang, Jing-Quan; Li, Bing; Lei, Zhi; Cai, Ya-Ping; Zheng, Jia-Gui; Cai, Wei; Zhang, Dong-Min

2008-03-01

CdS(y)Te(1-y) (0 co-evaporation of powders of CdTe and CdS. For the characterization of the structure and composition of the CdS(y)Te(1-y) thin films the X-ray diffraction (XRD) and energy-dispersive spectroscopy (EDS) were used. The results indicate that the values of sulfur content y detected and controlled by the quartz wafer detector show good agreement with the EDS results. The films were found to be cubic for x or = 0.3. The 20-50 nm of grain sizes for CdS(y)Te(1-y) thin films were calculated using a method of XRD analysis. Finally, the optical properties of CdS(y)Te(1-y) thin films were characterized by UV-Vis-NIR spectroscopy alone. According to a method from Swanepoel, together with the first-order Sellmeier model, the thickness, of d-535 nm, energy gap of E(g)-1.41 eV, absorption coefficient, alpha(lambda) and refractive index, n(lambda) of CdS(0.22) Te(0.78) thin films were determined from the transmittance at normal incidence of light in the wavelength range 300-2 500 nm. The results also indicate that the CdS(y)Te(1-y) thin films with any composition (0 co-evaporation, and the method to characterize the optical properties of CdS(y)Te(1-y) thin films can be implemented for other semiconductor thin films.

Impact of concomitant Y and Mn substitution on properties of La{sub 1-z}Y{sub z}Fe{sub 1-y}Mn{sub y}AsO{sub 0.9}F{sub 0.1}

Energy Technology Data Exchange (ETDEWEB)

Kappenberger, Rhea; Hammerath, Franziska; Wurmehl, Sabine; Buechner, Bernd [Leibniz Institute for Solid State and Materials Research Dresden, IFW Dresden (Germany); Institut fuer Festkoerperphysik, TU Dresden, Dresden (Germany); Asfaw Afrassa, Mesfin [Leibniz Institute for Solid State and Materials Research Dresden, IFW Dresden (Germany); Addis Ababa University, College of Natural Science, Addis Ababa (Ethiopia); Rousse, Pierre; Hess, Christian; Prando, Giacomo; Moroni, Matteo; Wolter, Anja U.B. [Leibniz Institute for Solid State and Materials Research Dresden, IFW Dresden (Germany); Sanna, Samuele; Carretta, Pietro [Dipartimento di Fisica e Unita di CNISM, Pavia (Italy); Lamura, Gianrico [Universita di Genova (Italy); CNR-SPIN, Genova (Italy); Kamusella, Sirko; Klauss, Hans-Henning [Institut fuer Festkoerperphysik, TU Dresden, Dresden (Germany)

2016-07-01

The substitution of constituents is frequently used as a local probe to check the microscopic properties of an unconventional superconductor in response to such an ''impurity''. In this talk, we present several structural parameters and the superconducting critical temperatures in response to different substitution levels of Mn and Y in La{sub 1-z}Y{sub z}Fe{sub 1-y}Mn{sub y}AsO{sub 0.9}F{sub 0.1}. We will discuss our findings in the light of chemical pressure inflicted by Y, which has a significantly smaller ionic radius than La, and strong electron localization caused by small amounts of paramagnetic Mn impurities.

Average annual doses, lifetime doses and associated risk of cancer death for radiation workers in various fuel fabrication facilities in India

International Nuclear Information System (INIS)

Iyer, P.S.; Dhond, R.V.

1980-01-01

Lifetime doses based on average annual doses are estimated for radiation workers in various fuel fabrication facilities in India. For such cumulative doses, the risk of radiation-induced cancer death is computed. The methodology for arriving at these estimates and the assumptions made are discussed. Based on personnel monitoring records from 1966 to 1978, the average annual dose equivalent for radiation workers is estimated as 0.9 mSv (90 mrem), and the maximum risk of cancer death associated with this occupational dose as 1.35x10 -5 a -1 , as compared with the risk of death due to natural causes of 7x10 -4 a -1 and the risk of death due to background radiation alone of 1.5x10 -5 a -1 . (author)

Effective dose and dose to crystalline lens during angiographic procedures

International Nuclear Information System (INIS)

Pages, J.

1998-01-01

The highest radiation doses levels received by radiologists are observed during interventional procedures. Doses to forehead and neck received by a radiologist executing angiographic examinations at the department of radiology at the academic hospital (AZ-VUB) have been measured for a group of 34 examinations. The doses to crystalline lens and the effective doses for a period of one year have been estimated. For the crystalline lens the maximum dose approaches the ICRP limit, that indicates the necessity for the radiologist to use leaded glasses. (N.C.)

Biological dosimetry in radiation accidents. Dose-response curve by chromosomal aberrations analysis

International Nuclear Information System (INIS)

Hadjidekova, V.; Hristova, R.; Atanasova, P.; Popova, L.; Stainova, A.; Bulanova, M.; Georgieva, I.; Vukov, M.

2005-01-01

The aim of this paper is to obtain a dose-response relationship for chromosomal aberrations induced in human lymphocytes after in vitro irradiation. Peripheral blood samples of 7 different donors were used. The blood irradiation was done with Cs137 gamma-rays at different doses: 0.0, 0.05, 0.1, 0.25, 0.5, 0.75, 1.0, 1.5, 2.0 and 3.0 Gy. Lymphocyte cultures were established and maintain for 48 hours at 37 0 C in CO 2 incubator for chromosomal aberration analysis. The dose response relationship has been established based on dysenteric and ring chromosomes yield. The relationship can be described by the following equation: Y = 0.0274D + 0.0251 D 2 , where (Y) = dysenteric and ring chromosomes yield, (D) = radiation dose obtained. EXCEL software was established for calculation of the received dose by using this equation, as a whole body equivalent dose acute irradiation

Introduction to benchmark dose methods and U.S. EPA's benchmark dose software (BMDS) version 2.1.1

International Nuclear Information System (INIS)

Davis, J. Allen; Gift, Jeffrey S.; Zhao, Q. Jay

2011-01-01

Traditionally, the No-Observed-Adverse-Effect-Level (NOAEL) approach has been used to determine the point of departure (POD) from animal toxicology data for use in human health risk assessments. However, this approach is subject to substantial limitations that have been well defined, such as strict dependence on the dose selection, dose spacing, and sample size of the study from which the critical effect has been identified. Also, the NOAEL approach fails to take into consideration the shape of the dose-response curve and other related information. The benchmark dose (BMD) method, originally proposed as an alternative to the NOAEL methodology in the 1980s, addresses many of the limitations of the NOAEL method. It is less dependent on dose selection and spacing, and it takes into account the shape of the dose-response curve. In addition, the estimation of a BMD 95% lower bound confidence limit (BMDL) results in a POD that appropriately accounts for study quality (i.e., sample size). With the recent advent of user-friendly BMD software programs, including the U.S. Environmental Protection Agency's (U.S. EPA) Benchmark Dose Software (BMDS), BMD has become the method of choice for many health organizations world-wide. This paper discusses the BMD methods and corresponding software (i.e., BMDS version 2.1.1) that have been developed by the U.S. EPA, and includes a comparison with recently released European Food Safety Authority (EFSA) BMD guidance.

Exposure doses to angiographers during interventional angiography

International Nuclear Information System (INIS)

Fukutomi, Yukimi; Yasuhara, Yoshifumi; Sugata, Shigenori; Fujii, Takashi; Kawakami, Toshiaki; Ikezoe, Junpei

1997-01-01

We report the exposure doses to angiographers during interventional angiography and the protective efficacy of protective aprons against X-rays in this study. The first (main) angiographer was exposed to the maximum dose of 1 μSv/min at the left chest area and lower abdominal area inside the protective apron. The second (assistant) angiographer was exposed to the maximum dose of 2 μSv/min at the left chest area and 1 μSv/min at the lower abdominal area. X-ray transmission ratio of the protective apron was 4.9 percent or less for UL25L, O percent for 0.35 mmPb and 4.3 percent or less for 0.5 mmPb. These results were lower than the dose equivalent limit based on the laws and ordinances. The protection capacities of these protective aprons proved to be sufficient. The exposure dose at the left extremity area outside the protective apron, however, was 24 times higher than at the left chest area inside. The data showed that it was not protected from scattered X-rays outside the protective apron. It is imperative to consider secondary protective material for the area outside the protective apron. Considering the risk of radiation, we need to better control exposure to angiographers. (author)

90Y/90 Sr electron induced damages in an essential eucalyptus oil related to the absorbed dose

International Nuclear Information System (INIS)

Heredia Cardona, J.A.; Diaz Rizo, O.; Martinez Luzardo, F.; Quert, R.

2007-01-01

A good irradiation geometry was achieved in order to carry out the irradiation of an essential eucalyptus oil with a 90 Y/ 90 Sr electron source. The Monte Carlo simulation code MCNP-4C was employed to determine the absorbed doses in this particular experimental configuration. It also helped us to understand which electrons (from an energetic point of view) were responsible for the damages. In order to identify the induced damages, the irradiated samples were studied by mass spectrometry. The obtained results were related to the absorbed doses determined by the computational simulation

Patient dose measurement and dose reduction in chest radiography

Directory of Open Access Journals (Sweden)

Milatović Aleksandra A.

2014-01-01

Full Text Available Investigations presented in this paper represent the first estimation of patient doses in chest radiography in Montenegro. In the initial stage of our study, we measured the entrance surface air kerma and kerma area product for chest radiography in five major health institutions in the country. A total of 214 patients were observed. We reported the mean value, minimum and third quartile values, as well as maximum values of surface air kerma and kerma area product of patient doses. In the second stage, the possibilities for dose reduction were investigated. Mean kerma area product values were 0.8 ± 0.5 Gycm2 for the posterior-anterior projection and 1.6 ± 0.9 Gycm2 for the lateral projection. The max/min ratio for the entrance surface air kerma was found to be 53 for the posterior-anterior projection and 88 for the lateral projection. Comparing the results obtained in Montenegro with results from other countries, we concluded that patient doses in our medical centres are significantly higher. Changes in exposure parameters and increased filtration contributed to a dose reduction of up to 36% for posterior-anterior chest examinations. The variability of the estimated dose values points to a significant space for dose reduction throughout the process of radiological practice optimisation.

Accurate convolution/superposition for multi-resolution dose calculation using cumulative tabulated kernels

International Nuclear Information System (INIS)

Lu Weiguo; Olivera, Gustavo H; Chen Mingli; Reckwerdt, Paul J; Mackie, Thomas R

2005-01-01

Convolution/superposition (C/S) is regarded as the standard dose calculation method in most modern radiotherapy treatment planning systems. Different implementations of C/S could result in significantly different dose distributions. This paper addresses two major implementation issues associated with collapsed cone C/S: one is how to utilize the tabulated kernels instead of analytical parametrizations and the other is how to deal with voxel size effects. Three methods that utilize the tabulated kernels are presented in this paper. These methods differ in the effective kernels used: the differential kernel (DK), the cumulative kernel (CK) or the cumulative-cumulative kernel (CCK). They result in slightly different computation times but significantly different voxel size effects. Both simulated and real multi-resolution dose calculations are presented. For simulation tests, we use arbitrary kernels and various voxel sizes with a homogeneous phantom, and assume forward energy transportation only. Simulations with voxel size up to 1 cm show that the CCK algorithm has errors within 0.1% of the maximum gold standard dose. Real dose calculations use a heterogeneous slab phantom, both the 'broad' (5 x 5 cm 2 ) and the 'narrow' (1.2 x 1.2 cm 2 ) tomotherapy beams. Various voxel sizes (0.5 mm, 1 mm, 2 mm, 4 mm and 8 mm) are used for dose calculations. The results show that all three algorithms have negligible difference (0.1%) for the dose calculation in the fine resolution (0.5 mm voxels). But differences become significant when the voxel size increases. As for the DK or CK algorithm in the broad (narrow) beam dose calculation, the dose differences between the 0.5 mm voxels and the voxels up to 8 mm (4 mm) are around 10% (7%) of the maximum dose. As for the broad (narrow) beam dose calculation using the CCK algorithm, the dose differences between the 0.5 mm voxels and the voxels up to 8 mm (4 mm) are around 1% of the maximum dose. Among all three methods, the CCK algorithm

Disaggregation of collective dose-a worked example based on future discharges from the Sellafield nuclear fuel reprocessing site, UK

International Nuclear Information System (INIS)

Jones, S R; Lambers, B; Stevens, A

2004-01-01

Collective dose has long been advocated as an important measure of the detriment associated with practices that involve the use of radioactivity. Application of collective dose in the context of worker protection is relatively straightforward, whereas its application in the context of discharges to the environment can yield radically different conclusions depending upon the population groups and integration times that are considered. The computer program PC-CREAM98 has been used to provide an indicative disaggregation into individual dose bands of the collective dose due to potential future radioactive discharges from the nuclear fuel reprocessing site at Sellafield in the UK. Two alternative discharge scenarios are considered, which represent a 'stop reprocessing early, minimum discharge' scenario and a 'reprocessing beyond current contracts' scenario. For aerial discharges, collective dose at individual effective dose rates exceeding 0.015 μSv y -1 is only incurred within the UK, and at effective dose rates exceeding 1.5 μSv y -1 is only incurred within about 20 km of Sellafield. The geographical distribution of collective dose from liquid discharges is harder to assess, but it appears that collective dose incurred outside the UK is at levels of individual effective dose rate below 1.5 μSv y -1 , with the majority being incurred at rates of 0.002 μSv y -1 or less. In multi-attribute utility analyses, the view taken on the radiological detriment to be attributed to the two discharge scenarios will depend critically on the weight or monetary value ascribed to collective doses incurred within the differing bands of individual dose rate

Is the maximum permissible radiation burden for the population indeed permissible

International Nuclear Information System (INIS)

Renesse, R.L. van.

1975-01-01

It is argued that legislation based on the ICRP doses will, under economical influences, lead to a situation where the population is exposed to radiation doses near the maximum permissible dose. Due to cumulative radiation effects, this will introduce unacceptable health risks. Therefore, it will be necessary to lower the legal dose limit of 170 millrem per year per person by a factor 10 to 20

Studying and measuring the gamma radiation doses in Homs city

International Nuclear Information System (INIS)

Sofaan, A. H.

2001-01-01

The gamma radiation dose was measured in Homs city by using many portable dosimeters (electronic dosimeter and Geiger-Muller). The measurements were carried out in the indoor and outdoor buildings, for different time period, through one year (1999-2000). High purity germanium detector with low back ground radiation (HpGe) was used to determine radiation element contained in some building and the surrounding soil. The statistical analysis laws were applied to make sure that the measured dose distribution around average value is normal distribution. The measurement indicates that the gamma indoor dose varies from 312μSv/y to 511μSv/y, with the average annual dose of 385μSv/y. However the gamma outdoor dose rate varies from 307μSv/y to 366μSv/y with an average annual dose 385μSv/y. The annual outdoor gamma radiation dose is about %16 lower than the outdoor dose in Homs City. These measurements have indicated that environmental gamma doses in Homs City are relatively low. This is because that most of the soils and rocks in the area are limestone. (author)

Comparative Assessment of a Single Dose and a 2-dose Vaccination Series of a Quadrivalent Meningococcal CRM-conjugate Vaccine (MenACWY-CRM) in Children 2-10 Years of Age.

Science.gov (United States)

Johnston, William; Essink, Brandon; Kirstein, Judith; Forleo-Neto, Eduardo; Percell, Sandra; Han, Linda; Keshavan, Pavitra; Smolenov, Igor

2016-01-01

We compared the immunogenicity, safety and 1-year antibody persistence of a single-dose and a 2-dose series of a licensed meningococcal ACWY-CRM conjugate vaccine (MenACWY-CRM) in 2- to 10-year-old children. In this phase III, multicenter, observer-blind study, children aged 2-5 years (n = 359) and 6-10 years (n = 356) were randomized 1:1 to receive 2 doses of MenACWY-CRM (ACWY2) or 1 dose of placebo followed by 1 dose of MenACWY-CRM (ACWY1), 2 months apart. Immunogenicity was measured using serum bactericidal activity with human complement (hSBA). Primary outcomes were to assess the immunologic noninferiority and superiority of ACWY2 versus ACWY1. One-month after the second dose, the hSBA seroresponse in ACWY2 was noninferior to ACWY1 for all 4 serogroups, in both age cohorts, and was superior for serogroups C and Y in the 2- to 5-year-old age cohort and for serogroup Y in the 6- to 10-year-old age cohort. Overall, 90%-99% of subjects in ACWY2 and 65%-96% in ACWY1 had hSBA titers ≥ 8; geometric mean titers were 1.8- to 6.4-fold higher in ACWY2 than ACWY1 across serogroups. At 1 year postvaccination, geometric mean titers declined, and the differences between ACWY2 and ACWY1 remained significant for serogroups A and C in the 2- to 5-year-old age cohort and for serogroups C and Y in the 6- to 10-year-old age cohort. The safety profile of MenACWY-CRM was similar in both groups. The single dose and 2-dose MenACWY-CRM series were immunogenic and well tolerated. Although antibody responses were greater after 2 doses, especially in the 2- to 5-year-old age cohort, this difference was less pronounced at 1 year postvaccination.

Pharmacokinetics of surotomycin from phase 1 single and multiple ascending dose studies in healthy volunteers.

Science.gov (United States)

Chandorkar, Gurudatt; Zhan, Qiao; Donovan, Julie; Rege, Shruta; Patino, Hernando

2017-03-28

Surotomycin, a novel, orally administered, cyclic, lipopeptide antibacterial in development for the treatment of Clostridium difficile-associated diarrhea, has demonstrated minimal intestinal absorption in animal models. Safety, tolerability, and plasma pharmacokinetics of single and multiple ascending oral doses (SAD/MAD) of surotomycin in healthy volunteers were characterized in two randomized, double-blind, placebo-controlled, phase 1 studies. Participants were sequentially enrolled into one of four SAD (500, 1000, 2000, 4000 mg surotomycin) or three MAD (250, 500, 1000 mg surotomycin twice/day for 14 days) cohorts. Ten subjects were randomized 4:1 into each cohort to receive surotomycin or placebo. Surotomycin plasma concentrations rose as dose increased (maximum plasma concentration [C max ]: 10.5, 21.5, 66.6, and 86.7 ng/mL). Systemic levels were generally low, with peak median surotomycin plasma concentrations observed 6-12 h after the first dose. In the MAD study, surotomycin plasma concentrations were higher on day 14 (C max : 25.5, 37.6, and 93.5 ng/mL) than on day 1 (C max : 6.8, 11.0, and 21.1 ng/mL for increasing doses), indicating accumulation. In the SAD study, <0.01% of the administered dose was recovered in urine. Mean surotomycin stool concentration from the 1000 mg MAD cohort was 6394 μg/g on day 5. Both cohorts were well tolerated with all adverse events reported as mild to moderate. Both SAD and MAD studies of surotomycin demonstrated minimal systemic exposure, with feces the primary route of elimination following oral administration; consistent with observations with similar compounds, such as fidaxomicin. Results of these phase 1 studies support the continued clinical development of surotomycin for the treatment of Clostridium difficile-associated diarrhea. NCT02835118 and NCT02835105 . Retrospectively registered, July 13 2016.

Effects of neuropeptide Y on regulation of blood flow rate in canine myocardium

DEFF Research Database (Denmark)

Svendsen, Jesper Hastrup; Sheikh, S P; Jørgensen, J

1990-01-01

The effect of neuropeptide Y (NPY) on tension development was examined in isolated canine coronary arteries, and the effects on local myocardial blood flow rate were studied in open-chest anesthetized dogs by the local 133Xe washout technique. By immunohistochemistry, numerous NPY-like immunoreac......The effect of neuropeptide Y (NPY) on tension development was examined in isolated canine coronary arteries, and the effects on local myocardial blood flow rate were studied in open-chest anesthetized dogs by the local 133Xe washout technique. By immunohistochemistry, numerous NPY......+. In contrast, intracoronary NPY (0.01-10 micrograms) induced a considerable degree of vasoconstriction; the reduction of blood flow rate was dose related, with a maximum reduction to 52% of control values. The effect of intracoronary NPY (1 microgram) on maximally relaxed arterioles elicited by 30 s...... of ischemia was studied in separate experiments during reactive hyperemia. NPY induced a decrease in maximum blood flow during reactive hyperemia (166.6 vs. 214.6% of preocclusive blood flow rate, mean values; P = 0.05), an increase in the cumulative excess blood flow (61.0 vs. 35.3 ml/100 g; P = 0...

Dosimetric comparison of electron beam and 90Sr+90Y applicator for keloids treatment

International Nuclear Information System (INIS)

Coelho, Talita S.; Tada, Ariane; Antonio, Patricia L.; Yoriyaz, Helio; Fernandes, Marco A.R.

2009-01-01

Studies have been shown that among several methods that have been used for the treatment of keloids the surgical excision followed by the adjuvant radiotherapy presents the lowest relapsed rate of the injury. In this work a comparative dosimetric study has been performed using a 4 MeV electron beam from a Varian Clinac 2100C linear accelerator at the radiotherapy service of the Hospital das Clinicas of UNESP-HC, Botucatu-SP and an Amershan 90 Sr+ 90 Y brachytherapy applicator with 1491 MBq of activity. Percentage depth dose curves from ionization chamber measurements and through Monte Carlo simulation have been obtained and compared. Dose measurements have been obtained using parallel plates ionization chamber (Esradin A12) and extrapolation mini-chamber developed at IPEN. The dose calculations have been obtained using the well-known Monte Carlo radiation transport code MCNP-4C. Maximum dose differences obtained between measured/calculated values for 90 Sr+ 90 Y applicator and for the electron beam were, respectively: 7.8 % and 8.0%. The profiles of the depth and superficial tissue dose distribution produced by the electron beam revealed themselves flatter and more homogeneous than those produced by the 90 Sr+ 90 Y applicator, especially to wider fields, which cannot be obtained with beta therapy applicators because of their geometric limitations. In conclusion this present work has shown that 90 Sr+ 90 Y applicators could be efficient for small and very superficial lesions but in most cases electron beam sources are more adequate especially for large and deeper lesions. (author)

Absorbed doses profiles vs Synovia tissue depth for the Y-90 and P-32 used in radiosynoviortesis treatment

International Nuclear Information System (INIS)

Torres B, M.B.; Ayra P, F.E.; Garcia R, E.; Cornejo D, N.; Yoriyaz, H.

2006-01-01

The radiosynoviortesis treatment has been used during more of 40 years as an alternative to the chemical and surgical synovectomy to alleviate the pain and to reduce the inflammation in suffered patients of rheumatic arthropathies, haemophilic arthropathies and other articulation disorders. It consists on the injection of radioactive isotopes inside a synovial cavity. For to evaluate the dosimetry of the radiosynoviortesis treatment is of great interest to know the absorbed dose in the volume of the target (synovia). The precise calculation of the absorbed dose in the inflamed synovia it is difficult, for numerous reasons, since the same one will depend on the thickness of the synovial membrane, the size of the articular space, the structure of the synovial membrane, the distribution in the articulation, the nature of the articular liquid, etc. Also the presence of the bone and the articular cartilage, components also of the articulation, it even complicated more the calculations. The method used to evaluate the dosimetry in radioactive synovectomy is known as the Monte Carlo method. The objective of our work consists on estimating with the Monte Carlo code MCNP4B the absorbed dose of the Y-90 and the P-32 in the depth of the synovial tissue. The results are presented as absorbed dose for injected millicurie (Gy/mCi) versus depth of synovial tissue. The simulation one carries out keeping in mind several synovia areas, of 50 cm 2 to 250 cm 2 keeping in mind three states of progression of the illness. Those obtained values of absorbed dose using the MCNP4B code will allow to introduce in our country an optimized method of dose prescription to the patient, to treat the rheumatic arthritis in medium and big articulations using the Y-90 and the P-32, eliminating the fixed doses and fixed radionuclides for each articulation like it happens in many clinics of Europe, as well as the empiric doses. (Author)

Microstructural study of Y{sub 1}Ba{sub 2}Cu{sub 3}O{sub 7-x}/Ag samples irradiated with {sup 60}Co {gamma} rays at high doses

Energy Technology Data Exchange (ETDEWEB)

Rangel, R [Programa de Postgrado en Fisica de Materiales, Centro de Investigacion Cientifica y de Educacion Superior de Ensenada, Apartado Postal 2681, CP 22800, Ensenada, BC (Mexico); Galvan, D H [CECIMAC-UNAM, Apartado Postal 2681, CP 22800, Ensenada, BC (Mexico); Adem, E [Instituto de Fisica-UNAM, Apartado Postal 20-364, CP 01000, Mexico DF (Mexico); Bartolo-Perez, P [CINVESTAV-IPN Unidad Merida, Departamento de Fisica Aplicada, Merida, Yucatan (Mexico); Maple, M B [Physics Department and Institute for Pure and Applied Physical Sciences, La Jolla, CA (United States)

1998-06-01

We have investigated the damage induced by irradiation in Y{sub 1}Ba{sub 2}Cu{sub 3}O{sub 7-x} silver added samples. The samples were prepared with 0 and 6.5 wt% of silver and irradiated by high-energy {gamma} irradiation (50-150 Mrad). The roles of silver and dosage irradiation are discussed in terms of their effects on microstructure, crystallinity, critical temperature (T{sub c}) and zero-resistance temperature (T{sub 0}). After irradiation, T{sub c} decreased while the room-temperature electrical resistance increased by a factor of 8 for some of the samples. The difference in T{sub 0} between irradiated and non-irradiated YBCO samples was of the order of 10 K. We have found that the difference is bigger for silver-added samples. We have also observed several changes in diffraction patterns of YBCO and YBCO-silver samples. SEM images, EDS and XPS analysis showed that silver resided inside the grains as single atoms and as metallic clusters. The relative concentrations of the elements in samples were quantified by Auger electron spectroscopy. The values showed a gradual increase for radiation doses ranging between 0 and 100 Mrad. For doses up to 100 Mrad, J{sub c} decreased because of the weak-link breakage induced by high doses of {gamma} rays. (author)

Inhomogeneous target-dose distributions: a dimension more for optimization?

International Nuclear Information System (INIS)

Gersem, Werner R.T. de; Derycke, Sylvie; Colle, Christophe O.; Wagter, Carlos de; Neve, Wilfried J. de

1999-01-01

Purpose: To evaluate if the use of inhomogeneous target-dose distributions, obtained by 3D conformal radiotherapy plans with or without beam intensity modulation, offers the possibility to decrease indices of toxicity to normal tissues and/or increase indices of tumor control stage III non-small cell lung cancer (NSCLC). Methods and Materials: Ten patients with stage III NSCLC were planned using a conventional 3D technique and a technique involving noncoplanar beam intensity modulation (BIM). Two planning target volumes (PTVs) were defined: PTV1 included macroscopic tumor volume and PTV2 included macroscopic and microscopic tumor volume. Virtual simulation defined the beam shapes and incidences as well as the wedge orientations (3D) and segment outlines (BIM). Weights of wedged beams, unwedged beams, and segments were determined by optimization using an objective function with a biological and a physical component. The biological component included tumor control probability (TCP) for PTV1 (TCP1), PTV2 (TCP2), and normal tissue complication probability (NTCP) for lung, spinal cord, and heart. The physical component included the maximum and minimum dose as well as the standard deviation of the dose at PTV1. The most inhomogeneous target-dose distributions were obtained by using only the biological component of the objective function (biological optimization). By enabling the physical component in addition to the biological component, PTV1 inhomogeneity was reduced (biophysical optimization). As indices for toxicity to normal tissues, NTCP-values as well as maximum doses or dose levels to relevant fractions of the organ's volume were used. As indices for tumor control, TCP-values as well as minimum doses to the PTVs were used. Results: When optimization was performed with the biophysical as compared to the biological objective function, the PTV1 inhomogeneity decreased from 13 (8-23)% to 4 (2-9)% for the 3D-(p = 0.00009) and from 44 (33-56)% to 20 (9-34)% for the BIM

Effects of prenatal low dose beta radiation from tritiated water on rat hippocampus neurons. Electrophysiological and neuro behavioural changes

International Nuclear Information System (INIS)

Gao Weimin; Zhou Xiangyan

1997-01-01

Pregnent Wistar rats were exposed to tritiated water (HTO) on day 13 of gestation so that for their offsprings, the absorbed doses were estimated to be 0.000, 0.044, 0.088 and 0.264 Gy. The influence of HTO to the morphology and number of hippocampus pyramidal neurons and the maximum electric current of Ca 2+ in neurons was observed for the in-vitro-cultured hippocampus of new-born rats and the learning and memory behaviours were assessed by the electric avoidance reflex test in a Y-maze and the condition reflex test for young rats. The results show that prenatal exposure to HTO in a cumulative dose of 0.088 Gy can cause a reduction in number of neurons in hippocampus cultured in vitro, and that the electric current of Ca 2+ tends to decline with cumulative dose increasing, with the significant decrease in offsprings prenatally exposed to HTO in dose of 0.264 Gy. The results of electric avoidance reflex test in a Y-maze and condition reflex test indicate that for young rats prenatally exposed to HTO, a cumulative dose of 0.088 Gy could induce damage in their learning and memory behaviours

Maximum credible accident analysis for TR-2 reactor conceptual design

International Nuclear Information System (INIS)

Manopulo, E.

1981-01-01

A new reactor, TR-2, of 5 MW, designed in cooperation with CEN/GRENOBLE is under construction in the open pool of TR-1 reactor of 1 MW set up by AMF atomics at the Cekmece Nuclear Research and Training Center. In this report the fission product inventory and doses released after the maximum credible accident have been studied. The diffusion of the gaseous fission products to the environment and the potential radiation risks to the population have been evaluated

Internal doses of French adult population linked to the intake of radionuclides from the decay-chains of uranium and thorium by foodstuffs ingestion

International Nuclear Information System (INIS)

Renaud, Ph.; Parache, V.; Roussel-Debet, S.

2015-01-01

This study provides the first dose assessment to the French adult population due to the intake of radionuclides from the decay chains of uranium and thorium by foodstuff ingestion (water consumption excepted). This dose varies widely with the consumption of seafood, from less than 200 μSv.y -1 for people who do not consume shellfish or crustaceans at all, to more than 2,000 μSv.y -1 for the biggest consumers (about 150 kg.y -1 according to specific dietary surveys carried out along the French seaside). For moderate consumers of seafood (around 4.6 kg.y -1 ), who probably represent a major part of the population, this internal dose would be around 330 μSv.y -1 . This variable consumption of seafood overshadows all the other causes of variability of these internal dose estimates. (authors)

The MLC tongue-and-groove effect on IMRT dose distributions

Energy Technology Data Exchange (ETDEWEB)

Deng Jun [Department of Radiation Oncology, Stanford University School of Medicine, Stanford, CA 94305 (United States). E-mail: jun@reyes.stanford.edu; Pawlicki, Todd; Chen Yan; Li Jinsheng; Jiang, Steve B.; Ma, C.-M. [Department of Radiation Oncology, Stanford University School of Medicine, Stanford, CA 94305 (United States)

2001-04-01

We have investigated the tongue-and-groove effect on the IMRT dose distributions for a Varian MLC. We have compared the dose distributions calculated using the intensity maps with and without the tongue-and-groove effect. Our results showed that, for one intensity-modulated treatment field, the maximum tongue-and-groove effect could be up to 10% of the maximum dose in the dose distributions. For an IMRT treatment with multiple gantry angles ({>=} 5), the difference between the dose distributions with and without the tongue-and-groove effect was hardly visible, less than 1.6% for the two typical clinical cases studied. After considering the patient setup errors, the dose distributions were smoothed with reduced and insignificant differences between plans with and without the tongue-and-groove effect. Therefore, for a multiple-field IMRT plan ({>=} 5), the tongue-and-groove effect on the IMRT dose distributions will be generally clinically insignificant due to the smearing effect of individual fields. The tongue-and-groove effect on an IMRT plan with small number of fields (<5) will vary depending on the number of fields in a plan (coplanar or non-coplanar), the MLC leaf sequences and the patient setup uncertainty, and may be significant (>5% of maximum dose) in some cases, especially when the patient setup uncertainty is small ({<=} 2 mm). (author)

Natural radioactivity, dose assessment and uranium uptake by agricultural crops at Khan Al-Zabeeb, Jordan

International Nuclear Information System (INIS)

Al-Kharouf, Samer J.; Al-Hamarneh, Ibrahim F.; Dababneh, Munir

2008-01-01

Khan Al-Zabeeb, an irrigated cultivated area lies above a superficial uranium deposits, is regularly used to produce vegetables and fruits consumed by the public. Both soil and plant samples collected from the study area were investigated for their natural radioactivity to determine the uranium uptake by crops and hence to estimate the effective dose equivalent to human consumption. Concentrations of 238 U, 235 U, 232 Th, 226 Ra, 222 Rn, 137 Cs and 40 K in nine soil profiles were measured by gamma-ray spectrometry whereas watermelon and zucchini crops were analyzed for their uranium content by means of alpha spectrometry after radiochemical separation. Correlations between measured radionuclides were made and their activity ratios were determined to evaluate their geochemical behavior in the soil profiles. Calculated soil-plant transfer factors indicate that the green parts (leaves, stems and roots) of the studied crops tend to accumulate uranium about two orders of magnitude higher than the fruits. The maximum dose from ingestion of 1 kg of watermelon pulp was estimated to be 3.1 and 4.7 nSv y -1 for 238 U and 234 U, respectively. Estimations of the annual effective dose equivalent due to external exposure showed extremely low values. Radium equivalent activity and external hazard index were seen to exceed the permissible limits of 370 Bq kg -1 and 1, respectively

Dose constraints and guidance for exposure of individuals knowingly and willingly helping in the support and comfort of individuals undergoing medical exposure

International Nuclear Information System (INIS)

Jansen, J. Th M.; Zoetelief, J.

2006-01-01

The council of the European Union (EU) has adopted directive 97/43/ EURATOM that states that Member States shall ensure that dose constraints are established for exposure of those individuals (voluntary helpers) knowingly and willingly helping patients undergoing medical diagnosis or treatment. This study investigates for which medical diagnoses and treatments voluntary helpers are active. It provides a rough estimation of the effective dose to the voluntary helper for various applications. It summarises the dose constraints established in various EU Member States. Voluntary helpers are especially active in paediatric radiology and in nuclear medicine for both diagnostic and for therapeutic purposes. No voluntary helpers are active during radiotherapy. Voluntary helpers are commonly one of the parents, relatives or friends of the patient. In The Netherlands, the highest effective dose to voluntary helpers of ∼2.3 mSv is found for therapy of patients younger than 1 y with metaiodobenzylguanidine labelled with 131 I. Effective doses to voluntary helpers in paediatric radiology are, generally, quite small, i.e. lower than several tens of μSv at maximum without wearing protective clothing. (authors)

Phase I dose-escalation study to examine the safety and tolerability of LY2603618, a checkpoint 1 kinase inhibitor, administered 1 day after pemetrexed 500 mg/m(2) every 21 days in patients with cancer.

Science.gov (United States)

Weiss, Glen J; Donehower, Ross C; Iyengar, Tara; Ramanathan, Ramesh K; Lewandowski, Karen; Westin, Eric; Hurt, Karla; Hynes, Scott M; Anthony, Stephen P; McKane, Scott

2013-02-01

This phase I study aims at assessing the safety and tolerability of LY2603618, a selective inhibitor of Checkpoint Kinase 1, in combination with pemetrexed and determining the maximum tolerable dose and the pharmacokinetic parameters. This was an open-label, multicenter, dose-escalation study in patients with advanced solid tumors. Increasing doses of LY2603618 (40-195 mg/m(2)) were combined with 500 mg/m(2) of pemetrexed. LY2603618 was administered on Days 1 and 9 and pemetrexed on Day 8 in a 28-day cycle. For all subsequent 21-day cycles, pemetrexed was administered on Day 1 and LY2603618 on Day 2. Antitumor activity was evaluated as per Response Evaluation Criteria in Solid Tumors 1.0. A total of 31 patients were enrolled into six cohorts (three at 40 mg/m(2) over 4.5-hour infusion, 1-hour infusion in subsequent cohorts: three each at 40 mg/m(2), 70 mg/m(2), and 195 mg/m(2); 13 at 105 mg/m(2); six at 150 mg/m(2)). Four patients experienced a dose-limiting toxicity: diarrhea (105 mg/m(2)); reversible infusion-related reaction (150 mg/m(2)); thrombocytopenia (195 mg/m(2)); and fatigue (195 mg/m(2)). The maximum tolerated dose was defined as 150 mg/m(2). The pharmacokinetic data demonstrated that the exposure of LY2603618 increased in a dose-dependent manner, displayed a suitable half-life for maintaining required human exposures while minimizing the intra- and inter-cycle accumulation, and was unaffected by the pemetrexed administration. The pharmacokinetic-defined biologically efficacious dose was achieved at doses ≥105 mg/m(2). LY2603618 administered approximately 24 h after pemetrexed showed acceptable safety and pharmacokinetic profiles.

Determination of radon activity concentration in drinking water and evaluation of the annual effective dose in Hassan district, Karnataka state, India

International Nuclear Information System (INIS)

Srinivasa, E.; Rangaswamy, D.R.; Sannappa, J.

2015-01-01

The radon concentration has been determined in 27 drinking water samples of Hassan district and was estimated by using emanometry technique and physicochemical parameters were estimated using standard techniques. The 222 Rn concentrations in water are varying from 0.85 ± 0.2 to 60.74 ± 2.5 Bq l -1 with an average value of 26.5 ± 1.65 Bq l -1 . This study reveals that 66 % of the drinking water samples have radon concentration level in excess of the EPA recommended maximum contamination level of 11.1 Bq l -1 . There is no significant correlation noted between radon concentration and physicochemical parameters. The mean annual effective ingestion doses received from all samples are lower than 0.1 mSv y -1 . (author)

Evaluation of a pyrex glass shield for the dose reduction in extremities to manipulate a 90 Sr- 90 Y generator

International Nuclear Information System (INIS)

Ayra P, F.E.; Xiques C, A.; Torres B, M.B.

2006-01-01

The production of Y-90 of high activity it specifies (free of payee) for their use in radioimmunotherapy uses the Strontium 90 as isotope source. Depending on the method employee for the separation of both isotopes several types of generators are described in different bibliographies. The column generator used in the facilities of the Center of Isotopes requires of a frequent manipulation causing significant dose in the skin of the extremities due to the exhibition to the radiation beta of high energy. The properties of the shieldings for this radiation type have been well studied Y they consist in several publications. To be in correspondence with requirements of radiological protection in the Cuban legislation, the column was covered with a tube of glass pyrex of 5 mm of thickness and it was monitored the exposure with an ionization chamber. At the own time, the shielding using the Monte Carlo method was evaluated. It was used the MCNP 4C code to simulate the absorption of the beta particles generated in the process of disintegration of the Sr-90 and Y-90 in the glass shielding. The column generator and the fluence of beta particles were modeled in different points inside the shielding to determine if the experimentally measured values correspond to electrons that were not absorbed or to the weak stopping radiation generated in the glass due to the deceleration of these particles. A cylinder of 4 mm of diameter simulates the source (it dilutes) and a tube of walls of 6 mm of thickness simulates the shielding more the wall of the column around the generator. This it was divided in cells of 1 mm of thickness and the energy deposited in them was evaluated. The results show that all the electrons generated in the source are absorbed in the shielding and the exposure rates decrease in more of 78 times using the 5 mm of pyrex glass. The doses in extremities to the operators of the generator don't surpass the 70 mSv by year that is the dose restriction imposed in the

Natural radioactivity contents in tobacco and radiation dose induced from smoking

International Nuclear Information System (INIS)

Shousha, H. A.; Ahmad, F.

2012-01-01

One of the causative factors for cancer-inducing mechanisms in humans is radioactive elements present in tobacco leaves used in the manufacture of cigarettes. Smoking of tobacco and its products increases the internal intake and radiation dose due to naturally occurring radionuclides that are considered to be one of the most significant causes of lung cancer. In this work, different commercial types of cigarettes, cigar and moassel were collected from market. Naturally occurring radionuclides 226 Ra and 214 Bi ( 238 U series), 228 Ac and 228 Ra ( 232 Th series), 40 K and man-made 137 Cs were measured in tobacco using gamma-ray spectrometer. Results show that the average concentrations of 238 U, 232 Th and 40 K were 4.564, 3.940 and 1289.53 Bq kg -1 , respectively. This reflects their origin from the soil by root uptake and fertilisers used in the cultivation of tobacco plants. Concentration of 137 Cs was 0.348 Bq kg -1 due to root uptake or deposition onto the leaf foliage. For smokers, the annual effective dose due to inhalation of 238 U varied from 49.35 to 139.40 μSv -1 (average 104.27 μSv y -1 ), while of 232 Th from 23.86 to 111.06 μSv y -1 (average 65.52 μSv y -1 ). The annual effective dose resulting from 137 Cs was varied from 10.96 to 24.01 nSv y -1 (average 19.41 nSv y -1 ). (authors)

Committed effective dose determination in southern Brazilian cereal flours.

Science.gov (United States)

Scheibel, V; Appoloni, C R

2013-01-01

The health impact of radionuclide ingestion from foodstuffs was evaluated by the committed effective doses determined in eight commercial samples of South-Brazilian cereal flours (soy, wheat, cornmeal, cassava, rye, oat, barley and rice flours). The radioactivity traces of (228)Th, (228)Ra, (226)Ra, (40)K, (7)Be and (137)Cs were measured by gamma-ray spectrometry employing an HPGe detector of 66 % relative efficiency. The efficiency curve has taken into account the differences in densities and chemical composition between the matrix and the certified sample. The highest concentration levels of (228)Th and (40)K were 3.5±0.4 and 1469±17 Bq kg(-1) for soy flour, respectively, within the 95 % confidence level. The lower limit of detection for (137)Cs ranged from 0.04 to 0.4 Bq kg(-1). The highest committed effective dose was 0.36 μSv.y(-1) for (228)Ra in cassava flour (adults). All committed effective doses determined at the present work were lower than the International Atomic Energy Agency dose limit of 1 mSv.y(-1), to the public exposure.

Committed effective dose determination in southern Brazilian cereal flours

International Nuclear Information System (INIS)

Scheibel, V.; Appoloni, C. R.

2013-01-01

The health impact of radionuclide ingestion from foodstuffs was evaluated by the committed effective doses determined in eight commercial samples of South-Brazilian cereal flours (soy, wheat, cornmeal, cassava, rye, oat, barley and rice flours). The radioactivity traces of 228 Th, 228 Ra, 226 Ra, 40 K, 7 Be and 137 Cs were measured by gamma-ray spectrometry employing an HPGe detector of 66 % relative efficiency. The efficiency curve has taken into account the differences in densities and chemical composition between the matrix and the certified sample. The highest concentration levels of 228 Th and 40 K were 3.5±0.4 and 1469±17 Bq kg -1 for soy flour, respectively, within the 95 % confidence level. The lower limit of detection for 137 Cs ranged from 0.04 to 0.4 Bq kg -1 . The highest committed effective dose was 0.36 μSv.y -1 for 228 Ra in cassava flour (adults). All committed effective doses determined at the present work were lower than the International Atomic Energy Agency dose limit of 1 mSv.y -1 , to the public exposure. (authors)

Dosimetry in radionuclide therapies with 90Y-conjugates. The IEO experience

International Nuclear Information System (INIS)

Cremonesi, M.; Ferrari, M.; Chinol, M.; Bartolomei, M.; Sacco, E.; Fiorenza, M.; Tosi, G.; Paganelli, G.; Stabin, M. G.

2000-01-01

The basis for successful radionuclide therapy is a high and stable uptake of the radiopharmaceutical in the target tissue along with low activity concentration in other normal organs. The contribution of dosimetry in radionuclide therapy is to predict before the treatment the absorbed doses in tumor and normal organs, to identify the critical organs, to minimize any possible toxicity and to evaluate the maximum tolerated dose. In this article is reported the experience concerning pharmacokinetics and dosimetry of two 90 Y-therapeutic protocols: 3-step pretargeting radioimmunotherapy (RIT) according to the biotin-avidin system and receptor mediated radionuclide therapy with the somatostatin analogue (DOTA-D-Phe 1 -Tyr 3 ) octreotide named DOTATOC. For the dosimetric analysis, analogous approaches for the two radiolabeled compounds due to the similar pharmacokinetic characteristics were adopted; the MIRD formalism was applied, taking into account both the physical and the biological characteristics of the radio conjugate and patients' metabolism. In order to determine biological clearance, serial blood samples and complete urine collection were obtained up to 48 hours after injection; to evaluate biodistribution, several whole body scans were acquired. Both therapies showed the advantageous characteristics of a fast blood clearance and a predominantly renal excretion of the radiopharmaceuticals thus lowering the irradiation of the total body. Although pharmacokinetic characteristics were similar, different critical organs were found for the two therapies: in particular, some considerations regarding red marrow, spleen and kidneys were required. The results of the studies indicate that high activities of 90 Y-biotin (3-step RIT) and 90 Y-DOTATOC can be administered with acceptable radiation doses to normal organs

Low-dose/dose-rate γ radiation depresses neural differentiation and alters protein expression profiles in neuroblastoma SH-SY5Y cells and C17.2 neural stem cells.

Science.gov (United States)

Bajinskis, Ainars; Lindegren, Heléne; Johansson, Lotta; Harms-Ringdahl, Mats; Forsby, Anna

2011-02-01

The effects of low doses of ionizing radiation on cellular development in the nervous system are presently unclear. The focus of the present study was to examine low-dose γ-radiation-induced effects on the differentiation of neuronal cells and on the development of neural stem cells to glial cells. Human neuroblastoma SH-SY5Y cells were exposed to (137)Cs γ rays at different stages of retinoic acid-induced neuronal differentiation, and neurite formation was determined 6 days after exposure. When SH-SY5Y cells were exposed to low-dose-rate γ rays at the onset of differentiation, the number of neurites formed per cell was significantly less after exposure to either 10, 30 or 100 mGy compared to control cells. Exposure to 10 and 30 mGy attenuated differentiation of immature C17.2 mouse-derived neural stem cells to glial cells, as verified by the diminished expression of glial fibrillary acidic protein. Proteomic analysis of the neuroblastoma cells by 2D-PAGE after 30 mGy irradiation showed that proteins involved in neuronal development were downregulated. Proteins involved in cell cycle and proliferation were altered in both cell lines after exposure to 30 mGy; however, the rate of cell proliferation was not affected in the low-dose range. The radiation-induced attenuation of differentiation and the persistent changes in protein expression is indicative of an epigenetic rather than a cytotoxic mechanism.

Exposure dose in recent treatment of nuclear medicine and countermeasures

International Nuclear Information System (INIS)

Iio, Masahiro

1974-01-01

Radioactive pharmaceuticals widely used for the diagnosis in nuclear medicine utilize radiation as tracer for dynamic behavior measurement and locality diagnosis, and the exposure due to their use has very little chance to attain the maximum permissible dose of ICRP. The MIRD (Medical Internal Radiation Dose) method tends to be adopted for the measurement of internally absorbed dose due to radio-pharmaceuticals in future. The feature of the MIRD method is that the targeted object is not a critical organ but the region of interest, and the source organ and target organ are fully taken into consideration. Recently, the exposure of patients has been significantly lowered by applying sup(99m)Tc and the like. Though the contribution to national dose is small, it is required to perform immediate conversion from the older nuclear medicine typified with conventional 131 I, 198 Au and 203 Hg to modern one centering around sup(99m)Tc. The problems in calculating the absorbed dose due to nuclear medicine diagnosis are very low accuracy of biological data though the high accuracy of data in physics has been achieved, and the difficulty to obtain data for calculating patients' absorbed dose in routine inspection. (Wakatsuki, Y.)

Value of public health and safety actions and radiation dose avoided

Energy Technology Data Exchange (ETDEWEB)

Baum, J.W. [Brookhaven National Lab., Upton, NY (United States)

1994-05-01

The values judged best to reflect the willingness of society to pay for the avoidance or reduction of risk were deduced from studies of costs of health care, transportation safety, consumer product safety, government agency actions, wage-risk compensation, consumer behavior (market) studies, and willingness-to-pay surveys. The results ranged from $1,400,000 to $2,700,000 per life saved. Applying the mean of these values ($2,100,000) and the latest risk per unit dose coefficients used by the ICRP (1991), which take into account risks to the general public, including genetic effects and nonfatal cancers, yields a value of dose avoided of $750 to $1,500 per person-cSv for public exposures. The lower value applies if adjustments are made for years of life lost per fatality. A nominal value of $1,000 per person-cSv seems appropriate in light of the many uncertainties involved in deducing these values. These values are consistent with values recommended by several European countries for individual doses in the region of 1 mSv/y (100 mrem/y). Below this dose rate, most countries have values a factor of 7 to 10 lower, based on the assumption that society is less concerned with fatality risks below about 10{sup {minus}4}/y.

Value of public health and safety actions and radiation dose avoided

International Nuclear Information System (INIS)

Baum, J.W.

1994-05-01

The values judged best to reflect the willingness of society to pay for the avoidance or reduction of risk were deduced from studies of costs of health care, transportation safety, consumer product safety, government agency actions, wage-risk compensation, consumer behavior (market) studies, and willingness-to-pay surveys. The results ranged from $1,400,000 to $2,700,000 per life saved. Applying the mean of these values ($2,100,000) and the latest risk per unit dose coefficients used by the ICRP (1991), which take into account risks to the general public, including genetic effects and nonfatal cancers, yields a value of dose avoided of $750 to $1,500 per person-cSv for public exposures. The lower value applies if adjustments are made for years of life lost per fatality. A nominal value of $1,000 per person-cSv seems appropriate in light of the many uncertainties involved in deducing these values. These values are consistent with values recommended by several European countries for individual doses in the region of 1 mSv/y (100 mrem/y). Below this dose rate, most countries have values a factor of 7 to 10 lower, based on the assumption that society is less concerned with fatality risks below about 10 -4 /y

Cosmic-ray-induced radiation environment and dose to man for low-orbit space applications

International Nuclear Information System (INIS)

Sandmeier, H.A.; Hansen, G.E.; Battat, M.E.; O'Brien, K.

1981-09-01

Neutrons and photons resulting from the interaction of galactic cosmic rays with the material of an orbiting satellite or an orbiting space station at an altitude of some few hundreds of kilometers, and below the level of the radiation belts, have been calculated as a function of geomagnetic latitude and solar activity level. The photon and neutron leakage currents from the top of the atmosphere have been computed. The radiation dose-equivalent rate to an unshielded astronaut has also been calculated. The maximum dose-equivalent rate, near the magnetic poles, was 2 mrem/h. In deep space this would amount to 18 rem/y, indicating that for a prolonged stay in space, shielding would be needed

Isothermal section of the Y-Co-V ternary system at 500 deg. C

International Nuclear Information System (INIS)

Wei, X.X.; Yan, J.L.; Du, H.W.; Wu, C.L.; Zhou, K.W.; Zhuang, Y.H.; Li, J.Q.

2011-01-01

Research highlights: → The isothermal section of the Y-Co-V system at 500 deg. C has been established. → Only one ternary compound YV x Co 12-x was found in this system and it exhibits a linear homogeneity range for 1.30 ≤ x ≤ 3.64. → The maximum solid solubilities of V in the compounds Y 2 Co 17 , Y 2 Co 7 , YCo 3 , YCo 2 and Y 3 Co are about 10, 1.0, 3.0, 4.0 and 4.0 at.%, respectively. - Abstract: The isothermal section of the Y-Co-V system at 500 deg. C has been investigated by X-ray diffraction, scanning electron microscopy and energy dispersive X-ray spectroscopy. Only one ternary compound YV x Co 12-x with a homogeneity range of 1.30 ≤ x ≤3.64 was found in this system. The maximum solid solubilities of V in Y 2 Co 17 , Y 2 Co 7 , YCo 3 , YCo 2 and Y 3 Co are about 10.0, 1.0, 3.0, 4.0 and 4.0 at.% V, respectively. The compounds VCo and VCo 3 have a homogeneity range of 46-66 at.% V and 22-30 at.% V, respectively. The maximum solid solubility of Y in VCo is about 2.0 at.% Y.

The absorbed dose to blood from blood-borne activity

International Nuclear Information System (INIS)

Hänscheid, H; Fernández, M; Lassmann, M

2015-01-01

The radiation absorbed dose to blood and organs from activity in the blood is relevant for nuclear medicine dosimetry and for research in biodosimetry. The present study provides coefficients for the average absorbed dose rates to the blood from blood-borne activity for radionuclides frequently used in targeted radiotherapy and in PET diagnostics. The results were deduced from published data for vessel radius-dependent dose rate coefficients and reasonable assumptions on the blood-volume distribution as a function of the vessel radius. Different parts of the circulatory system were analyzed separately. Vessel size information for heart chambers, aorta, vena cava, pulmonary artery, and capillaries was taken from published results of morphometric measurements. The remaining blood not contained in the mentioned vessels was assumed to reside in fractal-like vascular trees, the smallest branches of which are the arterioles or venules. The applied vessel size distribution is consistent with recommendations of the ICRP on the blood-volume distribution in the human. The resulting average absorbed dose rates to the blood per nuclear disintegration per milliliter (ml) of blood are (in 10 −11  Gy·s −1 ·Bq −1 ·ml) Y-90: 5.58, I-131: 2.49, Lu-177: 1.72, Sm-153: 2.97, Tc-99m: 0.366, C-11: 4.56, F-18: 3.61, Ga-68: 5.94, I-124: 2.55. Photon radiation contributes 1.1–1.2·10 −11  Gy·s −1 ·Bq −1 ·ml to the total dose rate for positron emitters but significantly less for the other nuclides. Blood self-absorption of the energy emitted by ß-particles in the whole blood ranges from 37% for Y-90 to 80% for Tc-99m. The correspondent values in vascular trees, which are important for the absorbed dose to organs, range from 30% for Y-90 to 82% for Tc-99m. (paper)

Randomized Trial of 2 Versus 1 Dose of Measles Vaccine

DEFF Research Database (Denmark)

Brønd, Marie; Martins, Cesario L; Byberg, Stine

2018-01-01

Background: Two doses of measles vaccine (MV) might reduce the nonmeasles mortality rate more than 1 dose of MV does. The effect of 2 versus 1 dose on morbidity has not been examined. Within a randomized trial of the effect of 2 doses versus 1 dose of MV on mortality in Guinea-Bissau, we investig...

Committed effective dose determination in cereal flours by gamma-ray spectrometry

International Nuclear Information System (INIS)

Scheibel, Viviane

2006-01-01

The health impact from radionuclides ingestion of foodstuffs was evaluated by the committed effective doses determined in commercial samples of South-Brazilian cereal flours (soy, wheat, corn, manioc, rye, oat, barley and rice flour). The radioactivity traces of 228 Th, 228 Ra, 226 Ra, 40 K, 7 Be and 137 Cs were measured by gamma-ray spectrometry employing a 66% relative efficiency HPGe detector. The energy resolution for the 1332.46 keV line of 60 Co was 2.03 keV. The committed effective doses were calculated with the activities analyzed in the present flour samples, the foodstuff rates of consumption (Brazilian Institute of Geography and Statistics) and the ingestion dose coefficients (International Commission of Radiological Protection). The reliability median activities were verified with χ 2 tests, assuring the fittings quality. The highest concentration levels of 228 Th and 40 K were 3.5 ± 0.4 and 1469 ± 17 Bq.kg -1 for soy flour, respectively, with 95% of confidence level. The lower limit of detection for 137 Cs ranged from 0.04 to 0.4 Bq.kg -1 . The highest committed effective dose was 0.36 μSv.y -1 for 228 Ra in manioc flour (adults). All committed effective doses determined at the present work were lower than the UNSCEAR limits of 140 μSv.y -1 and much lower than the ICRP (1991) limits of 1 mSv.y -1 , for general public. There are few literature references for natural and artificial radionuclides in foodstuffs and mainly for committed effective doses. This work brings the barley flour data, which is not present at the literature and 7 Be data which is not encountered in foodstuffs at the literature, besides all the other flours data information about activities and committed effective doses. (author)

Phase I dose escalation safety study of nanoparticulate paclitaxel (CTI 52010 in normal dogs

Directory of Open Access Journals (Sweden)

Axiak SM

2011-10-01

Full Text Available Sandra M Axiak1, Kim A Selting1, Charles J Decedue2, Carolyn J Henry1,3, Deborah Tate1, Jahna Howell2, K James Bilof1, Dae Y Kim4 1Department of Veterinary Medicine and Surgery, University of Missouri, Columbia, MO, USA; 2CritiTech Inc, Lawrence, KS, USA; 3Department of Internal Medicine, Division of Hematology and Oncology; 4Department of Veterinary Pathobiology, University of Missouri, Columbia, MO, USA Background: Paclitaxel is highly effective in the treatment of many cancers in humans, but cannot be routinely used in dogs as currently formulated due to the exquisite sensitivity of this species to surfactant-solubilizing agents. CTI 52010 is a formulation of nanoparticulate paclitaxel consisting of drug and normal saline. Our objectives were to determine the maximally tolerated dose, dose-limiting toxicities, and pharmacokinetics of CTI 52010 administered intravenously to normal dogs. Methods: Three normal adult hound dogs were evaluated by physical examination, complete blood count, chemistry profile, and urinalysis. Dogs were treated with staggered escalating dosages of CTI 52010 with a 28-day washout. All dogs were treated with a starting dosage of 40 mg/m2, and subsequent dosages were escalated at 50% (dog 1, 100% (dog 2, or 200% (dog 3 with each cycle, to a maximum of 240 mg/m2. Dogs were monitored by daily physical assessment and weekly laboratory evaluation. Standard criteria were used to grade adverse events. Plasma was collected at regular intervals to determine pharmacokinetics. Dogs were euthanized humanely, and necropsy was performed one week after the last treatment. Results: The dose-limiting toxicity was grade 4 neutropenia and the maximum tolerated dosage was 120 mg/m2. Grade 1–2 gastrointestinal toxicity was noted at higher dosages. Upon post mortem evaluation, no evidence of organ (liver, kidney, spleen toxicity was noted. Conclusion: CTI 52010 was well tolerated when administered intravenously to normal dogs. A starting

Pediatric cT: Implementation of ASIR for Substantial Radiation Dose Reduction While Maintaining Pre-ASIR Image Noise1

Science.gov (United States)

Brady, Samuel L.; Moore, Bria M.; Yee, Brian S.; Kaufman, Robert A.

2015-01-01

Purpose To determine a comprehensive method for the implementation of adaptive statistical iterative reconstruction (ASIR) for maximal radiation dose reduction in pediatric computed tomography (CT) without changing the magnitude of noise in the reconstructed image or the contrast-to-noise ratio (CNR) in the patient. Materials and Methods The institutional review board waived the need to obtain informed consent for this HIPAA-compliant quality analysis. Chest and abdominopelvic CT images obtained before ASIR implementation (183 patient examinations; mean patient age, 8.8 years ± 6.2 [standard deviation]; range, 1 month to 27 years) were analyzed for image noise and CNR. These measurements were used in conjunction with noise models derived from anthropomorphic phantoms to establish new beam current–modulated CT parameters to implement 40% ASIR at 120 and 100 kVp without changing noise texture or magnitude. Image noise was assessed in images obtained after ASIR implementation (492 patient examinations; mean patient age, 7.6 years ± 5.4; range, 2 months to 28 years) the same way it was assessed in the pre-ASIR analysis. Dose reduction was determined by comparing size-specific dose estimates in the pre- and post-ASIR patient cohorts. Data were analyzed with paired t tests. Results With 40% ASIR implementation, the average relative dose reduction for chest CT was 39% (2.7/4.4 mGy), with a maximum reduction of 72% (5.3/18.8 mGy). The average relative dose reduction for abdominopelvic CT was 29% (4.8/6.8 mGy), with a maximum reduction of 64% (7.6/20.9 mGy). Beam current modulation was unnecessary for patients weighing 40 kg or less. The difference between 0% and 40% ASIR noise magnitude was less than 1 HU, with statistically nonsignificant increases in patient CNR at 100 kVp of 8% (15.3/14.2; P = .41) for chest CT and 13% (7.8/6.8; P = .40) for abdominopelvic CT. Conclusion Radiation dose reduction at pediatric CT was achieved when 40% ASIR was implemented as a dose

Estimation of eye absorbed doses in head & neck radiotherapy practices using thermoluminescent detectors

Directory of Open Access Journals (Sweden)

Gh Bagheri

2011-09-01

Full Text Available  Determination of eye absorbed dose during head & neck radiotherapy is essential to estimate the risk of cataract. Dose measurements were made in 20 head & neck cancer patients undergoing 60Co radiotherapy using LiF(MCP thermoluminescent dosimeters. Head & neck cancer radiotherapy was delivered by fields using SAD & SSD techniques. For each patient, 3 TLD chips were placed on each eye. Head & neck dose was about 700-6000 cGy in 8-28 equal fractions. The range of eye dose is estimated to be (3.49-639.1 mGy with a mean of maximum dose (98.114 mGy, which is about 3 % of head & neck dose. Maximum eye dose was observed for distsnces of about 3 cm from edge of the field to eye.

Pressurizer /Auxiliary Spray Piping Stress Analysis For Determination Of Lead Shielding Maximum Allow Able Load

International Nuclear Information System (INIS)

Setjo, Renaningsih

2000-01-01

Piping stress analysis for PZR/Auxiliary Spray Lines Nuclear Power Plant AV Unit I(PWR Type) has been carried out. The purpose of this analysis is to establish a maximum allowable load that is permitted at the time of need by placing lead shielding on the piping system on class 1 pipe, Pressurizer/Auxiliary Spray Lines (PZR/Aux.) Reactor Coolant Loop 1 and 4 for NPP AV Unit one in the mode 5 and 6 during outage. This analysis is intended to reduce the maximum amount of radiation dose for the operator during ISI ( In service Inspection) period.The result shown that the maximum allowable loads for 4 inches lines for PZR/Auxiliary Spray Lines is 123 lbs/feet

Development of age-specific Japanese physical phantoms for dose evaluation in infant CT examinations

International Nuclear Information System (INIS)

Yamauchi-Kawaura, C.; Fujii, K.; Imai, K.; Ikeda, M.; Akahane, K.; Obara, S.; Yamauchi, M.; Narai, K.; Katsu, T.

2016-01-01

Secondary to the previous development of age-specific Japanese head phantoms, the authors designed Japanese torso phantoms for dose assessment in infant computed tomography (CT) examinations and completed a Japanese 3-y-old head-torso phantom. For design of age-specific torso phantoms (0, 0.5, 1 and 3 y old), anatomical structures were measured from CT images of Japanese infant patients. From the CT morphometry, it was found that rib cages of Japanese infants were smaller than those in Europeans and Americans. Radiophotoluminescence glass dosemeters were used for dose measurement of a 3-y-old head-torso phantom. To examine the validity of the developed phantom, organ and effective doses by the in-phantom dosimetry system were compared with simulation values in a web-based CT dose calculation system (WAZA-ARI). The differences in doses between the two systems were <20 % at the doses of organs within scan regions and effective doses in head, chest and abdomino-pelvic CT examinations. (authors)

Inhibition of gamma-ray dose-rate effects by D2O and inhibitors of poly(ADP-ribose) synthetase in cultured mammalian L5178Y cells

International Nuclear Information System (INIS)

Ueno, A.M.; Tanaka, O.; Matsudaira, H.

1984-01-01

Effects of deuterium oxide (D 2 O) and 3-aminobenzamide, an inhibitor of poly(ADP-ribose) synthetase, on cell proliferation and survival were studied in cultured mammalian L5178Y cells under growing conditions and after acute and low-dose-rate irradiation at about 0.1 to 0.4 Gy/hr of γ rays. Growth of irradiated and unirradiated cells was inhibited by 45% D 2 O but not by 3-aminobenzamide at 10mM, except for treatments longer than 30 hr. The presence of these agents either alone or in combination during irradiation at low dose rates suppressed almost totally the decrease in cell killing due to the decrease in dose rate. Among other inhibitors tested, theobromine and theophylline were found to be effective in eliminating the dose-rate effects of γ rays. Possible mechanisms underlying the inhibition are discussed

Study of Stark Effect in n-doped 1.55 μm InN0.92yP1-1.92yBiy/InP MQWs

Science.gov (United States)

Bilel, C.; Chakir, K.; Rebey, A.; Alrowaili, Z. A.

2018-05-01

The effect of an applied electric field on electronic band structure and optical absorption properties of n-doped InN0.92y P1-1.92y Bi y /InP multiple quantum wells (MQWs) was theoretically studied using a self-consistent calculation combined with the 16-band anti-crossing model. The incorporation of N and Bi atoms into an InP host matrix leads to rapid reduction of the band gap energy covering a large infrared range. The optimization of the well parameters, such as the well/barrier widths, N/Bi compositions and doping density, allowed us to obtain InN0.92y P1-1.92y Bi y /InP MQWs operating at the wavelength 1.55 μm. Application of the electric field causes a red-shift of the fundamental transition energy T 1 accompanied by a significant change in the spatial distribution of confined electron density. The Stark effect on the absorption coefficient of n-doped InN0.92y P1-1.92y Bi y /InP MQWs was investigated. The Bi composition of these MQWs was adjusted for each electric field value in order to maintain the wavelength emission at 1.55 μm.

Modulation-free bismuth-lead cuprate superconductors: BiPbSr1+xL1-xCuO6 and BiPbSr2Y1-xCaxCu2O8

International Nuclear Information System (INIS)

Manivannan, V.; Gopalakrishnan, J.; Rao, C.N.R.

1991-01-01

Modulation-free BiPbSrLCuO 6 (L=La, Pr, Nd) and BiPbSr 2 YCu 2 O 8 , which are isotypic with the n=1 and 2 members of the Bi 2 Sr 2 Ca n-1 Cu n O 2n+4 family, have been prepared and characterized. These parent compounds are nonsuperconducting, but when doped with holes by substitution chemistry give modulation-free superconducting cuprates of the general formulas BiPbSr 1+xL1-x CuO 6 and BiPbSr 2 Y 1-x Ca x Cu 2 O 8 , exhibiting maximum T c 's of 24 and 85 K, respectively. Significantly, the hole concentration at the maximum T c is 0.12 in the cuprate family with a single Cu-O layer and 0.22 in that with two Cu-O layers

Considerations on absorbed dose estimates based on different β-dose point kernels in internal dosimetry

International Nuclear Information System (INIS)

Uchida, Isao; Yamada, Yasuhiko; Yamashita, Takashi; Okigaki, Shigeyasu; Oyamada, Hiyoshimaru; Ito, Akira.

1995-01-01

In radiotherapy with radiopharmaceuticals, more accurate estimates of the three-dimensional (3-D) distribution of absorbed dose is important in specifying the activity to be administered to patients to deliver a prescribed absorbed dose to target volumes without exceeding the toxicity limit of normal tissues in the body. A calculation algorithm for the purpose has already been developed by the authors. An accurate 3-D distribution of absorbed dose based on the algorithm is given by convolution of the 3-D dose matrix for a unit cubic voxel containing unit cumulated activity, which is obtained by transforming a dose point kernel into a 3-D cubic dose matrix, with the 3-D cumulated activity distribution given by the same voxel size. However, beta-dose point kernels affecting accurate estimates of the 3-D absorbed dose distribution have been different among the investigators. The purpose of this study is to elucidate how different beta-dose point kernels in water influence on the estimates of the absorbed dose distribution due to the dose point kernel convolution method by the authors. Computer simulations were performed using the MIRD thyroid and lung phantoms under assumption of uniform activity distribution of 32 P. Using beta-dose point kernels derived from Monte Carlo simulations (EGS-4 or ACCEPT computer code), the differences among their point kernels gave little differences for the mean and maximum absorbed dose estimates for the MIRD phantoms used. In the estimates of mean and maximum absorbed doses calculated using different cubic voxel sizes (4x4x4 mm and 8x8x8 mm) for the MIRD thyroid phantom, the maximum absorbed doses for the 4x4x4 mm-voxel were estimated approximately 7% greater than the cases of the 8x8x8 mm-voxel. They were found in every beta-dose point kernel used in this study. On the other hand, the percentage difference of the mean absorbed doses in the both voxel sizes for each beta-dose point kernel was less than approximately 0.6%. (author)

Vitamin K3 increased BMD at 1 and 2 months post-surgery and the maximum stress of the middle femur in the rat.

Science.gov (United States)

Hong, You-jia; Liu, Sheng; Jiang, Ning-yi; Jiang, Sen; Liang, Jiu-gen

2015-02-01

The therapeutic effects of vitamin K3 (VK3) on osteoporosis are still unknown. In this study, we hypothesized that VK3 possesses therapeutic effects on osteoporosis; to verify this hypothesis, the ovariectomized rat was used as an osteoporosis model. Fifty-six Sprague-Dawley female rats aged 8 to 9 months were randomly assigned to 4 groups: sham surgery, ovariectomy with saline, ovariectomy with low-dose VK3, and ovariectomy with high-dose VK3. Intramuscular injection of VK3 was performed every other day beginning 1 month postoperatively. The therapeutic effects of VK3 on osteoporosis were evaluated by measurement of bone mineral density (BMD), bone biochemical markers, biomechanical properties, and bone morphometric parameters. The overall average BMD in VK3-treated groups increased to a level between those of the ovariectomy group and the sham surgery group. The procollagen I N-terminal peptide level peaked at 2 months after surgery in all groups except in the group that had undergone ovariectomy with low-dose VK3. The tartrate-resistant acid phosphatase 5b level increased more slowly at 4 months after surgery than at 2 months after surgery in the VK3-treated groups. The ovariectomy with high-dose VK3 group had the highest maximum stress of the middle femur of all groups. With VK3 treatment, the trabecular bone area percentage increased. All morphometric indicators for the middle tibia in the VK3-treated groups reached the levels found in the sham surgery group. In summary, VK3 therapy increased BMD at 1 and 2 months postsurgery and the maximum stress of the middle femur. In addition, VK3 therapy slowed the increase in bone turnover in ovariectomized rats. Furthermore, VK3 can improve morphometric indicators for the middle tibia. Our preliminary study indicates that VK3 has a potential therapeutic effect on osteoporosis and is worthy of further investigation. Copyright © 2015 Elsevier Inc. All rights reserved.

Variability of Marker-Based Rectal Dose Evaluation in HDR Cervical Brachytherapy

International Nuclear Information System (INIS)

Wang Zhou; Jaggernauth, Wainwright; Malhotra, Harish K.; Podgorsak, Matthew B.

2010-01-01

In film-based intracavitary brachytherapy for cervical cancer, position of the rectal markers may not accurately represent the anterior rectal wall. This study was aimed at analyzing the variability of rectal dose estimation as a result of interfractional variation of marker placement. A cohort of five patients treated with multiple-fraction tandem and ovoid high-dose-rate (HDR) brachytherapy was studied. The cervical os point and the orientation of the applicators were matched among all fractional plans for each patient. Rectal points obtained from all fractions were then input into each clinical treated plan. New fractional rectal doses were obtained and a new cumulative rectal dose for each patient was calculated. The maximum interfractional variation of distances between rectal dose points and the closest source positions was 1.1 cm. The corresponding maximum variability of fractional rectal dose was 65.5%. The percentage difference in cumulative rectal dose estimation for each patient was 5.4%, 19.6%, 34.6%, 23.4%, and 13.9%, respectively. In conclusion, care should be taken when using rectal markers as reference points for estimating rectal dose in HDR cervical brachytherapy. The best estimate of true rectal dose for each fraction should be determined by the most anterior point among all fractions.

Occupational radiation dose in Indonesia 1981-1986

International Nuclear Information System (INIS)

Hiswara, E.; Ismono, A.

1993-01-01

Occupational radiation dose in Indonesia 1981-1986. This paper presents the occupational radiation dose in Indonesia during the period of 1981-1986. The highest collective dose accurated in 1983 was calculated to be 2.68 man-Sv, with the maximum mean dose per worker, who received dose more than zero, was around 11.07 mSv in the same year. In 1985, a relative collective dose from medical occupations of 1.88 man mSv for 10 6 population was estimated based on its total collective dose of 0.31 man-mSv. The total number of workers who received annual collective dose less than 5 mSv varied from 97.0% in 1981 to 99.5% in 1986. As a group, the industrial occupations has considerably higher risk in receiving a dose than others. (authors). 11 refs., 7 tabs

Production and electrical parameters of La /SUB 1-x/ Ca /SUB x/ Cr /SUB 1-y/ Ni /SUB y/ O3 (x ranging from 0-0.3; y ranging from 0-1)

International Nuclear Information System (INIS)

Kononyuk, I.F.; Surmach, N.G.; Tolochko, S.P.

1986-01-01

This paper deals with the conditions for the formation of LaCr /SUB 1-y/ Ni /SUB y/ O 3 , La /SUB 1-x/ Ca /SUB x/ CrO 3 , and La /SUB 1-x/ Ca /SUB x/ Cr /SUB 1-y/ Ni /SUB y/ O 3 solid solutions and the electrical parameters of these. The initial materials were lanthanum, calcium, nickel, and chromium nitrates of pure or analytical grade. It is shown that partial replacement of lanthanum by calcium does not have any substantial effect on the electrical parameters of La /SUB 1-x/ Ca /SUB x/ Cr /SUB 1-y/ Ni /SUB y/ O 3 solid solutions for y = 0.2-0.6, but it increases the conductivity of La /SUB 1-x/ Ca /SUB x/ CrO 3 by three orders of magnitude as x varies from 0 to 0.3. The electrical parameters are virtually the same for lanthanum chromites containing calcium and strontium. The solubility of calcium in lanthanum chromite is reduced in the presence of nickel

Georgia fishery study: implications for dose calculations

International Nuclear Information System (INIS)

Turcotte, M.D.S.

1983-01-01

Fish consumption will contribute a major portion of the estimated individual and population doses from L-Reactor liquid releases and Cs-137 remobilization in Steel Creek. It is therefore important that the values for fish consumption used in dose calculations be as realistic as possible. Since publication of the L-Reactor Environmental Information Document (EID), data have become available on sport fishing in the Savannah River. These data provide SRP with site-specific sport fish harvest and consumption values for use in dose calculations. The Georgia fishery data support the total population fish consumption and calculated dose reported in the EID. The data indicate, however, that both the EID average and maximum individual fish consumption have been underestimated, although each to a different degree. The average fish consumption value used in the EID is approximately 3% below the lower limit of the fish consumption range calculated using the Georgia data. A fish consumption value of 11.3 kg/yr should be used to recalculate dose to the average individual from L-Reactor restart. Maximum fish consumption in the EID has been underestimated by approximately 60%, and doses to the maximum individual should also be recalculated. Future dose calculations should utilize an average fish consumption value of 11.3 kg/yr, and a maximum fish consumption value of 34 kg/yr

The elementary discussion of volumetric modulated arc therapy using the orthogonal plane dose verification

International Nuclear Information System (INIS)

Shi Jinping; Chen Lixin; Xie Qiuying; Zhang Liwen; Teng Jianjian

2012-01-01

Objective: This study was to explore the feasibility of using the orthogonal plane dose formed by the coronal and sagittal plane to verify the volumetric modulated arc therapy (VMAT) plan. Methods: The VMAT plans of 12 patients were included in this study. The orthogonal plane dose formed by the coronal and sagittal plane were measured based on the combination of 2D ionization chamber array and multicube phantom, and the point dose were measured based on a multiple hole cylindrical phantom attached with two 0.125 cm 3 ionization chamber probes. Results: In the measurement of the point dose, the average error was 1.5% in high dose area (more than 80% of maximum), and 1.7% in low dose area (less than 80% of maximum), respectively. The discrepancy of point dose measurement was 1.3% between the 2D ionization chamber array and the VMAT planning system. In the measurement of the orthogonal plane dose, the pass rate of γ were 93.7% for 2%/2 mm and 97.2% for 3%/3 mm. Conclusion: It is reliable for using the orthogonal plane dose formed by the coronal and sagittal plane to verify the VMAT plan. (authors)

Dose assessment from potential radionuclide emissions from stacks on the Hanford Site

International Nuclear Information System (INIS)

Davis, W.E.; Barnett, J.M.

1995-04-01

On February 3, 1993, the US Department of Energy, Richland Operations Office (RL), received a Compliance Order and Information Request from the Director of the Air and Toxics Division of the US Environmental Protection Agency (EPA), Region 10. The Compliance Order required RL to (1) evaluate all radionuclide emission points at the Hanford Site to determine which points are subject to the continuous emission sampling requirements of Title 40, Code of Federal Regulations, Part 61 (40 CFR 61), Subpart H, and (2) continuously sample radionuclide emissions in accordance with requirements in 40 CFR 61.93. The Information Request required RL to provide a written Compliance Plan to meet the requirements of the Compliance Order. A Compliance Plan was submitted to EPA, Region 10, on April 30, 1993. The Compliance Plan specified that a dose assessment would be performed for 84 Westinghouse Hanford Company (WHC) stacks registered with the Washington State Department of Health on the Hanford Site. Any stack identified in the assessment as having potential emissions to cause an effective dose equivalent (EDE) to a maximum exposed individual (MEI) greater than 0.1 mrem y -1 must have a compliant sampling system. In addition, a Federal Facility Compliance Agreement (FFCA) was signed on. February 7, 1994. The FFCA required that all unregistered stacks on the Hanford Site be assessed. This requirement increased the number of stacks to be assessed to 123 stacks. Six methods for performing the assessments are described. An initial assessment using only the HEPA filtration factor for back calculations identified 32 stacks that would have emissions which would cause an EDE to the MEI greater than 0.1 mrem y -1 . When the other methods were applied the number was reduced to 20 stacks. The paper discusses reasons for these overestimates

Dose linearity and monitor unit stability of a G4 type cyberknife robotic stereotactic radiosurgery system

International Nuclear Information System (INIS)

Sudahar, H.; Kurup, P.G.G.; Murali, V.; Velmurugan, J.

2012-01-01

Dose linearity studies on conventional linear accelerators show a linearity error at low monitor units (MUs). The purpose of this study was to establish the dose linearity and MU stability characteristics of a cyberknife (Accuracy Inc., USA) stereotactic radiosurgery system. Measurements were done at a depth of 5 cm in a stereotactic dose verification phantom with a source to surface distance of 75 cm in a Generation 4 (G4) type cyberknife system. All the 12 fixed-type collimators starting from 5 to 60 mm were used for the dose linearity study. The dose linearity was examined in small (1-10), medium (15-100) and large (125-1000) MU ranges. The MU stability test was performed with 60 mm collimator for 10 MU and 20 MU with different combinations. The maximum dose linearity error of -38.8% was observed for 1 MU with 5 mm collimator. Dose linearity error in the small MU range was considerably higher than in the medium and large MU ranges. The maximum error in the medium range was -2.4%. In the large MU range, the linearity error varied between -0.7% and 1.2%. The maximum deviation in the MU stability was -3.03%. (author)

SU-F-T-687: Comparison of SPECT/CT-Based Methodologies for Estimating Lung Dose from Y-90 Radioembolization

Energy Technology Data Exchange (ETDEWEB)

Kost, S; Yu, N [Cleveland Clinic, Cleveland, OH (United States); Lin, S [Cleveland State University, Cleveland, OH (United States)

2016-06-15

Purpose: To compare mean lung dose (MLD) estimates from 99mTc macroaggregated albumin (MAA) SPECT/CT using two published methodologies for patients treated with {sup 90}Y radioembolization for liver cancer. Methods: MLD was estimated retrospectively using two methodologies for 40 patients from SPECT/CT images of 99mTc-MAA administered prior to radioembolization. In these two methods, lung shunt fractions (LSFs) were calculated as the ratio of scanned lung activity to the activity in the entire scan volume or to the sum of activity in the lung and liver respectively. Misregistration of liver activity into the lungs during SPECT acquisition was overcome by excluding lung counts within either 2 or 1.5 cm of the diaphragm apex respectively. Patient lung density was assumed to be 0.3 g/cm{sup 3} or derived from CT densitovolumetry respectively. Results from both approaches were compared to MLD determined by planar scintigraphy (PS). The effect of patient size on the difference between MLD from PS and SPECT/CT was also investigated. Results: Lung density from CT densitovolumetry is not different from the reference density (p = 0.68). The second method resulted in lung dose of an average 1.5 times larger lung dose compared to the first method; however the difference between the means of the two estimates was not significant (p = 0.07). Lung dose from both methods were statistically different from those estimated from 2D PS (p < 0.001). There was no correlation between patient size and the difference between MLD from PS and both SPECT/CT methods (r < 0.22, p > 0.17). Conclusion: There is no statistically significant difference between MLD estimated from the two techniques. Both methods are statistically different from conventional PS, with PS overestimating dose by a factor of three or larger. The difference between lung doses estimated from 2D planar or 3D SPECT/CT is not dependent on patient size.

Determination of the maximum individual dose exposure resulting from a hypothetical LEU plate-melt accident

International Nuclear Information System (INIS)

Abdelhady, Amr

2013-01-01

Highlights: ► Studying the radioactive release results from hypothetical plate-melt accident. ► Hotspot code was used to study the dose distributions around the reactor. ► A 90% decrease in the received dose in proper operation of filtration. ► The received dose is lower than the annual permissible dose after filtration. - Abstract: The objective of this study was to provide an estimate of the potential impact of accidental radioactive release from the testing cell of the Egyptian second research reactor ETRR-2 on the dose level of public around the reactor. The assessment was performed for two cases: an evaluation of the impact that accidental release has on the dose that would be received by public around the reactor in case of proper operation of testing cell filtration system; and an assessment of the potential dose in case of loss of testing cell filtration system. The results show that the filtration system has a great role in decreasing the dose received by an individual located outside the reactor to a dose level lower than the annual permissible dose

Spine stereotactic body radiation therapy plans: Achieving dose coverage, conformity, and dose falloff

International Nuclear Information System (INIS)

Hong, Linda X.; Shankar, Viswanathan; Shen, Jin; Kuo, Hsiang-Chi; Mynampati, Dinesh; Yaparpalvi, Ravindra; Goddard, Lee; Basavatia, Amar; Fox, Jana; Garg, Madhur; Kalnicki, Shalom; Tomé, Wolfgang A.

2015-01-01

We report our experience of establishing planning objectives to achieve dose coverage, conformity, and dose falloff for spine stereotactic body radiation therapy (SBRT) plans. Patients with spine lesions were treated using SBRT in our institution since September 2009. Since September 2011, we established the following planning objectives for our SBRT spine plans in addition to the cord dose constraints: (1) dose coverage—prescription dose (PD) to cover at least 95% planning target volume (PTV) and 90% PD to cover at least 99% PTV; (2) conformity index (CI)—ratio of prescription isodose volume (PIV) to the PTV < 1.2; (3) dose falloff—ratio of 50% PIV to the PTV (R 50% ); (4) and maximum dose in percentage of PD at 2 cm from PTV in any direction (D 2cm ) to follow Radiation Therapy Oncology Group (RTOG) 0915. We have retrospectively reviewed 66 separate spine lesions treated between September 2009 and December 2012 (31 treated before September 2011 [group 1] and 35 treated after [group 2]). The χ 2 test was used to examine the difference in parameters between groups. The PTV V 100% PD ≥ 95% objective was met in 29.0% of group 1 vs 91.4% of group 2 (p < 0.01) plans. The PTV V 90% PD ≥ 99% objective was met in 38.7% of group 1 vs 88.6% of group 2 (p < 0.01) plans. Overall, 4 plans in group 1 had CI > 1.2 vs none in group 2 (p = 0.04). For D 2cm , 48.3% plans yielded a minor violation of the objectives and 16.1% a major violation for group 1, whereas 17.1% exhibited a minor violation and 2.9% a major violation for group 2 (p < 0.01). Spine SBRT plans can be improved on dose coverage, conformity, and dose falloff employing a combination of RTOG spine and lung SBRT protocol planning objectives

Spine stereotactic body radiation therapy plans: Achieving dose coverage, conformity, and dose falloff

Energy Technology Data Exchange (ETDEWEB)

Hong, Linda X., E-mail: lhong0812@gmail.com [Department of Radiation Oncology, Montefiore Medical Center, Bronx, NY (United States); Department of Radiation Oncology, Albert Einstein College of Medicine, Bronx, NY (United States); Shankar, Viswanathan [Department of Epidemiology and Population Health, Albert Einstein College of Medicine, Bronx, NY (United States); Shen, Jin [Department of Radiation Oncology, Montefiore Medical Center, Bronx, NY (United States); Kuo, Hsiang-Chi [Department of Radiation Oncology, Montefiore Medical Center, Bronx, NY (United States); Department of Radiation Oncology, Albert Einstein College of Medicine, Bronx, NY (United States); Mynampati, Dinesh [Department of Radiation Oncology, Montefiore Medical Center, Bronx, NY (United States); Yaparpalvi, Ravindra [Department of Radiation Oncology, Montefiore Medical Center, Bronx, NY (United States); Department of Radiation Oncology, Albert Einstein College of Medicine, Bronx, NY (United States); Goddard, Lee [Department of Radiation Oncology, Montefiore Medical Center, Bronx, NY (United States); Basavatia, Amar; Fox, Jana; Garg, Madhur; Kalnicki, Shalom; Tomé, Wolfgang A. [Department of Radiation Oncology, Montefiore Medical Center, Bronx, NY (United States); Department of Radiation Oncology, Albert Einstein College of Medicine, Bronx, NY (United States)

2015-10-01

We report our experience of establishing planning objectives to achieve dose coverage, conformity, and dose falloff for spine stereotactic body radiation therapy (SBRT) plans. Patients with spine lesions were treated using SBRT in our institution since September 2009. Since September 2011, we established the following planning objectives for our SBRT spine plans in addition to the cord dose constraints: (1) dose coverage—prescription dose (PD) to cover at least 95% planning target volume (PTV) and 90% PD to cover at least 99% PTV; (2) conformity index (CI)—ratio of prescription isodose volume (PIV) to the PTV < 1.2; (3) dose falloff—ratio of 50% PIV to the PTV (R{sub 50%}); (4) and maximum dose in percentage of PD at 2 cm from PTV in any direction (D{sub 2cm}) to follow Radiation Therapy Oncology Group (RTOG) 0915. We have retrospectively reviewed 66 separate spine lesions treated between September 2009 and December 2012 (31 treated before September 2011 [group 1] and 35 treated after [group 2]). The χ{sup 2} test was used to examine the difference in parameters between groups. The PTV V{sub 100%} {sub PD} ≥ 95% objective was met in 29.0% of group 1 vs 91.4% of group 2 (p < 0.01) plans. The PTV V{sub 90%} {sub PD} ≥ 99% objective was met in 38.7% of group 1 vs 88.6% of group 2 (p < 0.01) plans. Overall, 4 plans in group 1 had CI > 1.2 vs none in group 2 (p = 0.04). For D{sub 2cm}, 48.3% plans yielded a minor violation of the objectives and 16.1% a major violation for group 1, whereas 17.1% exhibited a minor violation and 2.9% a major violation for group 2 (p < 0.01). Spine SBRT plans can be improved on dose coverage, conformity, and dose falloff employing a combination of RTOG spine and lung SBRT protocol planning objectives.

Monte Carlo dose characterization of a new 90Sr/90Y source with balloon for intravascular brachytherapy

International Nuclear Information System (INIS)

Wang Ruqing; Li, X. Allen; Lobdell, John

2003-01-01

Beta emitting source wires or seeds have been adopted in clinical practice of intravascular brachytherapy for coronary vessels. Due to the limitation of penetration depth, this type of source is normally not applicable to treat vessels with large diameter, e.g., peripheral vessel. In the effort to extend application of its beta source for peripheral vessels, Novoste has recently developed a new catheter-based system, the Corona trade mark sign 90 Sr/ 90 Y system. It is a source train of 6 cm length and is jacketed by a balloon. The existence of the balloon increases the penetration of the beta particles and maintains the source within a location away from the vessel wall. Using the EGSnrc Monte Carlo system, we have calculated the two-dimensional (2-D) dose rate distribution of the Corona trade mark sign system in water for a balloon diameter of 5 mm. The dose rates on the transverse axis obtained in this study are in good agreement with calibration results of the National Institute of Standards and Technology for the same system for balloon diameters of 5 and 8 mm. Features of the 2-D dose field were studied in detail. The dose parameters based on AAPM TG-60 protocol were derived. For a balloon diameter of 5 mm, the dose rate at the reference point (defined as r 0 =4.5 mm, 2 mm from the balloon surface) is found to be 0.010 28 Gy min -1 mCi -1 . A new formalism for a better characterization of this long source is presented. Calculations were also performed for other balloon diameters. The dosimetry for this source is compared with a 192 Ir source, commonly used for peripheral arteries. In conclusion, we have performed a detailed dosimetric characterization for a new beta source for peripheral vessels. Our study shows that, from dosimetric point of view, the Corona trade mark sign system can be used for the treatment of an artery with a large diameter, e.g., peripheral vessel

Patient radiation doses from neuroradiology procedures

Energy Technology Data Exchange (ETDEWEB)

Garcia-Roman, M J; Abreu-Luis, J; Hernandez-Armas, J [Servicio de Fisica Medica, Hospital Universitario de Canarias, La Laguna, Tenerife (Spain); Prada-Martinez, E [Servicio de Radiodiagnostico, Hospital Universitario de Canarias, La Laguna, Tenerife (Spain)

2001-03-01

Following the presentation of radiation-induced deterministic effects by some patients undergoing neuroradiological procedures during successive sessions, such as temporary epilation, in the 'Hospital Universitario de Canarias', measurements were made of dose to patients. The maximum dose-area product measured by ionization chamber during these procedures was 39617 cGy.cm{sup 2} in a diagnostic of aneurysm and the maximum dose to the skin measured by thermoluminescent dosemeters (TLDs) was 462.53 mGy. This can justify certain deterministic effects but it is unlikely that the patients will suffer serious effects from this skin dose. Also, measurements were made of effective dose about two usual procedures, embolisation of tumour und embolisation of aneurysm. These procedures were reproduced with an anthropomorphic phantom Rando and doses were measured with TLDs. Effective doses obtained were 3.79 mSv and 4.11 mSv, respectively. The effective dose valued by the program EFFDOSE was less than values measured with TLDs. (author)

Patient radiation doses from neuroradiology procedures

International Nuclear Information System (INIS)

Garcia-Roman, M.J.; Abreu-Luis, J.; Hernandez-Armas, J.; Prada-Martinez, E.

2001-01-01

Following the presentation of radiation-induced deterministic effects by some patients undergoing neuroradiological procedures during successive sessions, such as temporary epilation, in the 'Hospital Universitario de Canarias', measurements were made of dose to patients. The maximum dose-area product measured by ionization chamber during these procedures was 39617 cGy.cm 2 in a diagnostic of aneurysm and the maximum dose to the skin measured by thermoluminescent dosemeters (TLDs) was 462.53 mGy. This can justify certain deterministic effects but it is unlikely that the patients will suffer serious effects from this skin dose. Also, measurements were made of effective dose about two usual procedures, embolisation of tumour und embolisation of aneurysm. These procedures were reproduced with an anthropomorphic phantom Rando and doses were measured with TLDs. Effective doses obtained were 3.79 mSv and 4.11 mSv, respectively. The effective dose valued by the program EFFDOSE was less than values measured with TLDs. (author)

Daily radionuclide ingestion and internal radiation doses in Aomori prefecture, Japan.

Science.gov (United States)

Ohtsuka, Yoshihito; Kakiuchi, Hideki; Akata, Naofumi; Takaku, Yuichi; Hisamatsu, Shun'ichi

2013-10-01

To assess internal annual dose in the general public in Aomori Prefecture, Japan, 80 duplicate cooked diet samples, equivalent to the food consumed over a 400-d period by one person, were collected from 100 volunteers in Aomori City and the village of Rokkasho during 2006–2010 and were analyzed for 11 radionuclides. To obtain average rates of ingestion of radionuclides, the volunteers were selected from among office, fisheries, agricultural, and livestock farm workers. Committed effective doses from ingestion of the diet over a 1-y period were calculated from the analytical results and from International Commission on Radiological Protection dose coefficients; for 40K, an internal effective dose rate from the literature was used. Fisheries workers had significantly higher combined internal annual dose than the other workers, possibly because of high rates of ingestion of marine products known to have high 210Po concentrations. The average internal dose rate, weighted by the numbers of households in each worker group in Aomori Prefecture, was estimated at 0.47 mSv y-1. Polonium-210 contributed 49% of this value. The sum of committed effective dose rates for 210Po, 210Pb, 228Ra, and 14C and the effective dose rate of 40K accounted for approximately 99% of the average internal dose rate.

EFECTO DEL 1-METILCICLOPROPENO (1-MCP Y TRATAMIENTO HIDROTÉRMICO SOBRE LA FISIOLOGÍA Y CALIDAD DEL MANGO 'KEITT'

Directory of Open Access Journals (Sweden)

J. A. Osuna-García

2007-01-01

Full Text Available El objetivo del presente trabajo fue evaluar el efecto del 1-MCP (0 y 300 nl·litro-1 y diferentes niveles de tratamiento hidrotérmico (0, 52 °C por 5 min y 46 °C por 110 min sobre la fisiología y calidad de mango 'Keitt'. Se analizó velocidad de respiración, pérdida de peso, firmeza, color de pulpa, sólidos solubles totales y porcentaje de frutos enfermos. Se encontró que la efectividad del 1-MCP varió acorde al nivel de tratamiento hidrotérmico. En frutos sin hidrotérmico el 1-MCP disminuyó velocidad de respiración, no influyó en la pérdida de peso, mantuvo cuatro veces más la firmeza y retrasó el cambio de color de pulpa y el aumento de los sólidos solubles. Sin embargo, bajo tratamiento hidrotérmico por 5 min el 1-MCP incrementó velocidad de respiración, no influyó en la pérdida de peso, mantuvo dos veces más la firmeza de pulpa, retrasó el desarrollo del color de pulpa y mantuvo sin cambios los sólidos solubles. La efectividad del 1-MCP sobre firmeza y pérdida de peso fue significativamente afectada por el tratamiento hidrotérmico de 110 min, y no tuvo ningún efecto sobre el control de enfermedades, sin embargo, el tratamiento con agua caliente por 5 min redujo en más de 50 % la presencia de frutos enfermos. El 1-MCP en combinación con el tratamiento hidrotérmico de 5 min alargó en cinco días la vida de anaquel de los frutos y podría ser una alternativa viable en mercados que no requieren tratamiento hidrotérmico cuarentenario para el control de mosca de la fruta.