TH-E-209-00: Radiation Dose Monitoring and Protocol Management

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-06-15

Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

Real-time electron-beam dose monitoring

International Nuclear Information System (INIS)

McKeown, J.

1995-01-01

A new technique to monitor the integrated dose that a product receives in an irradiation facility is determined by collecting the charge that passes through the product. The technique allows the absorbed dose to be monitored as the irradiation is taking place, i.e. on-line and in real time. The procedure will also provide a means of directly measuring the electron energy, independent of the accelerator control system. The irradiation plant operator can immediately detect a problem of inadequate electron energy and take appropriate action. Examples taken on the IMPELA trademark accelerator at the Iotron Irradiation Facility in Vancouver are presented

Real-time eye lens dose monitoring during cerebral angiography procedures

Energy Technology Data Exchange (ETDEWEB)

Safari, M.J.; Wong, J.H.D.; Kadir, K.A.A.; Ng, K.H. [University of Malaya, Department of Biomedical Imaging, Faculty of Medicine, Kuala Lumpur (Malaysia); University of Malaya, University of Malaya Research Imaging Centre (UMRIC), Faculty of Medicine, Kuala Lumpur (Malaysia); Thorpe, N.K.; Cutajar, D.L.; Petasecca, M.; Lerch, M.L.F.; Rosenfeld, A.B. [University of Wollongong, Centre for Medical Radiation Physics (CMRP), Wollongong, NSW (Australia)

2016-01-15

To develop a real-time dose-monitoring system to measure the patient's eye lens dose during neuro-interventional procedures. Radiation dose received at left outer canthus (LOC) and left eyelid (LE) were measured using Metal-Oxide-Semiconductor Field-Effect Transistor dosimeters on 35 patients who underwent diagnostic or cerebral embolization procedures. The radiation dose received at the LOC region was significantly higher than the dose received by the LE. The maximum eye lens dose of 1492 mGy was measured at LOC region for an AVM case, followed by 907 mGy for an aneurysm case and 665 mGy for a diagnostic angiography procedure. Strong correlations (shown as R{sup 2}) were observed between kerma-area-product and measured eye doses (LOC: 0.78, LE: 0.68). Lateral and frontal air-kerma showed strong correlations with measured dose at LOC (AK{sub L}: 0.93, AK{sub F}: 0.78) and a weak correlation with measured dose at LE. A moderate correlation was observed between fluoroscopic time and dose measured at LE and LOC regions. The MOSkin dose-monitoring system represents a new tool enabling real-time monitoring of eye lens dose during neuro-interventional procedures. This system can provide interventionalists with information needed to adjust the clinical procedure to control the patient's dose. (orig.)

Real-time eye lens dose monitoring during cerebral angiography procedures

International Nuclear Information System (INIS)

Safari, M.J.; Wong, J.H.D.; Kadir, K.A.A.; Ng, K.H.; Thorpe, N.K.; Cutajar, D.L.; Petasecca, M.; Lerch, M.L.F.; Rosenfeld, A.B.

2016-01-01

To develop a real-time dose-monitoring system to measure the patient's eye lens dose during neuro-interventional procedures. Radiation dose received at left outer canthus (LOC) and left eyelid (LE) were measured using Metal-Oxide-Semiconductor Field-Effect Transistor dosimeters on 35 patients who underwent diagnostic or cerebral embolization procedures. The radiation dose received at the LOC region was significantly higher than the dose received by the LE. The maximum eye lens dose of 1492 mGy was measured at LOC region for an AVM case, followed by 907 mGy for an aneurysm case and 665 mGy for a diagnostic angiography procedure. Strong correlations (shown as R 2 ) were observed between kerma-area-product and measured eye doses (LOC: 0.78, LE: 0.68). Lateral and frontal air-kerma showed strong correlations with measured dose at LOC (AK L : 0.93, AK F : 0.78) and a weak correlation with measured dose at LE. A moderate correlation was observed between fluoroscopic time and dose measured at LE and LOC regions. The MOSkin dose-monitoring system represents a new tool enabling real-time monitoring of eye lens dose during neuro-interventional procedures. This system can provide interventionalists with information needed to adjust the clinical procedure to control the patient's dose. (orig.)

[Evaluation of an Experimental Production Wireless Dose Monitoring System for Radiation Exposure Management of Medical Staff].

Science.gov (United States)

Fujibuchi, Toshioh; Murazaki, Hiroo; Kuramoto, Taku; Umedzu, Yoshiyuki; Ishigaki, Yung

2015-08-01

Because of the more advanced and more complex procedures in interventional radiology, longer treatment times have become necessary. Therefore, it is important to determine the exposure doses received by operators and patients. The aim of our study was to evaluate an experimental production wireless dose monitoring system for pulse radiation in diagnostic X-ray. The energy, dose rate, and pulse fluoroscopy dependence were evaluated as the basic characteristics of this system for diagnostic X-ray using a fully digital fluoroscopy system. The error of 1 cm dose equivalent rate was less than 15% from 35.1 keV to 43.2 keV with energy correction using metal filter. It was possible to accurately measure the dose rate dependence of this system, which was highly linear until 100 μSv/h. This system showed a constant response to the pulse fluoroscopy. This system will become useful wireless dosimeter for the individual exposure management by improving the high dose rate and the energy characteristics.

A dose-per-pulse monitor for a dual-mode medical accelerator

International Nuclear Information System (INIS)

Galbraith, D.M.; Martell, E.S.; Fueurstake, T.; Norrlinger, B.; Schwendener, H.; Rawlinson, J.A.

1990-01-01

On a radiotherapy accelerator, the dose monitoring system is the last level of protection between the patient and the extremely high dose rate which all accelerators are capable of producing. The risk of losing this level of protection is substantially reduced if two or more dose monitoring systems are used which are mechanically and electrically independent in design. This paper describes the installation of an independent radiation monitor in a dual-mode, computer-controlled accelerator with a moveable monitor chamber. The added device is fixed in the beam path, is capable of monitoring each beam pulse, and is capable of terminating irradiation within the pulse repetition period if any measured pulse is unacceptably high

TH-E-209-02: Dose Monitoring and Protocol Optimization: The Pediatric Perspective

International Nuclear Information System (INIS)

MacDougall, R.

2016-01-01

Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

TH-E-209-02: Dose Monitoring and Protocol Optimization: The Pediatric Perspective

Energy Technology Data Exchange (ETDEWEB)

MacDougall, R. [Boston Children’s Hospital (United States)

2016-06-15

Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

Required accuracy and dose thresholds in individual monitoring

DEFF Research Database (Denmark)

Christensen, P.; Griffith, R.V.

1994-01-01

this uncertainty factor, a value of 21% can be evaluated for the allowable maximum overall standard deviation for dose measurements at dose levels near the annual dose limits increasing to 45% for dose levels at the lower end of the dose range required to be monitored. A method is described for evaluating...... the overall standard deviation of the dosimetry system by combining random and systematic uncertainties in quadrature, and procedures are also given for determining each individual uncertainty connected to the dose measurement. In particular, attention is paid to the evaluation of the combined uncertainty due...... to energy and angular dependencies of the dosemeter. In type testing of personal dosimetry systems, the estimated overall standard deviation of the dosimetry system is the main parameter to be tested. An important characteristic of a personal dosimetry system is its capability of measuring low doses...

Dose monitoring in nuclear emergency

International Nuclear Information System (INIS)

Nan Hongjie; Yang Zhongping; Lei Xin

2012-01-01

In order to protect people from irradiation sickness and rebuild the radiation filed in nuclear emergency, personal and environmental dose need to be monitored. The application of TLD in dose monitoring is discussed in this paper. (authors)

A real-time stack radioactivity monitoring system and dose projection program

Energy Technology Data Exchange (ETDEWEB)

Hull, A.P.; Michael, P.A. [Brookhaven National Laboratory, Upton, NY (United States); Bernstein, H.J. [Bernstein & Sons, Bellport, NY (United States)

1995-02-01

At Brookhaven National Laboratory, a commercial Low- and High-Range Air Effluent Monitor has become operational at the 60 Mw (t) High Flux Beam Reactor. Its output data is combined with that from ground-level and elevated meteorological sensors to provide a real-time projection of the down-wind dose rates from noble gases and radioiodines released from the HFBR`s 100 m stack. The output of the monitor, and the meteorological sensors and the dose projections can be viewed at emergency response terminals located in the Reactor Control Room, its Technical Support Center and at the laboratory`s separately located Meteorological Station and Monitoring and Assessment Center.

Dose and dose rate monitor

International Nuclear Information System (INIS)

Novakova, O.; Ryba, J.; Slezak, V.; Svobodova, B.; Viererbl, L.

1984-10-01

The methods are discussea of measuring dose rate or dose using a scintillation counte. A plastic scintillator based on polystyrene with PBD and POPOP activators and coated with ZnS(Ag) was chosen for the projected monitor. The scintillators were cylindrical and spherical in shape and of different sizes; black polypropylene tubes were chosen as the best case for the probs. For the counter with different plastic scintillators, the statistical error 2σ for natural background was determined. For determining the suitable thickness of the ZnS(Ag) layer the energy dependence of the counter was measured. Radioisotopes 137 Cs, 241 Am and 109 Cd were chosen as radiation sources. The best suited ZnS(Ag) thickness was found to be 0.5 μm. Experiments were carried out to determine the directional dependence of the detector response and the signal to noise ratio. The temperature dependence of the detector response and its compensation were studied, as were the time stability and fatigue manifestations of the photomultiplier. The design of a laboratory prototype of a dose rate and dose monitor is described. Block diagrams are given of the various functional parts of the instrument. The designed instrument is easiiy portable, battery powered, measures dose rates from natural background in the range of five orders, i.e., 10 -2 to 10 3 nGy/s, and allows to determine a dose of up to 10 mGy. Accouracy of measurement in the energy range of 50 keV to 1 MeV is better than +-20%. (E.S.)

The software and hardware design of a 16 channel online dose rate monitoring system

International Nuclear Information System (INIS)

Tang Wenjuan; Yan Yonghong; Yang Shiming; Li Xiaonan; Min Jian

2011-01-01

The software and hardware design of a 16 channel online dose rate monitoring system is presented. After being amplified and A/D converted, the output signal of the sensors was sent to a microprocessor through an FPGA, where the low-frequency filter, calculation, temperature compensation and pedestal deduction were accomplished. Such steps corrected the variation of dark current dependent on temperature fluctuations in a effective way, and finally the instantaneous dose rate results with enough precise were obtained. (authors)

Development of miniature γ dose rate monitor with high sensitivity

International Nuclear Information System (INIS)

Shi Huilu; Tuo Xianguo; Xi Dashun; Tang Rong; Mu Keliang; Yang Jianbo

2009-01-01

This paper introduces a miniature γ dose rate monitor with high sensitivity which design based on single chip microcomputer, it can continue monitoring γ dose rate and then choose wire or wireless communications to sent the monitoring data to host according to the actual conditions. It has two kinds of power supply system, AC power supply system and battery which can be chose by concrete circumstances. The design idea and implementation technology of hardware and software and the system structure of the monitor are detailed illustrated in this paper. The experimental results show that measurable range is 0.1 mR/h-200 mR/h, the sensitivity of γ is 90 cps/mR/h, dead time below 200 us, error of stability below ±10%. (authors)

TH-E-209-03: Development of An In-House CT Dose Monitoring and Management System Based On Open-Source Software Resources -- Pearls and Pitfalls

International Nuclear Information System (INIS)

Zhang, D.

2016-01-01

Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

TH-E-209-03: Development of An In-House CT Dose Monitoring and Management System Based On Open-Source Software Resources -- Pearls and Pitfalls

Energy Technology Data Exchange (ETDEWEB)

Zhang, D. [Beth Israel Deaconess Medical Center (Israel)

2016-06-15

Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

Monitoring and Analysis of Environmental Gamma Dose Rate around Serpong Nuclear Complex

Directory of Open Access Journals (Sweden)

I.P. Susila

2017-08-01

Full Text Available An environmental radiation monitoring system that continuously measures gamma dose rate around nuclear facilities is an important tool to present dose rate information to the public or authorities for radiological protection during both normal operation and radiological accidents. We have developed such a system that consists of six GM-based device for monitoring the environmental dose rate around Serpong Nuclear Complex. It has operated since 2010. In this study, a description of the system and analysis of measured data are presented. Analysis of the data for the last five years shows that the average dose rate levels were between 84-99 nSv/h which are still lower than terrestrial gamma radiation levels at several other locations in Indonesia. Time series analysis of the monitoring data demonstrates a good agreement between an increase in environmental gamma dose rate and the presence of iodine and argon in the air by in situ measurement. This result indicates that system is also effective for an early warning system in the case of radiological emergency.

Evaluation of personal dose equivalent 'HP(d)' in a external individual monitoring system for X and gamma radiation

International Nuclear Information System (INIS)

Santoro, C.; Antonio Filho, J.; Santos, M.A.P.

2007-01-01

The good of individual monitoring for external radiation is the assessment of occupational exposure from X and γ radiations in order to assure that the radiological conditions of the workplace are acceptable, safe and satisfactory. The evaluation of radiations doses for workers must not exceed dose limits specified for workers, according to national regulatory agencies. Nowadays, there are two external monitoring systems in use, both based on ICRU definitions. In the conventional system, the workers doses are evaluated in terms of Hx. The personal dosimeter is worn over chest surface and it is calibrated in function of air kerma. In the new system, the workers doses are evaluated in terms of HP(d) and the personal dosimeter is calibrated in function of phantom doses. The aim of this paper is to adapt an external dosimetry laboratory (based on photographic dosimetry) to evaluate the personal dosimeters in terms of HP(d). In this way, a simple methodology, based on linear programming, was utilized. In this adaptation, calibration curves were obtained for radiation qualities (W and N series) described by International Organization for Standardization (ISO 4037-1, 1995). These calibration curves offer a better accuracy on dose determinations and energy below 140 keV, improving the quality of service rendered the society. (author)

A review of radiology staff doses and dose monitoring requirements

International Nuclear Information System (INIS)

Martin, C. J.

2009-01-01

Studies of radiation doses received during X-ray procedures by radiology, cardiology and other clinical staff have been reviewed. Data for effective dose (E), and doses to the eyes, thyroid, hands and legs have been analysed. These data have been supplemented with local measurements to determine the most exposed part of the hand for monitoring purposes. There are ranges of 60-100 in doses to individual tissues reported in the literature for similar procedures at different centres. While ranges in the doses per unit dose-area product (DAP) are between 10 and 25, large variations in dose result from differences in the sensitivity of the X-ray equipment, the type of procedure and the operator technique, but protection factors are important in maintaining dose levels as low as possible. The influence of shielding devices is significant for determining the dose to the eyes and thyroid, and the position of the operator, which depends on the procedure, is the most significant factor determining doses to the hands. A second body dosemeter worn at the level of the collar is recommended for operators with high workloads for use in assessment of effective dose and the dose to the eye. It is proposed that the third quartile values from the distributions of dose per unit DAP identified in the review might be employed in predicting the orders of magnitude of doses to the eye, thyroid and hands, based on interventional operator workloads. Such dose estimates could be employed in risk assessments when reviewing protection and monitoring requirements. A dosemeter worn on the little finger of the hand nearest to the X-ray tube is recommended for monitoring the hand. (authors)

The development of wireless radiation dose monitoring using smart phone

Energy Technology Data Exchange (ETDEWEB)

Lee, Jin Woo; Jeong, Gyo Seong; Lee, Yun Jong [Advanced Radiation Technology Institute, Korea Atomic Energy Research Institute, Jeongeup (Korea, Republic of); Kim, Chong Yeal [Chonbuk National University, Jeonju (Korea, Republic of); Lim, Chai Wan [REMTECH, Seoul (Korea, Republic of)

2016-11-15

Radiation workers at a nuclear facility or radiation working area should hold personal dosimeters. some types of dosimeters have functions to generate audible or visible alarms to radiation workers. However, such devices used in radiation fields these days have no functions to communicate with other equipment or the responsible personnel. our project aims at the development of a remote wireless radiation dose monitoring system that can be utilized to monitor the radiation dose for radiation workers and to notify the radiation protection manager of the dose information in real time. We use a commercial survey meter for personal radiation measurement and a smart phone for a mobile wireless communication tool and a Beacon for position detection of radiation workers using Blue tooth communication. In this report, the developed wireless dose monitoring of cellular phone is introduced.

OLDES - an on-line dose evaluation system that can be integrated into the remote monitoring system of nuclear power stations for additional monitoring and prognostic assessment in case of major accidental activity release

International Nuclear Information System (INIS)

Witt, H. de; Brenk, H.D.; Kruschel, K.P.; Knaup, A.G.

1986-01-01

Remote monitoring systems are an inherent part of the environmental surveillance installations of most commercial LWR power plants in the FRG. The systems are designed to cover routine and accident situations. They provide meteorological data, gross effluent dose rates, and dose measurements at approximately 25 locations in the vicinity of the plant in time steps of 10 minutes. Based on such a network, an attempt has been made to develop an on-line dose evaluation system (OLDES) as a tool to aid decision making processes in case of major accidental releases. On-line, here means that the software package directly includes the measurements at the monitoring stations in order to adjust the dose computations to the measurements in time steps of 10 minutes. In this way the system yields the best possible bases, both for actual diagnosis of radiation exposure, and for dose projections. The software package uses a Gaussian puff trajectory model to simulate atmospheric dispersion and deposition of radionuclides. It includes 'cloud- and ground-shine irradiation' and allows for changing weather conditions without exceeding the limits of real time calculation. Preliminary tests of the software package revealed reasonable semioperational performance. (orig.)

Routine monitoring of eye dose; and reply

Energy Technology Data Exchange (ETDEWEB)

Palmer, K; Jeans, S P; Faulkner, K; Bardsley, R A; Love, H G

1985-12-01

This letter briefly reports the assessment at Papworth Hospital of the feasibility of monitoring eye doses of staff using a film badge worn on the shoulder in addition to the badge worn under the lead apron. For three consecutive months hand and eye (forehead) dose were monitored using TLDs, while shoulder and body dose, recorded under the lead apron, were measured with film badges. For the four doctors monitored, (two radiologists and two cardiologists) the shoulder badge somewhat overestimated the eye dose. In the case of nurses, the dose recorded by the shoulder badge was of a similar order to the TLD-recorded eye dose. The reply from the Christie Hospital at Manchester comments on the use of the shoulder badge and contends that the use of forehead dosemeters to measure eye dose is to be preferred whenever possible.

Dose record keeping: a multi purpose tool in individual monitoring

International Nuclear Information System (INIS)

Bermann, F.; Julius, H.W.

1993-01-01

Proper recording of radiation doses is an essential part of the process of individual monitoring and shares in the same objective. A dose record keeping system is more than just a computer based data storage system and should rather be a Dose Registration and Information System (DRIS). Objectives of dose record keeping are given. As a result of the integration of member states of the European Communities, co-operation and exchange of personnel between countries will be increasing. This will probably require national dose registration systems and adequate data communication between them. These developments emphasize the necessity for international harmonization of dose record keeping systems and categorization of the data they contain. General characteristics and specific aspects of dose record keeping systems will be dealt with. Attention will also be given to some special applications of the recorded information, such as: the use of data for epidemiological studies and for QA purposes. (authors). 5 tabs., 4 refs

Monitoring and dose recording for the individual

International Nuclear Information System (INIS)

1988-01-01

This document specifies the conditions under which monitoring of individuals is required. For workers identified as Atomic Radiation Workers, determination of dose or exposure must be made. In circumstances where personal monitoring techniques are impractical, doses and exposures may be estimated by non-personal monitoring techniques. For workers not identified as Atomic Radiation Workers, licensees must be able to demonstrate that there is no reasonable potential for accumulating radiation doses or exposures in excess of regulatory limits. (L.L.)

Development of autonomous gamma dose logger for environmental monitoring.

Science.gov (United States)

Jisha, N V; Krishnakumar, D N; Surya Prakash, G; Kumari, Anju; Baskaran, R; Venkatraman, B

2012-03-01

Continuous monitoring and archiving of background radiation levels in and around the nuclear installation is essential and the data would be of immense use during analysis of any untoward incidents. A portable Geiger Muller detector based autonomous gamma dose logger (AGDL) for environmental monitoring is indigenously designed and developed. The system operations are controlled by microcontroller (AT89S52) and the main features of the system are software data acquisition, real time LCD display of radiation level, data archiving at removable compact flash card. The complete system operates on 12 V battery backed up by solar panel and hence the system is totally portable and ideal for field use. The system has been calibrated with Co-60 source (8.1 MBq) at various source-detector distances. The system is field tested and performance evaluation is carried out. This paper covers the design considerations of the hardware, software architecture of the system along with details of the front-end operation of the autonomous gamma dose logger and the data file formats. The data gathered during field testing and inter comparison with GammaTRACER are also presented in the paper. AGDL has shown excellent correlation with energy fluence monitor tuned to identify (41)Ar, proving its utility for real-time plume tracking and source term estimation.

Monitoring of individual doses and its information management system for CAEP's employees

International Nuclear Information System (INIS)

Wei Xiye; Lei Jiarong; Yuan Yonggang; Zhao Lin; Zhao Minzhi; Cui Gaoxian

2007-01-01

Employees' individual dose is very important to radiation workers, this paper introduces the monitoring of individual doses for the employees of CAEP in brief. A mass of employees' individual dose information records needed for being disposed, the data management software IDDMS for individual dose was developed. This paper describes the database structure, main modules, statistic and printing functions in this program. Based on much experience of many years in data management of individual dose, this program is developed using the object-oriented language Visual Foxpro 6.0. Meanwhile, it had been tested for several months. The results show that this software can be used directly for daily management of individual dose, and report forms of individual dose can also be printed easily for the related superior department. (authors)

Real-Time Patient and Staff Radiation Dose Monitoring in IR Practice

Energy Technology Data Exchange (ETDEWEB)

Sailer, Anna M., E-mail: karmanna@stanford.edu; Paulis, Leonie, E-mail: leonie.paulis@mumc.nl; Vergoossen, Laura; Kovac, Axel O., E-mail: axel.kovac@mumc.nl; Wijnhoven, Geert, E-mail: g.wijnhoven@mumc.nl [Maastricht University Medical Centre, Department of Radiology (Netherlands); Schurink, Geert Willem H., E-mail: gwh.schurink@mumc.nl; Mees, Barend, E-mail: barend.mees@mumc.nl [Maastricht University Medical Centre, Department of Vascular Surgery (Netherlands); Das, Marco, E-mail: m.das@mumc.nl; Wildberger, Joachim E., E-mail: j.wildberger@mumc.nl; Haan, Michiel W. de, E-mail: m.de.haan@mumc.nl; Jeukens, Cécile R. L. P. N., E-mail: cecile.jeukens@mumc.nl [Maastricht University Medical Centre, Department of Radiology (Netherlands)

2017-03-15

PurposeKnowledge of medical radiation exposure permits application of radiation protection principles. In our center, the first dedicated real-time, automated patient and staff dose monitoring system (DoseWise Portal, Philips Healthcare) was installed. Aim of this study was to obtain insight in the procedural and occupational doses.Materials and MethodsAll interventional radiologists, vascular surgeons, and technicians wore personal dose meters (PDMs, DoseAware, Philips Healthcare). The dose monitoring system simultaneously registered for each procedure dose-related data as the dose area product (DAP) and effective staff dose (E) from PDMs. Use and type of shielding were recorded separately. All procedures were analyzed according to procedure type; these included among others cerebral interventions (n = 112), iliac and/or caval venous recanalization procedures (n = 68), endovascular aortic repair procedures (n = 63), biliary duct interventions (n = 58), and percutaneous gastrostomy procedure (n = 28).ResultsMedian (±IQR) DAP doses ranged from 2.0 (0.8–3.1) (percutaneous gastrostomy) to 84 (53–147) Gy cm{sup 2} (aortic repair procedures). Median (±IQR) first operator doses ranged from 1.6 (1.1–5.0) μSv to 33.4 (12.1–125.0) for these procedures, respectively. The relative exposure, determined as first operator dose normalized to procedural DAP, ranged from 1.9 in biliary interventions to 0.1 μSv/Gy cm{sup 2} in cerebral interventions, indicating large variation in staff dose per unit DAP among the procedure types.ConclusionReal-time dose monitoring was able to identify the types of interventions with either an absolute or relatively high staff dose, and may allow for specific optimization of radiation protection.

TH-E-209-01: Fluoroscopic Dose Monitoring and Patient Follow-Up Program at Massachusetts General Hospital

International Nuclear Information System (INIS)

Liu, B.

2016-01-01

Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

TH-E-209-01: Fluoroscopic Dose Monitoring and Patient Follow-Up Program at Massachusetts General Hospital

Energy Technology Data Exchange (ETDEWEB)

Liu, B. [Massachusetts General Hospital (United States)

2016-06-15

Radiation dose monitoring solutions have opened up new opportunities for medical physicists to be more involved in modern clinical radiology practices. In particular, with the help of comprehensive radiation dose data, data-driven protocol management and informed case follow up are now feasible. Significant challenges remain however and the problems faced by medical physicists are highly heterogeneous. Imaging systems from multiple vendors and a wide range of vintages co-exist in the same department and employ data communication protocols that are not fully standardized or implemented making harmonization complex. Many different solutions for radiation dose monitoring have been implemented by imaging facilities over the past few years. Such systems are based on commercial software, home-grown IT solutions, manual PACS data dumping, etc., and diverse pathways can be used to bring the data to impact clinical practice. The speakers will share their experiences with creating or tailoring radiation dose monitoring/management systems and procedures over the past few years, which vary significantly in design and scope. Topics to cover: (1) fluoroscopic dose monitoring and high radiation event handling from a large academic hospital; (2) dose monitoring and protocol optimization in pediatric radiology; and (3) development of a home-grown IT solution and dose data analysis framework. Learning Objectives: Describe the scope and range of radiation dose monitoring and protocol management in a modern radiology practice Review examples of data available from a variety of systems and how it managed and conveyed. Reflect on the role of the physicist in radiation dose awareness.

Individual external monitoring system for gamma and X ray evaluation of the individual dose equivalent 'HP(10)', utilizing a photographic dosimetry technique

International Nuclear Information System (INIS)

Santoro, Christiana; Filho, Joao Antonio

2008-01-01

Full text: Individual monitoring evaluates external sources of ionizing radiation X, γ, β and n, to which workers are occupationally exposed, for ensuring safe and acceptable radiological conditions in their places of employment. The dose received by workers should attend the limits authorized by national regulatory organs. Nowadays, there are two radiometric unit systems, based on resolutions of the National Nuclear Energy Commission (NNEC) and the International Commission on Radiation Units and Measurements (ICRU); in the conventional (NNEC) system, the doses received by workers are evaluated through the individual dose H x , where dosemeters used on surface of thorax are calibrated in terms of air kerma; in the recent system (ICRU), the doses are evaluated through the individual dose equivalent H P (d), where dosemeters are calibrated in terms of dose from phantom. The recent system improves the method of evaluation, by taking into account the scattering effect and absorption of radiation in the human body. This work adapts a photographic dosimetry service to the recent ICRU publications, for evaluation of individual monitoring, in function of the individual dose equivalent H P (10) of strong penetrating radiation. For this, a methodology based on linear programming and determination of calibration curves is used for radiation capacities, wide (W) and narrow (N) spectra, as described by the International Organization for Standardization (ISO 4037-1, 1995). These calibration curves offer better accuracy in the determination of doses and energy, which will improve the quality of the service given to society. The results show that the values of individual dose equivalent, evaluated at intervals of 0.2 to 200 mSv, have lower significant uncertainties (10%) than those recommended by the ICRP 75, for individual monitoring; therefore, the evaluation system for developed doses attends the new recommendations proposed by International Commissions. From what has been

Computerized clinical decision support systems for therapeutic drug monitoring and dosing: A decision-maker-researcher partnership systematic review

Directory of Open Access Journals (Sweden)

Weise-Kelly Lorraine

2011-08-01

Full Text Available Abstract Background Some drugs have a narrow therapeutic range and require monitoring and dose adjustments to optimize their efficacy and safety. Computerized clinical decision support systems (CCDSSs may improve the net benefit of these drugs. The objective of this review was to determine if CCDSSs improve processes of care or patient outcomes for therapeutic drug monitoring and dosing. Methods We conducted a decision-maker-researcher partnership systematic review. Studies from our previous review were included, and new studies were sought until January 2010 in MEDLINE, EMBASE, Evidence-Based Medicine Reviews, and Inspec databases. Randomized controlled trials assessing the effect of a CCDSS on process of care or patient outcomes were selected by pairs of independent reviewers. A study was considered to have a positive effect (i.e., CCDSS showed improvement if at least 50% of the relevant study outcomes were statistically significantly positive. Results Thirty-three randomized controlled trials were identified, assessing the effect of a CCDSS on management of vitamin K antagonists (14, insulin (6, theophylline/aminophylline (4, aminoglycosides (3, digoxin (2, lidocaine (1, or as part of a multifaceted approach (3. Cluster randomization was rarely used (18% and CCDSSs were usually stand-alone systems (76% primarily used by physicians (85%. Overall, 18 of 30 studies (60% showed an improvement in the process of care and 4 of 19 (21% an improvement in patient outcomes. All evaluable studies assessing insulin dosing for glycaemic control showed an improvement. In meta-analysis, CCDSSs for vitamin K antagonist dosing significantly improved time in therapeutic range. Conclusions CCDSSs have potential for improving process of care for therapeutic drug monitoring and dosing, specifically insulin and vitamin K antagonist dosing. However, studies were small and generally of modest quality, and effects on patient outcomes were uncertain, with no convincing

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)

Development of autonomous gamma dose logger for environmental monitoring

Energy Technology Data Exchange (ETDEWEB)

Jisha, N. V.; Krishnakumar, D. N.; Surya Prakash, G.; Kumari, Anju; Baskaran, R.; Venkatraman, B. [Radiological Safety Division, Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, Tamil Nadu (India)

2012-03-15

Continuous monitoring and archiving of background radiation levels in and around the nuclear installation is essential and the data would be of immense use during analysis of any untoward incidents. A portable Geiger Muller detector based autonomous gamma dose logger (AGDL) for environmental monitoring is indigenously designed and developed. The system operations are controlled by microcontroller (AT89S52) and the main features of the system are software data acquisition, real time LCD display of radiation level, data archiving at removable compact flash card. The complete system operates on 12 V battery backed up by solar panel and hence the system is totally portable and ideal for field use. The system has been calibrated with Co-60 source (8.1 MBq) at various source-detector distances. The system is field tested and performance evaluation is carried out. This paper covers the design considerations of the hardware, software architecture of the system along with details of the front-end operation of the autonomous gamma dose logger and the data file formats. The data gathered during field testing and inter comparison with GammaTRACER are also presented in the paper. AGDL has shown excellent correlation with energy fluence monitor tuned to identify {sup 41}Ar, proving its utility for real-time plume tracking and source term estimation.

Automated size-specific CT dose monitoring program: Assessing variability in CT dose

International Nuclear Information System (INIS)

Christianson, Olav; Li Xiang; Frush, Donald; Samei, Ehsan

2012-01-01

Purpose: The potential health risks associated with low levels of ionizing radiation have created a movement in the radiology community to optimize computed tomography (CT) imaging protocols to use the lowest radiation dose possible without compromising the diagnostic usefulness of the images. Despite efforts to use appropriate and consistent radiation doses, studies suggest that a great deal of variability in radiation dose exists both within and between institutions for CT imaging. In this context, the authors have developed an automated size-specific radiation dose monitoring program for CT and used this program to assess variability in size-adjusted effective dose from CT imaging. Methods: The authors radiation dose monitoring program operates on an independent health insurance portability and accountability act compliant dosimetry server. Digital imaging and communication in medicine routing software is used to isolate dose report screen captures and scout images for all incoming CT studies. Effective dose conversion factors (k-factors) are determined based on the protocol and optical character recognition is used to extract the CT dose index and dose-length product. The patient's thickness is obtained by applying an adaptive thresholding algorithm to the scout images and is used to calculate the size-adjusted effective dose (ED adj ). The radiation dose monitoring program was used to collect data on 6351 CT studies from three scanner models (GE Lightspeed Pro 16, GE Lightspeed VCT, and GE Definition CT750 HD) and two institutions over a one-month period and to analyze the variability in ED adj between scanner models and across institutions. Results: No significant difference was found between computer measurements of patient thickness and observer measurements (p= 0.17), and the average difference between the two methods was less than 4%. Applying the size correction resulted in ED adj that differed by up to 44% from effective dose estimates that were not

Environmental radiation monitoring system

International Nuclear Information System (INIS)

Kato, Tsutomu; Shioiri, Masatoshi; Sakamaki, Tsuyoshi

2007-01-01

Environmental radiation monitoring systems are used to measure and monitoring gamma-rays at the observation boundaries of nuclear facilities and in the surrounding areas. In recent years, however, few new nuclear facilities have been constructed and the monitoring systems shift to renewal of existing systems. In addition, in order to increase public acceptance, the facilities are being equipped with communication lines to provide data to prefectural environmental centers. In this text, we introduce the latest technology incorporated in replacement of environmental radiation monitoring systems. We also introduce a replacement method that can shorten the duration during which environmental dose rate measurement is interrupted by enabling both the replacement system and the system being replaced to perform measurements in parallel immediately before and after the replacement. (author)

Real-time measurement and monitoring of absorbed dose for electron beams

Science.gov (United States)

Korenev, Sergey; Korenev, Ivan; Rumega, Stanislav; Grossman, Leon

2004-09-01

The real-time method and system for measurement and monitoring of absorbed dose for industrial and research electron accelerators is considered in the report. The system was created on the basis of beam parameters method. The main concept of this method consists in the measurement of dissipated kinetic energy of electrons in the irradiated product, determination of number of electrons and mass of irradiated product in the same cell by following calculation of absorbed dose in the cell. The manual and automation systems for dose measurements are described. The systems are acceptable for all types of electron accelerators.

Real-time measurement and monitoring of absorbed dose for electron beams

Energy Technology Data Exchange (ETDEWEB)

Korenev, Sergey E-mail: sergey_korenev@steris.com; Korenev, Ivan; Rumega, Stanislav; Grossman, Leon

2004-10-01

The real-time method and system for measurement and monitoring of absorbed dose for industrial and research electron accelerators is considered in the report. The system was created on the basis of beam parameters method. The main concept of this method consists in the measurement of dissipated kinetic energy of electrons in the irradiated product, determination of number of electrons and mass of irradiated product in the same cell by following calculation of absorbed dose in the cell. The manual and automation systems for dose measurements are described. The systems are acceptable for all types of electron accelerators.

Real-time measurement and monitoring of absorbed dose for electron beams

International Nuclear Information System (INIS)

Korenev, Sergey; Korenev, Ivan; Rumega, Stanislav; Grossman, Leon

2004-01-01

The real-time method and system for measurement and monitoring of absorbed dose for industrial and research electron accelerators is considered in the report. The system was created on the basis of beam parameters method. The main concept of this method consists in the measurement of dissipated kinetic energy of electrons in the irradiated product, determination of number of electrons and mass of irradiated product in the same cell by following calculation of absorbed dose in the cell. The manual and automation systems for dose measurements are described. The systems are acceptable for all types of electron accelerators

Estimation of inhalation doses from airborne releases using gross monitors

International Nuclear Information System (INIS)

Goldstein, N.P.

1978-01-01

Monitoring programs at most nuclear facilities involve continuous gross measurements supplemented by periodic isotopic analyses of release samples. The isotopic measurements are required to accurately assess the potential dose from the various effluent streams, but in between these measurements, one depends on the gross monitors to provide approximate indications of the dose. The effluent streams release a variety of nuclides, each with its own dose factor. This means that the relationship between the counting rate in a gross monitor and the potential dose of the effluent being monitored will depend on the isotopic composition of this release. If this composition changes, then the dose indicated by the gross monitor (calibrated for the original group of isotopes) may be significantly in error. The problem of indicating inhalation doses from gross monitoring of airborne releases is considered. In order for this type of monitor to accurately indicate dose, regardless of the isotopic makeup of a release, the analysis shows that its response to each isotope should be proportional to the dose factor of that isotope. These ideas are applied to the monitoring of air particulates using gross beta and gross gamma monitors. The study shows that the former more closely satisfies this condition and as a result, satisfactorily indicates the actual dose from reactor effluents, as determined from detailed isotopic data published in the literature. On the other hand, the gross gamma monitor, with its poorer fit to the condition, provided less than satisfactory accuracy in its dose estimates. In addition, a variety of other mathematical response functions were considered but their dose estimation capabilities were not much better than the straight beta response. The study shows that reasonably accurate dose estimates can be made using properly selected gross monitors, but that significant errors can result with improper ones. (author)

Monitoring Effective Doses Received By Air Crews With A Space Weather Application

Science.gov (United States)

Lantos, P.

To fulfil new requirements of the European Community concerning monitoring of effective doses received by air crews, the French Aviation Authority has developed an operational system called Sievert. The SIEVERT system is analysed as an exam- ple of Space Weather application. One of its characteristics is to calculate the dose received on-board each flight on the basis of the specific and detailled flight given by companies. Operational models will be used. As input to the models, the system needs monitoring of galactic cosmic rays and of solar flare particles. The French neu- tron monitors located in Kerguelen Islands (South Indian Ocean) and Terre Adélie (Antarctica) will be used for this purpose. Particular attention will be devoted to evo- lution of the system in conjunction with new measurements available in the frame of a permanent validation process.

Automated size-specific CT dose monitoring program: Assessing variability in CT dose

Energy Technology Data Exchange (ETDEWEB)

Christianson, Olav; Li Xiang; Frush, Donald; Samei, Ehsan [Clinical Imaging Physics Group, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 and Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Clinical Imaging Physics Group, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States) and Carl E. Ravin Advanced Imaging Laboratories, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Clinical Imaging Physics Group, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Carl E. Ravin Advanced Imaging Laboratories, Department of Radiology, Duke University Medical Center, Durham, North Carolina 27705 (United States); Medical Physics Graduate Program, Duke University, Durham, North Carolina 27705 (United States); Department of Physics, Duke University, Durham, North Carolina 27710 (United States); and Department of Biomedical Engineering, Duke University, Durham, North Carolina 27708 (United States)

2012-11-15

Purpose: The potential health risks associated with low levels of ionizing radiation have created a movement in the radiology community to optimize computed tomography (CT) imaging protocols to use the lowest radiation dose possible without compromising the diagnostic usefulness of the images. Despite efforts to use appropriate and consistent radiation doses, studies suggest that a great deal of variability in radiation dose exists both within and between institutions for CT imaging. In this context, the authors have developed an automated size-specific radiation dose monitoring program for CT and used this program to assess variability in size-adjusted effective dose from CT imaging. Methods: The authors radiation dose monitoring program operates on an independent health insurance portability and accountability act compliant dosimetry server. Digital imaging and communication in medicine routing software is used to isolate dose report screen captures and scout images for all incoming CT studies. Effective dose conversion factors (k-factors) are determined based on the protocol and optical character recognition is used to extract the CT dose index and dose-length product. The patient's thickness is obtained by applying an adaptive thresholding algorithm to the scout images and is used to calculate the size-adjusted effective dose (ED{sub adj}). The radiation dose monitoring program was used to collect data on 6351 CT studies from three scanner models (GE Lightspeed Pro 16, GE Lightspeed VCT, and GE Definition CT750 HD) and two institutions over a one-month period and to analyze the variability in ED{sub adj} between scanner models and across institutions. Results: No significant difference was found between computer measurements of patient thickness and observer measurements (p= 0.17), and the average difference between the two methods was less than 4%. Applying the size correction resulted in ED{sub adj} that differed by up to 44% from effective dose

Environmental radiation monitoring system with GPS (global positioning system)

International Nuclear Information System (INIS)

Komoto, Itsuro

2000-01-01

This system combines a radiation monitoring car with GPS and a data processor (personal computer). It distributes the position information acquired through GPS to the data such as measured environmental radiation dose rate and energy spectrum. It also displays and edits the data for each measuring position on a map. Transmitting the data to the power station through mobile phone enables plan managers to easily monitor the environmental radiation dose rate nearby and proper emergency monitoring. (author)

Dose monitoring in radiology departments. Status quo and future perspectives

International Nuclear Information System (INIS)

Boos, J.; Bethge, O.T.; Antoch, G.; Kroepil, P.

2016-01-01

The number of computed tomography examinations has continuously increased over the last decades and accounts for a major part of the collective radiation dose from medical investigations. For purposes of quality assurance in modern radiology a systematic monitoring and analysis of dose related data from radiological examinations is mandatory. Various ways of collecting dose data are available today, for example the Digital Imaging and Communication in Medicine - Structured Report (DICOM-SR), optical character recognition and DICOM-modality performed procedure steps (MPPS). The DICOM-SR is part of the DICOM-standard and provides the DICOM-Radiation Dose Structured Report, which is an easily applicable and comprehensive solution to collect radiation dose parameters. This standard simplifies the process of data collection and enables comprehensive dose monitoring. Various commercial dose monitoring software devices with varying characteristics are available today. In this article, we discuss legal obligations, various ways to monitor dose data, current dose monitoring software solutions and future perspectives in regard to the EU Council Directive 2013/59/EURATOM.

Environmental gamma dose rate monitoring along Mumbai-Pune route using environmental radiation monitor with navigational aid

International Nuclear Information System (INIS)

Padmanabhan, N.; Kale, M.S.; Raman, N.; Krishnamachari, G.; Harikumar, M.; Sharma, D.N.; Mehta, S.K.

1997-01-01

A continuous environmental radiation monitor with navigational aid (ERMNA) for mapping natural gamma radiation background on country wide scale by deployment in railway coaches, has been designed. The system makes use of Indian railway network which is one of the widest network of railways in the world covering nearly complete length and breadth of the country. The system uses an energy compensated (within ± 30%) GN detectors for measurement of environmental dose rate due to natural background, a global positioning system (GPS) for on-line acquisition of positional co-ordinates (longitude and latitude) and an 8085 based data acquisition and processing unit. This system is deployed in guard's cabin of a train. The dose rate data tagged with positional co-ordinates and collected by the system during train journey is down loaded into a Lap Top PC for storage, analysis and graphical representation. The system has been used for background monitoring between Mumbai and Pune. The dose rates recorded over a period of three months ranging from November 1996 to February 1997 along the route show no change in the values which vary from 4 μr/h to 6 μR/h along the route. It drops down to <3 μR/h within tunnels en route. (author)

A unique radiation area monitoring system

International Nuclear Information System (INIS)

Murphy, P.C.; Allen, G.C.

1978-01-01

The Remote Area Monitoring Systems (RAMS) monitors four radiation areas with two independent systems in each area. Each system consists of power supplies, four ionization chambers, and four analog and digital circuits. The first system controls the warning beacons, horns, annunciation panel and interlocks. The second system presents a quantitative dose rate indication at the console and in the radiation area

Continuing education: online monitoring of haemodialysis dose.

Science.gov (United States)

Vartia, Aarne

2018-01-25

Kt/V urea reflects the efficacy of haemodialysis scaled to patient size (urea distribution volume). The guidelines recommend monthly Kt/V measurements based on blood samples. Modern haemodialysis machines are equipped with accessories monitoring the dose online at every session without extra costs, blood samples and computers. To describe the principles, devices, benefits and shortcomings of online monitoring of haemodialysis dose. A critical literature overview and discussion. UV absorbance methods measure Kt/V, ionic dialysance Kt (product of clearance and treatment time; cleared volume without scaling). Both are easy and useful methods, but comparison is difficult due to problems in scaling of the dialysis dose to the patient's size. The best dose estimation method is the one which predicts the quality of life and survival most accurately. There is some evidence on the predictive value of ionic dialysance Kt, but more documentation is required on the UV method. Online monitoring is a useful tool in everyday quality assurance, but blood samples are still required for more accurate kinetic modelling. After reading this article the reader should be able to: Understand the elements of the Kt/V equation for dialysis dose. Compare and contrast different methods of measurement of dialysis dose. Reflect on the importance of adequate dialysis dose for patient survival and life quality. © 2018 European Dialysis and Transplant Nurses Association/European Renal Care Association.

Design of movable fixed area γ dose rate monitor

International Nuclear Information System (INIS)

Li Dongyu; Cheng Wen; Li Jikai; Huang Hong; Shen Qiming; Zhang Qiang; Liu Zhengshan

2005-10-01

Movable fixed area γ dose rate monitor has not only the characteristics of fixed area γ dose rate monitor, but that of portable meter as well. Its main function is to monitor the areas where dose rate would change without orderliness to prevent unplanned radiation exposure accidents from happening. The design way of the monitor, the main indicators description, the working principle and the comprising of software and hardware are briefly introduced. The monitor has the characteristics of simple installation, easy maintenance, little power consumption, wide range, notability of visual and audible alarm and so on. Its design and technique have novelty and advancement. (authors)

Radon continuous monitoring in Altamira Cave (northern Spain) to assess user's annual effective dose

International Nuclear Information System (INIS)

Lario, J.; Sanchez-Moral, S.; Canaveras, J.C.; Cuezva, S.; Soler, V.

2005-01-01

In this work, we present the values of radon concentration, measured by continuous monitoring during a complete annual cycle in the Polychromes Hall of Altamira Cave in order to undertake more precise calculations of annual effective dose for guides and visitors in tourist caves. The 222 Rn levels monitored inside the cave ranges from 186 Bq m -3 to 7120 Bq m -3 , with an annual average of 3562 Bq m -3 . In order to more accurately estimate effective dose we use three scenarios with different equilibrium factors (F=0.5, 0.7 and 1.0) together with different dose conversion factors proposed in the literature. Neither effective dose exceeds international recommendations. Moreover, with an automatic radon monitoring system the time remaining to reach the maximum annual dose recommended could be automatically updated

IDEA system - a new computer-based expert system for incorporation monitoring

International Nuclear Information System (INIS)

Doerfel, H.

2007-01-01

Recently, at the Karlsruhe Research Centre, a computer-based expert system, Internal Dose Equivalent Assessment System (IDEA System), has been developed for assisting dosimetrists in applying the relevant recommendations and guidelines for internal dosimetry. The expert system gives guidance to the user with respect to: (a) planning of monitoring, (b) performing routine and special monitoring, and (c) evaluation of primary monitoring results. The evaluation is done according to the IDEA System guidelines (Doerfel, H. et al., General guidelines for the estimation of committed effective dose from incorporation monitoring data. Research Report FZKA 7243, Research Center Karlsruhe, Karlsruhe (2006). ISSN 0947-8260.) in a three-stage procedure according to the expected level of exposure. At the first level the evaluation is performed with default or site-specific parameter values, at the second level case-specific parameter values are applied and at the third level a special evaluation is performed with individual adjustment of model parameter values. With these well-defined procedures the expert system follows the aim, in which all recommendations and guidelines are applied properly and the results in terms of committed effective and organ doses are close to the best estimate. (author)

Adequate technologies for wireless real-time dose rate monitoring for off-site emergency management

International Nuclear Information System (INIS)

Dielmann, R.; Buerkin, W.

2003-01-01

Full text: What are the requirements for off-site gamma dose rate monitoring systems? What are the pros and cons of available communication technologies? This report gives an overview of modern communication techniques and their applicability for reliable real-time data acquisition as basis for off-site nuclear emergency management. The results of three years operating experience with a wireless gamma dose rate monitoring system, installed around the NPPs of KURSK, KALININ and BALAKOVA (Russia) in the year 2000, are shown. (author)

IDEA-system - a new computer based expert system for incorporation monitoring

International Nuclear Information System (INIS)

Doerfel, H.

2005-01-01

Full text: There is an increasing number of national and international recommendations and guidelines for incorporation monitoring (ICRP Publications, IAEA Safety Reports, ISO Standards, etc.). These recommendations cover different phases of incorporation monitoring and they provide general requirements for the measuring techniques, the monitoring procedures and for the procedures to evaluate intakes and doses from the monitoring results. There is, however, still a strong need for giving guidance to the dosimetrists on how to apply all the regulations properly. Thus, the EU project IDEAS was launched in order to provide general guidelines for the assessment of internal dose from incorporation monitoring data. These guidelines have recently been discussed in a virtual workshop on the internet (www.ideas-workshop.de) and they are being considered by ICRP for possible adoption in the near future. Recently, in the Karlsruhe Research Centre, a computer-based expert system has been developed for assisting dosimetrists in applying the relevant recommendations and guidelines for incorporation monitoring and internal dosimetry. The expert system gives guidance to the user with respect to: planning of monitoring (estimation of potential exposures, decision on the requirements of monitoring, definition of optimum measuring techniques and monitoring intervals); performing routine and special monitoring and evaluation of primary monitoring results. The evaluation of primary monitoring results is done according to the IDEAS guidelines in a threestage procedure according to the expected level of exposure (E = committed effective dose): standard evaluation with default or site specific parameter values (E 6 mSv). With these well-defined procedures the expert system follows the aim, that all recommendations and guidelines are applied properly and thus: internal exposures of more than 1 mSv are very likely to be detected in all situations; the results in terms of committed effective

SU-G-IeP3-12: Preliminary Report On the Experience of Patient Radiation Dose Monitoring and Tracking Systems; PEMNET, Radimetrics and DoseWatch

International Nuclear Information System (INIS)

Lin, P; Corwin, F; Ghita, M

2016-01-01

Purpose: Three patient radiation dose monitoring and tracking (PRDMT) systems have been in operation at this institution for the past 6 months. There are useful information that should be disseminated to those who are considering installation of PRDMT programs. In addition, there are “problems” uncovered in the process of estimating fluoroscopic “peak” skin dose (PSD), especially, for those patients who received interventional angiographic studies and in conjunction with surgical procedures. Methods: Upon exporting the PRDMT data to Microsoft Excel program, the peak skin dose can be estimated by applying various correction factors including; attenuation due to the tabletop and examination mattress, table height, tabletop translation, backscatter, etc. A procedure was established to screen and divide the PRDMT reported radiation dose and estimated PSD to three different levels of threshold to assess the potential skin injuries, to assist patient follow-up, risk management and provide radiation dosimetry information in case of “Sentinel Event”. Results: The Radiation Dose Structured Report (RDSR) was found to be the prerequisite for the PRDMT systems to work seamlessly. And, the geometrical parameters (gantry and table orientation) displayed by the equipment are not necessarily implemented in the “patient centric” manner which could result in a large error in the PSD estimation. Since, the PRDMT systems obtain their pertinent data from the DICOM tags including the polarity (+ and − signs), the geometrical parameters need to be verified. Conclusion: PRDMT systems provide a more accurate PSD estimation than previously possible as the air-kerma-area dose meter become widely implemented. However, care should be exercised to correctly apply the geometrical parameters in estimating the patient dose. In addition, further refinement is necessary for these software programs to account for all geometrical parameters such as the tabletop translation in the z

SU-G-IeP3-12: Preliminary Report On the Experience of Patient Radiation Dose Monitoring and Tracking Systems; PEMNET, Radimetrics and DoseWatch

Energy Technology Data Exchange (ETDEWEB)

Lin, P; Corwin, F; Ghita, M [Virginia Commonwealth University Medical Center, Richmond, VA (United States)

2016-06-15

Purpose: Three patient radiation dose monitoring and tracking (PRDMT) systems have been in operation at this institution for the past 6 months. There are useful information that should be disseminated to those who are considering installation of PRDMT programs. In addition, there are “problems” uncovered in the process of estimating fluoroscopic “peak” skin dose (PSD), especially, for those patients who received interventional angiographic studies and in conjunction with surgical procedures. Methods: Upon exporting the PRDMT data to Microsoft Excel program, the peak skin dose can be estimated by applying various correction factors including; attenuation due to the tabletop and examination mattress, table height, tabletop translation, backscatter, etc. A procedure was established to screen and divide the PRDMT reported radiation dose and estimated PSD to three different levels of threshold to assess the potential skin injuries, to assist patient follow-up, risk management and provide radiation dosimetry information in case of “Sentinel Event”. Results: The Radiation Dose Structured Report (RDSR) was found to be the prerequisite for the PRDMT systems to work seamlessly. And, the geometrical parameters (gantry and table orientation) displayed by the equipment are not necessarily implemented in the “patient centric” manner which could result in a large error in the PSD estimation. Since, the PRDMT systems obtain their pertinent data from the DICOM tags including the polarity (+ and − signs), the geometrical parameters need to be verified. Conclusion: PRDMT systems provide a more accurate PSD estimation than previously possible as the air-kerma-area dose meter become widely implemented. However, care should be exercised to correctly apply the geometrical parameters in estimating the patient dose. In addition, further refinement is necessary for these software programs to account for all geometrical parameters such as the tabletop translation in the z

Quality control of thermoluminesce personal dose monitoring

International Nuclear Information System (INIS)

Shang Aiguo; He Wenchang; Zhao Fengtao

2006-01-01

In order to evaluate the influence factor to thermoluminesce personal dose monitoring result, the every question that can appear based on the fact was analyzed. The results show that the detector, annealing, measuring process can influence the monitoring result. It gives some measures to enhance monitoring quality. (authors)

Monitoring of radiation exposure and registration of doses

International Nuclear Information System (INIS)

1993-01-01

The Section 32 of the Finnish Radiation Act (592/91) defines the requirements to be applied to the monitoring of the radiation exposure and working conditions in Finland. The concepts relevant to the monitoring and guidelines for determining the necessity of the monitoring as well as its organizing are given in the guide. Instructions for reporting doses to the Dose Register of the Finnish Centre for Radiation and Nuclear Safety (STUK) are given, also procedures for situations leading to exceptional exposures are described. (9 refs.)

Environmental monitoring with a portable TLD system

Energy Technology Data Exchange (ETDEWEB)

Szabo, P P; Feher, I; Deme, S; Szabo, B; Vagvoelgyi, J; German, E [Hungarian Academy of Sciences, Budapest. Central Research Inst. for Physics

1984-01-01

Two types of TLD systems are used for environmental dose monitoring. One is based on an NHZ-203 laboratory TLD reader and CaSO/sub 4/:Dy powder. The other is based on CaSO/sub 4/:Tm bulbs and a small, portable TLD reader built into a cross-country car and operated by means of the car battery. The laboratory TLD system has been used for many years for environmental monitoring and it has been tested and proved satisfactory at international intercomparisons for environmental dosemeters. The new portable TLD system has the advantage of being able to establish the dose in a few minutes at the environmental station. The transport dose is omitted as the TLDs are evaluated at the field site. The evaluation of a bulb needs only a few minutes and the measured dose value can be reported back by radio - an important aspect during an emergency situation.

Environmental radiation monitoring: mobile gamma dose rate measurements along Mumbai-Hyderabad rail route and Hyderabad city roads

International Nuclear Information System (INIS)

Divkar, J.K.; Padmanabhan, N.; Chaudhury, Probal; Pradeepkumar, K.S.; Pujari, R.N.; Dogra, Santosh; Sharma, D.N.; Rajagopalan, S.; Srivastava, G.K.

2005-01-01

Environmental Radiation monitoring based on gamma dose rate logging on a mobile platform integrated with real time position from a Global Positioning System is an effective tool to acquire dose rate profile and generate radiological map of any geographical region. The microcontroller based dose rate data acquisition system capable of storing the acquired data and transferring to an attached laptop/PC and providing a graphical illustration of relative variations in gamma background can also be used for quick assessment of environmental radiological impact assessment. This paper describes the methodology and results of the environmental gamma dose rate monitoring surveys carried out: (i) on Mumbai-Hyderabad rail route with the systems installed in the trains guard's room and (ii) Hyderabad city roads with systems installed in a monitoring van. The results indicate significant difference in the gamma background measured along the rail route between Mumbai-Hyderabad and in the radiological map generated after the Hyderabad city survey. (author)

Thermoluminescence dosimetry environmental monitoring system

International Nuclear Information System (INIS)

Bortoluzzi, S.

1989-01-01

In this report, characteristics and performances of an environmental monitoring system with thermoluminescence dosimetry are presented. Most of the work deals with the main physical parameters necessary for measurements of ambiental dose. At the end of this report some of level doses in the environment around the site of the ENEA Center of Energy Research Salluggia (Italy) are illustrated

Monitoring of high-radiation areas for the assessment of operational and body doses

International Nuclear Information System (INIS)

Chen, T.J.; Tung, C.J.; Yeh, W.W.; Liao, R.Y.

2004-01-01

The International Commission on Radiological Protection (ICRP) recommended a system of dose limits for the protection of ionizing radiation. This system was established based on the effective dose, E, and the equivalent dose to an organ or tissue, H T , to assess stochastic and deterministic effects. In radiation protection monitoring for external radiation, operational doses such as the deep dose equivalent index, H I,d , shallow dose equivalent index, H I,s , ambient dose equivalent [1,4-6], H*, directional dose equivalent, H', individual dose equivalent-penetrating, H p , and individual dose equivalent-superficial, H s , are implemented. These quantities are defined in an International Commission on Radiation Units and Measurements (ICRU) sphere and in an anthropomorphic phantom under simplified irradiation conditions. They are useful when equivalent doses are below the corresponding limits. In the case of equivalent doses far below the limits, the exposure or air kerma is commonly applied. For workers exposed to high levels of radiation, accurate assessments of effective doses and equivalent doses may be needed in order to acquire legal and health information. In the general principles of monitoring for radiation protection of workers, ICRP recommended that: 'A graduated response is advocated for the monitoring of the workplace and for individual monitoring - graduated in the sense that a greater degree of monitoring is deemed to be necessary as doses increase of as unpredictability increases. Gradually more complex or realistic procedures should be adopted as doses become higher. Thus, at low dose equivalents (corresponding say to those within Working Condition B) dosimetric quantities might be used directly to assess exposure, since accuracy is not crucial. At intermediate dose equivalents (corresponding say to Working Condition A and slight overexposures) somewhat greater accuracy is warranted, and the conversion coefficients from dosimetric to radiation

Quality assurance in CT: implementation of the updated national diagnostic reference levels using an automated CT dose monitoring system.

Science.gov (United States)

Appel, E; Kröpil, P; Bethge, O T; Aissa, J; Thomas, C; Antoch, G; Boos, J

2018-03-20

To evaluate the implementation of the updated computed tomography (CT) diagnostic reference levels (DRLs) from the German Federal Office for Radiation Protection into clinical routine using an automatic CT dose monitoring system. CT radiation exposure was analysed before and after implementing the updated national DRLs into routine clinical work in 2016. After the implementation process, institutional CT protocols were mapped to the anatomical regions for which DRLs were provided. Systematically, protocols that exceeded the thresholds were optimised and analysed in detail. The CT radiation output parameters analysed were volumetric CT dose index (CTDIvol) and dose-length product (DLP). Three radiologists evaluated subjective image quality using a three-point Likert scale. The study included 94,258 CT series (from 27,103 CT examinations) in adult patients performed in 2016. When averaged over all body regions with available DRL, institutional CTDIvol/DLP values were always below the DRLs (65.2±32.9%/67.3±41.5% initially; 59.4±32%/60.5±39.9% after optimisation). Values exceeding the national DRLs were found for pelvis (n=268; CTDIvol 107.7±65.7%/DLP 106.3±79.3%), lumbar spine (n=91; 160.8±74.7%/175.2±104.1%), and facial bones (n=527; 108±39%/152.7±75.7%). After optimisation, CTDIvol and DLP were 87.9±73%/87.8±80.8% for the pelvis, 67.8±33.2%/74.5±50.6% for the lumbar spine and 95.1±45.8%/133.3±74.6% for the viscerocranium. An automatic CT dose monitoring system enabled not only comprehensive monitoring of a DRL implementation process but can also help to optimise radiation exposure. Copyright © 2018 The Royal College of Radiologists. Published by Elsevier Ltd. All rights reserved.

Antipsychotic treatment dosing profile in patients with schizophrenia evaluated with electronic monitoring (MEMS®).

Science.gov (United States)

Acosta, Francisco J; Ramallo-Fariña, Yolanda; Bosch, Esperanza; Mayans, Teresa; Rodríguez, Carlos J; Caravaca, Ana

2013-05-01

Although the Medication Event Monitoring System (MEMS®) device offers accurate information on treatment dosing profile, such profile has never been studied in patients with schizophrenia. Enhancing our knowledge on this issue would help in developing intervention strategies to improve adherence to antipsychotic treatment in these patients. 74 outpatients with schizophrenia were monitored with the MEMS device for a 3-month period, for evaluation of antipsychotic treatment dosing profile, possible influence of medication schedule-related variables, adherence to treatment--considering dose intake within prescribed timeframes--and possible Hawthorne's effect of using the MEMS device. Dose-omission gaps occurred in 18.7% of monitoring days, most frequently during weekends, almost significantly. Almost one-third of prescribed doses were taken out of prescribed time. Neither the prescribed number of daily doses nor the indicated time of the day for dose intake (breakfast, dinner), were associated with correct antipsychotic dosing. Excess-dose was rare in general, and more frequent out of prescribed dose timeframe. No Hawthorne's effect was found for the MEMS device. Adherence reached only 35% according to a definition that included dose intake within prescribed timeframes. Antipsychotic treatment dosing was considerably irregular among patients with schizophrenia. Strategies to reduce dose-omission gaps and increase dosing within prescribed timeframes seem to be necessary. Gaining knowledge on precise oral antipsychotic dosing profiles or the influence of schedule-related variables may be useful to design strategies towards enhancing adherence. There appears to be no Hawthorne's effect associated with the use of MEMS devices in outpatients with schizophrenia. Copyright © 2013 Elsevier B.V. All rights reserved.

Monitoring of radiation exposure and registration of doses

International Nuclear Information System (INIS)

1996-01-01

The guide defines the concepts relevant to the monitoring of radiation exposure and working conditions and provides guidelines for determining the necessity of monitoring and subsequently organizing it. In addition, instructions are given for reporting doses to the Dose Register of the Finnish Centre for Radiation and Nuclear Safety (STUK). Also the procedures are described for situations leading to exceptional exposures. (10 refs., 1 tab.)

Personal radiation monitoring and assessment of doses received by radiation workers (1991)

International Nuclear Information System (INIS)

Morris, N.D.

1992-06-01

The Australian Radiation Laboratory has operated a Personal Radiation Monitoring Service since the early 1930's so that people working with radiation can determine the radiation doses that they receive due to their occupation. Since late 1986, all persons monitored by the Service have been registered on a data base which maintains records of the doses received by each individual wearer. Ultimately, this data base will become a National Register of the doses received within Australia. At present, the Service regularly monitors approximately 20,000 persons, which is roughly 70 percent of those monitored in Australia, and maintains dose histories of over 35,000 people. The skin dose for occupationally exposed workers can be measured by using one of the four types of monitor issued by the Service: 1. Thermoluminescent Dosemeter (TLD monitor) 2. Finger TLD 3. Neutron Monitor 4. Special TLD. The technical description of the monitors is provided along with the method for calculating the radiation dose. 5 refs., 7 tabs., 4 figs

TLD personnel monitoring dose estimation- extending the upper limit of the dose range

International Nuclear Information System (INIS)

Popli, K.L.; Sathian, Deepa; Divakaran, T.; Massand, O.P.

2001-01-01

TLD personnel monitoring was introduced in the year 1975 in India and at present nearly 41,000 radiation workers are being monitored by 13 monitoring laboratories all over India. The BARC- TLD being used for personnel monitoring is based on CaSO 4 :Dy embedded in PTFE and semi-automatic TL reader using hot N 2 Gas for heating the dosimeters. This reader has the range to measure γ dose from ten μSv to 3 μSv and x-ray dose form 1 μ Sv to 0.3 Sv due to the higher sensitivity of CaSO 4 : Dy to lower energy photons (20keV-50 keV) generated by diagnostic x-ray units. The x-ray radiation workers are at present nearly 35% of the total radiation workers monitored and this number is expected to grow as more and more number of x-ray workers are covered under this service. The upper limit of the x-ray dose range of the instrument is 0.3 Sv, whereas in the past one year it has been observed that at least 25% of the total overexposures reported in case of x-ray workers have recorded the dose more than 0.3 Sv. This paper presents the technique developed to extend the upper limit of the range from 0.3 Sv to 1 Sv for x-rays and 10 Sv for γ rays

A beta skin dose monitor using an Eberline RO-2 ion chamber

International Nuclear Information System (INIS)

Jester, W.A.; Levine, S.H.; Lin, T.J.; Hock, R.

1994-01-01

The authors have developed a portable beta skin dose monitor that uses an Eberline RO-2trademark ion chamber. The development was based, in part, upon the previous development of a beta skin dose monitor employing silicon detectors. In this current work, the two entrance windows of the RO-2 were replaced by windows having a total mass thickness of 1.74 mg/cm 2 . A two section source-detector holder was constructed. One section fastens to the RO-2 and holds the detector at the right position to determine the contact skin dose from beta emitters located on surfaces. A second section attaches to the first, and provides fixed counting geometry for radioactive samples such as hot particles. The first section also contains a slide mechanism that allows the placement of absorbers of zero (0), 8.38, and 1000 mg/cm 2 between the detector window and the beta source. The detector response to these absorbers allows for the determination of beta skin dose. The system was modeled using a Monte Carlo beta attenuation code computing the beta skin dose to RO-2 detector response as a function of absorber thickness, average beta energy, source diameter and source position. Using the RO-2 reading from each of the three absorber configurations allows the calculation of beta skin dose and the average beta energy. The results of these calculations were confirmed through the use of three massless radioactive beta sources, traceable to the National Institute of Standards and Technology, and several utility-supplied hot particles having well-established contact skin doses. An extrapolation chamber was also used to confirm the results obtained from this monitor. This system is now use at the Pennsylvania Power and Light (PP and L) Company, the project sponsor. ((orig.))

Personal radiation monitoring and assessment of doses received by radiation workers (1996)

International Nuclear Information System (INIS)

Morris, N.D.

1996-12-01

Since late 1986, all persons monitored by the Australian Radiation Laboratory have been registered on a data base which maintains records of the doses received by each individual wearer. At present, the Service regularly monitors approximately 30,000 persons, which is roughly 90 percent of those monitored in Australia, and maintains dose histories of over 75,000 people. The skin dose for occupationally exposed workers can be measured by using one of the five types of monitor issued by the Service: Thermoluminescent Dosemeter (TLD monitor), Finger TLD 3, Neutron Monitor, Special TLD and Environmental monitor. The technical description of the monitors is provided along with the method for calculating the radiation dose. 5 refs., 7 tabs., 5 figs

Requirements to a Norwegian National Automatic Gamma Monitoring System

International Nuclear Information System (INIS)

Lauritzen, B.; Hedemann Jensen, P.; Nielsen, F.

2005-04-01

An assessment of the overall requirements to a Norwegian gamma-monitoring network is undertaken with special emphasis on the geographical distribution of automatic gamma monitoring stations, type of detectors in such stations and the sensitivity of the system in terms of ambient dose equivalent rate increments above the natural background levels. The study is based upon simplified deterministic calculations of the radiological consequences of generic nuclear accident scenarios. The density of gamma monitoring stations has been estimated from an analysis of the dispersion of radioactive materials over large distances using historical weather data; the minimum density is estimated from the requirement that a radioactive plume may not slip unnoticed in between stations of the monitoring network. The sensitivity of the gamma monitoring system is obtained from the condition that events that may require protective intervention measures should be detected by the system. Action levels for possible introduction of sheltering and precautionary foodstuff restrictions are derived in terms of ambient dose equivalent rate. For emergency situations where particulates contribute with only a small fraction of the total ambient dose equivalent rate from the plume, it is concluded that measurements of dose rate are sufficient to determine the need for sheltering; simple dose rate measurements however, are inadequate to determine the need for foodstuff restrictions and spectral measurements are required. (au)

MO-FG-202-08: Real-Time Monte Carlo-Based Treatment Dose Reconstruction and Monitoring for Radiotherapy

Energy Technology Data Exchange (ETDEWEB)

Tian, Z; Shi, F; Gu, X; Tan, J; Hassan-Rezaeian, N; Jiang, S; Jia, X [UT Southwestern Medical Center, Dallas, TX (United States); Graves, Y [University of California, San Diego, La Jolla, CA (United States)

2016-06-15

Purpose: This proof-of-concept study is to develop a real-time Monte Carlo (MC) based treatment-dose reconstruction and monitoring system for radiotherapy, especially for the treatments with complicated delivery, to catch treatment delivery errors at the earliest possible opportunity and interrupt the treatment only when an unacceptable dosimetric deviation from our expectation occurs. Methods: First an offline scheme is launched to pre-calculate the expected dose from the treatment plan, used as ground truth for real-time monitoring later. Then an online scheme with three concurrent threads is launched while treatment delivering, to reconstruct and monitor the patient dose in a temporally resolved fashion in real-time. Thread T1 acquires machine status every 20 ms to calculate and accumulate fluence map (FM). Once our accumulation threshold is reached, T1 transfers the FM to T2 for dose reconstruction ad starts to accumulate a new FM. A GPU-based MC dose calculation is performed on T2 when MC dose engine is ready and a new FM is available. The reconstructed instantaneous dose is directed to T3 for dose accumulation and real-time visualization. Multiple dose metrics (e.g. maximum and mean dose for targets and organs) are calculated from the current accumulated dose and compared with the pre-calculated expected values. Once the discrepancies go beyond our tolerance, an error message will be send to interrupt the treatment delivery. Results: A VMAT Head-and-neck patient case was used to test the performance of our system. Real-time machine status acquisition was simulated here. The differences between the actual dose metrics and the expected ones were 0.06%–0.36%, indicating an accurate delivery. ∼10Hz frequency of dose reconstruction and monitoring was achieved, with 287.94s online computation time compared to 287.84s treatment delivery time. Conclusion: Our study has demonstrated the feasibility of computing a dose distribution in a temporally resolved fashion

Personnel monitoring system by thermoluminescence dosimeter - a study and review

International Nuclear Information System (INIS)

Iyer, V.S.; Alok, M.; Chandel, B.S.

2018-01-01

The principle objective of personnel monitoring system is to prevent overexposure and avoid unnecessary exposure of personnel working with various sources of radiation. The adequate system of personnel monitoring must provide for the measurement. evaluation and recording of significant doses accumulated by individuals together with a recording of conditions under which these doses are received

Analysis of workers' dose records from the Greek Dose Registry Information System

International Nuclear Information System (INIS)

Kamenopoulou, V.; Dimitriou, P.; Proukakis, Ch.

1995-01-01

The object of this work is the study of the individual film badge annual dose information of classified workers in Greece, monitored and assessed by the central dosimetry service of the Greek Atomic Energy Commission. Dose summaries were recorded and processed by the Dose Registry Information System. The statistical analysis refers to the years 1989-93 and deals with the distribution of individuals in the occupational groups, the mean annual dose, the collective dose, the distribution of the dose over the different specialties and the number of workers that have exceeded any of the established dose limits. Results concerning the annual dose summaries, demonstrate a year-by-year reduction in the mean individual dose to workers in the health sector. Conversely, exposures in the industrial sector did not show any decreasing tendency during the period under consideration. (Author)

Automated personal dosimetry monitoring system for NPP

International Nuclear Information System (INIS)

Chanyshev, E.; Chechyotkin, N.; Kondratev, A.; Plyshevskaya, D.

2006-01-01

Full text: Radiation safety of personnel at nuclear power plants (NPP) is a priority aim. Degree of radiation exposure of personnel is defined by many factors: NPP design, operation of equipment, organizational management of radiation hazardous works and, certainly, safety culture of every employee. Automated Personal Dosimetry Monitoring System (A.P.D.M.S.) is applied at all nuclear power plants nowadays in Russia to eliminate the possibility of occupational radiation exposure beyond regulated level under different modes of NPP operation. A.P.D.M.S. provides individual radiation dose registration. In the paper the efforts of Design Bureau 'Promengineering' in construction of software and hardware complex of A.P.D.M.S. (S.H.W. A.P.D.M.S.) for NPP with PWR are presented. The developed complex is intended to automatize activities of radiation safety department when caring out individual dosimetry control. The complex covers all main processes concerning individual monitoring of external and internal radiation exposure as well as dose recording, management, and planning. S.H.W. A.P.D.M.S. is a multi-purpose system which software was designed on the modular approach. This approach presumes modification and extension of software using new components (modules) without changes in other components. Such structure makes the system flexible and allows modifying it in case of implementation a new radiation safety requirements and extending the scope of dosimetry monitoring. That gives the possibility to include with time new kinds of dosimetry control for Russian NPP in compliance with IAEA recommendations, for instance, control of the equivalent dose rate to the skin and the equivalent dose rate to the lens of the eye S.H.W. A.P.D.M.S. provides dosimetry control as follows: Current monitoring of external radiation exposure: - Gamma radiation dose measurement using radio-photoluminescent personal dosimeters. - Neutron radiation dose measurement using thermoluminescent

SU-F-J-147: Magnetic Field Dose Response Considerations for a Linac Monitor Chamber

Energy Technology Data Exchange (ETDEWEB)

Reynolds, M; Fallone, B [Cross Cancer Institute, Edmonton, AB (Canada)

2016-06-15

Purpose: The impact of magnetic fields on the readings of a linac monitor chamber have not yet been investigated. Herein we examine the total dose response as well as any deviations in the beam parameters of flatness and symmetry when a Varian monitor chamber is irradiated within an applied magnetic field. This work has direct application to the development of Linac-MR systems worldwide. Methods: A Varian monitor chamber was modeled in the Monte Carlo code PENELOPE and irradiated in the presence of a magnetic field with a phase space generated from a model of a Linac-MR prototype system. The magnetic field strength was stepped from 0 to 3.0T in both parallel and perpendicular directions with respect to the normal surface of the phase space. Dose to each of the four regions in the monitor chamber were scored separately for every magnetic field adaptation to evaluate the effect of the magnetic field on flatness and symmetry. Results: When the magnetic field is perpendicular to the phase space normal we see a change in dose response with a maximal deviation (10–25% depending on the chamber region) near 0.75T. In the direction of electron deflection we expectedly see opposite responses in chamber regions leading to a measured asymmetry. With a magnetic field parallel to the phase space normal we see no measured asymmetries, however there is a monotonic rise in dose response leveling off at about +12% near 2.5T. Conclusion: Attention must be given to correct for the strength and direction of the magnetic field at the location of the linac monitor chamber in hybrid Linac-MR devices. Elsewise the dose sampled by these chambers may not represent the actual dose expected at isocentre; additionally there may be a need to correct for the symmetry of the beam recorded by the monitor chamber. Fallone is a co-founder and CEO of MagnetTx Oncology Solutions (under discussions to license Alberta bi-planar linac MR for commercialization).

Online radiation dose measurement system for ATLAS experiment

International Nuclear Information System (INIS)

Mandic, I.; Cindro, V.; Dolenc, I.; Gorisek, A.; Kramberger, G.; Mikuz, M.; Bronner, J.; Hartet, J.; Franz, S.

2009-01-01

In experiments at Large Hadron Collider, detectors and electronics will be exposed to high fluxes of photons, charged particles and neutrons. Damage caused by the radiation will influence performance of detectors. It will therefore be important to continuously monitor the radiation dose in order to follow the level of degradation of detectors and electronics and to correctly predict future radiation damage. A system for online radiation monitoring using semiconductor radiation sensors at large number of locations has been installed in the ATLAS experiment. Ionizing dose in SiO 2 will be measured with RadFETs, displacement damage in silicon in units of 1-MeV(Si) equivalent neutron fluence with p-i-n diodes. At 14 monitoring locations where highest radiation levels are expected the fluence of thermal neutrons will be measured from current gain degradation in dedicated bipolar transistors. The design of the system and tests of its performance in mixed radiation field is described in this paper. First results from this test campaign confirm that doses can be measured with sufficient sensitivity (mGy for total ionizing dose measurements, 10 9 n/cm 2 for NIEL (non-ionizing energy loss) measurements, 10 12 n/cm 2 for thermal neutrons) and accuracy (about 20%) for usage in the ATLAS detector

Procedures for operational monitoring of the environmental equivalent doses in cobalt therapy

International Nuclear Information System (INIS)

Perez Velasquez, Reytel; Gonzalez Lopez, Nadia; Perez Tamayo, Luis

2009-01-01

It took as its object of study environmental equivalent dose rates of field radiation they face radiophysicists technicians and medical physicists in the irradiation site of the radiation department of Lenin Hospital in Holguin, and the public that travels or remains in premises and areas surrounding the campus. It A review of national and international publications as well as technical documents to study the state of the art of the methodological existing monitoring of those dose rates and the valuation of impact in the context of an environmental management system. Since no detailed instructions and to perform the above-mentioned monitoring was proposed structure should contain a procedure to regulate the steps for this monitoring in the radiotherapy department of the Lenin Hospital Holguin, for which we studied the guidelines of NC ISO 14000 , and was conducted wide experiment whose led to: illustrate the level of doses required workers exposed occupationally exposed to radiation and the public compare these levels with natural radiation sources, assess the effectiveness of shielding the site of irradiation and the points of greatest risk within and outside the enclosure irradiation.Also assessed the impact it can have on the health of people exposed to such doses. Finally, we proposed a procedure for conducting subsequent monitoring and made recommendations to reduce levels radiation determined the lowest level reasonably achievable. (author)

SU-G-IeP3-13: Real-Time Patient and Staff Dose Monitoring in Fluoroscopy Guided Interventions

International Nuclear Information System (INIS)

Vergoossen, L; Sailer, A; Paulis, L; Wildberger, J; Jeukens, C

2016-01-01

Purpose: Interventional radiology procedures involve the use of X-rays, which can pose a large radiation burden on both patients and staff. Although some reports on radiation dose are available, most studies focus on limited types of procedures and only report patient dose. In our cathlabs a dedicated real-time patient and staff monitoring system was installed in November 2015. The aim of this study was to investigate the patient and staff dose exposure for different types of interventions. Methods: Radiologists involved in fluoroscopy guided interventional radiology procedures wore personal dose meters (PDM, DoseAware, Philips) on their lead-apron that measured the personal dose equivalent Hp(10), a measure for the effective dose (E). Furthermore, reference PDMs were installed in the C-arms of the fluoroscopy system (Allura XPer, Philips). Patient dose-area-product (DAP) and PDM doses were retrieved from the monitoring system (DoseWise, Philips) for each procedure. A total of 399 procedures performed between November 2015 and February 2016 were analyzed with respect to the type of intervention. Interventions were grouped by anatomy and radiologist position. Results: The mean DAP for the different types of interventions ranged from 2.86±2.96 Gycm"2 (percutaneous gastrostomy) to 147±178 Gycm"2 (aortic repair procedures). The radiologist dose (E) ranged from 5.39±7.38 µSv (cerebral interventions) to 84.7±106 µSv (abdominal interventions) and strongly correlated with DAP (R"2=0.83). The E normalized to DAP showed that the relative radiologist dose was higher for interventions in larger body parts (e.g. abdomen) compared to smaller body parts (e.g. head). Conclusion: Using a real-time dose monitoring system we were able to assess the staff and patient dose revealing that the relative staff dose strongly depended on the type of procedure and patient anatomy. This could be explained by the position of the radiologist with respect to the patient and X-ray tube. To

Upgraded national occupational dose registry system - implementation of Phase-II programme

International Nuclear Information System (INIS)

Sanaye, S.S.; Baburajan, Sujatha; Johnson, Seethal; Nalawade, S.K.; Tudu, S.C.; Khedekar, B.M.; Sapra, B.K.; Datta, D.

2016-01-01

National Occupational Dose Registry System (NODRS) of Bhabha Atomic Research Centre maintains and updates occupational dose data of all monitored radiation workers in the country. The registry was upgraded in 2008 by establishing networked NODRS system through which personnel monitoring labs at different nuclear installations were networked with main dose registry server using the departmental ANUNET and NPCNET facilities. This has facilitated online allotment of personal numbers, storing of biometric information as well as providing online dose information to respective Health Physics Units (HPUs). On the basis of operational experience of NODRS and its feedback from users, Phase-II program was designed, developed and implemented. The paper gives an overview of implementation of this program at various sites

Area and environmental gamma dose monitoring at PINSTECH

International Nuclear Information System (INIS)

Javed, M.; Awan, M.A.; Ahmad, S.; Afsar, M.; Orfi, S.D.

1986-11-01

Radiation dose monitoring of various radioactive laboratories including PARR building, radioactive waste disposal area and the environment upto initial peripheral limits of PINSTECH has been carried out by TLD's installed at different locations. Average dose rates in terms of percentage of dose limits have been compiled. The results for the year 1985 have been discussed in this report. (author)

Radiation control monitoring system on the High Temperature Engineering Test Reactor

International Nuclear Information System (INIS)

Minowa, Y.; Nakazawa, T.; Sato, K.; Kikuchi, H.; Nomura, T.

1999-01-01

Radiation control monitoring system of the HTTR is divided into three subsystems; exhaust monitoring equipment, room air monitoring equipment, dose equivalent rate monitoring equipment. The exhaust monitoring equipment consists of exhaust gas monitors, exhaust dust monitors, and a tritium and carbon sampling device at normal operation of the reactor. Accident gas monitors are also provided for the emergency. The tritium and carbon sampling device uses cupper oxide as a oxidizer, and ethanol amine as a sampling materials which collects continuously tritium and carbon in dust during about one month and is measured by a liquid scintillation counter. The accident gas monitors consist of two channels, for a low and a high range. The high range-gas monitor consists of two ionization chambers: one encloses argon gas and the other encloses xenon gas. Average energy of various gamma-rays, hence, accident exposure dose of the public can be estimated with the comparison of the sensitivity of two kinds of ionization chambers. The dose equivalent rate monitoring equipment consists of silicon semiconductor detectors for gamma-ray, a ionization chamber for gamma-ray, a BF 3 counter for neutron, and accident area monitors which are located in the reactor container. The message of 'check dose !' or 'temporary evacuation !' can be send to the workers in the reactor with a light and a sound. A computer system collects the radiation monitoring data every 10 sec cycle and accumulates them in a server computer. The leakage and the dispersion of helium gas must be taken into account on the radiation control monitoring system of the HTTR. (Suetake, M.)

Personal monitoring and assessment of doses received by radiation workers

International Nuclear Information System (INIS)

Swindon, T.N.; Morris, N.D.

1981-12-01

The Personal Radiation Monitoring Service operated by the Australian Radiation Laboratory is outlined and the types of monitors used for assessment of doses received by radiation workers are described. The distribution of doses received by radiation workers in different occupational categories is determined. From these distributions, the average doses received have been assessed and the maximum likely additional increase in cancer deaths in Australia as a result of occupational exposure estimated. This increase is shown to be very small. There is, however, a considerable spread of doses received by individuals within occupational groups

Online radiation dose measurement system for ATLAS experiment

Energy Technology Data Exchange (ETDEWEB)

Mandic, I.; Cindro, V.; Dolenc, I.; Gorisek, A.; Kramberger, G. [Jozef Stefan Institute, Jamova 39, Ljubljana (Slovenia); Mikuz, M. [Jozef Stefan Institute, Jamova 39, Ljubljana (Slovenia); Faculty of Mathematics and Physics, University of Ljubljana (Slovenia); Bronner, J.; Hartet, J. [Physikalisches Institut, Universitat Freiburg, Hermann-Herder-Str. 3, Freiburg (Germany); Franz, S. [CERN, Geneva (Switzerland)

2009-07-01

In experiments at Large Hadron Collider, detectors and electronics will be exposed to high fluxes of photons, charged particles and neutrons. Damage caused by the radiation will influence performance of detectors. It will therefore be important to continuously monitor the radiation dose in order to follow the level of degradation of detectors and electronics and to correctly predict future radiation damage. A system for online radiation monitoring using semiconductor radiation sensors at large number of locations has been installed in the ATLAS experiment. Ionizing dose in SiO{sub 2} will be measured with RadFETs, displacement damage in silicon in units of 1-MeV(Si) equivalent neutron fluence with p-i-n diodes. At 14 monitoring locations where highest radiation levels are expected the fluence of thermal neutrons will be measured from current gain degradation in dedicated bipolar transistors. The design of the system and tests of its performance in mixed radiation field is described in this paper. First results from this test campaign confirm that doses can be measured with sufficient sensitivity (mGy for total ionizing dose measurements, 10{sup 9} n/cm{sup 2} for NIEL (non-ionizing energy loss) measurements, 10{sup 12} n/cm{sup 2} for thermal neutrons) and accuracy (about 20%) for usage in the ATLAS detector

Preliminary characterization of the passive neutron dose equivalent monitor with TLDs

Energy Technology Data Exchange (ETDEWEB)

Tsujimura, Norio; Kanai, Katsuta; Momose, Takumaro; Hayashi, Naomi [Japan Nuclear Cycle Development Inst., Tokai Works, Tokai, Ibaraki (Japan); Chen Erhu [Beijing Institute of Nuclear Engineering, Beijing (China)

2001-02-01

The passive neutron dose equivalent monitor with TLDs is composed of a cubic polyethylene moderator and TLDs at the center of moderator. This monitor was originally designed for measurements of neutron doses over long-term period of time around the nuclear facilities. In this study, the energy response of this monitor was calculated by Monte Carlo methods and experimentally obtained under {sup 241}Am-Be, {sup 252}Cf and moderated {sup 252}Cf neutron irradiation. Additionally, the responses of two types of conventional neutron dose equivalent meters (rem counters) were also investigated as comparison. The authors concluded that this passive neutron monitor with TLDs had a good energy response similar to conventional rem counters and could evaluate neutron doses within 10% of accuracy to the moderated fission spectra. (author)

Monitoring requirements for assessment of internal dose

International Nuclear Information System (INIS)

Eckerman, K.F.

1985-01-01

Data obtained by routine personnel monitoring is usually not a sufficient basis for estimation of dose. Collected data must be interpreted carefully and supplemented with appropriate information before reasonably accurate estimates of dose (i.e., accurate enough to indicate whether or nor personnel are exposed in excess of recommended limits) can be developed. When the exposure is of sufficient magnitude that a rather precise estimate of dose is needed, the health physicist will bring to bear on the problem other, more refined, methods of dosimetry. These might include a reconstruction of the incident and, for internal emitters, an extensive series of in vivo measurements or analyses of excreta. Thus, cases of special significance must often be evaluated using techniques and resources beyond those routinely employed. This is not a criticism of most routine monitoring programs. These programs are usually carefully designed in a manner commensurate with the degree of exposure routinely encountered and the requirement of a practical program of radiation protection. 10 refs

The National Dose Registration and Information System: Dose distributions in the Netherlands over the period 1989-1993

International Nuclear Information System (INIS)

Dijk, J.W.E. van; Julius, H.W.; Bogaerde, M.A. van de

1994-01-01

In 1988 the Ministry of Social Affairs and Employment commissioned TNO Radiological Service to set up a National Dose REgistration and Information System (NDRIS). The government had three reasons in view to build NDRIS: To improve radiation protection by supervising the occupational doses of radiation workers by using one central database system; To improve the reliability of long term storage of dose data; To improve the possibilities for statistical analysis of occupational doses to guide policy making. Each approved dosimetry service (ADS) in the country sends its dose information to NDRIS on a monthly basis. IN its turn NDRIS sends back for each worker monitored by that ADS, the integrated dose as measured by any ADS. This creates the possibility for each ADS to report to the workers their total annual dose irrespectively whether they work for more than one employer or are monitored by more than one ADS, either simultaneously or successively in the course of the year. European legislation requires that the occupational dose should be controlled in this way. The availability of the centralized database replaces the need of a radiation passbook for national use. The passbook that is needed by radiation workers during interstate travelling can be produced using data from NDRIS

A real time dose monitoring and dose reconstruction tool for patient specific VMAT QA and delivery

International Nuclear Information System (INIS)

Tyagi, Neelam; Yang Kai; Gersten, David; Yan Di

2012-01-01

Purpose: To develop a real time dose monitoring and dose reconstruction tool to identify and quantify sources of errors during patient specific volumetric modulated arc therapy (VMAT) delivery and quality assurance. Methods: The authors develop a VMAT delivery monitor tool called linac data monitor that connects to the linac in clinical mode and records, displays, and compares real time machine parameters with the planned parameters. A new measure, called integral error, keeps a running total of leaf overshoot and undershoot errors in each leaf pair, multiplied by leaf width, and the amount of time during which the error exists in monitor unit delivery. Another tool reconstructs Pinnacle 3 ™ format delivered plan based on the saved machine logfile and recalculates actual delivered dose in patient anatomy. Delivery characteristics of various standard fractionation and stereotactic body radiation therapy (SBRT) VMAT plans delivered on Elekta Axesse and Synergy linacs were quantified. Results: The MLC and gantry errors for all the treatment sites were 0.00 ± 0.59 mm and 0.05 ± 0.31°, indicating a good MLC gain calibration. Standard fractionation plans had a larger gantry error than SBRT plans due to frequent dose rate changes. On average, the MLC errors were negligible but larger errors of up to 6 mm and 2.5° were seen when dose rate varied frequently. Large gantry errors occurred during the acceleration and deceleration process, and correlated well with MLC errors (r= 0.858, p= 0.0004). PTV mean, minimum, and maximum dose discrepancies were 0.87 ± 0.21%, 0.99 ± 0.59%, and 1.18 ± 0.52%, respectively. The organs at risk (OAR) doses were within 2.5%, except some OARs that showed up to 5.6% discrepancy in maximum dose. Real time displayed normalized total positive integral error (normalized to the total monitor units) correlated linearly with MLC (r= 0.9279, p < 0.001) and gantry errors (r= 0.742, p= 0.005). There is a strong correlation between total integral

An interactive RADIANCE toolkit for customizable CT dose monitoring and reporting.

Science.gov (United States)

Cook, Tessa S; Sundaram, Anand; Boonn, William W; Kim, Woojin

2013-08-01

The need for tools to monitor imaging-related radiation has grown dramatically in recent years. RADIANCE, a freely available open-source dose-monitoring tool, was developed in response to the need for an informatics solution in this realm. A number of open-source as well as commercial solutions have since been developed to enable radiology practices to monitor radiation dose parameters for modalities ranging from computed tomography to radiography to fluoroscopy. However, it is not sufficient to simply collect this data; it is equally important to be able to review it in the appropriate context. Most of the currently available dose-monitoring solutions have some type of reporting capability, such as a real-time dashboard or a static report. Previous versions of RADIANCE have included a real-time dashboard with pre-set screens that plot effective dose estimates according to different criteria, as well as monthly scorecards to summarize dose estimates for individuals within a radiology practice. In this work, we present the RADIANCE toolkit, a customizable reporting solution that allows users to generate reports of interest to them, summarizing a variety of metrics that can be grouped according to useful parameters. The output of the toolkit can be used for real-time dose monitoring or scheduled reporting, such as to a quality assurance committee. Making dose parameter data more accessible and more meaningful to the user promotes dose reduction efforts such as regular protocol review and optimization, and ultimately improves patient care by decreasing unnecessary radiation exposure.

MO-F-16A-06: Implementation of a Radiation Exposure Monitoring System for Surveillance of Multi-Modality Radiation Dose Data

International Nuclear Information System (INIS)

Stewart, B; Kanal, K; Dickinson, R; Zamora, D

2014-01-01

Purpose: We have implemented a commercially available Radiation Exposure Monitoring System (REMS) to enhance the processes of radiation dose data collection, analysis and alerting developed over the past decade at our sites of practice. REMS allows for consolidation of multiple radiation dose information sources and quicker alerting than previously developed processes. Methods: Thirty-nine x-ray producing imaging modalities were interfaced with the REMS: thirteen computed tomography scanners, sixteen angiography/interventional systems, nine digital radiography systems and one mammography system. A number of methodologies were used to provide dose data to the REMS: Modality Performed Procedure Step (MPPS) messages, DICOM Radiation Dose Structured Reports (RDSR), and DICOM header information. Once interfaced, the dosimetry information from each device underwent validation (first 15–20 exams) before release for viewing by end-users: physicians, medical physicists, technologists and administrators. Results: Before REMS, our diagnostic physics group pulled dosimetry data from seven disparate databases throughout the radiology, radiation oncology, cardiology, electrophysiology, anesthesiology/pain management and vascular surgery departments at two major medical centers and four associated outpatient clinics. With the REMS implementation, we now have one authoritative source of dose information for alerting, longitudinal analysis, dashboard/graphics generation and benchmarking. REMS provides immediate automatic dose alerts utilizing thresholds calculated through daily statistical analysis. This has streamlined our Closing the Loop process for estimated skin exposures in excess of our institutional specific substantial radiation dose level which relied on technologist notification of the diagnostic physics group and daily report from the radiology information system (RIS). REMS also automatically calculates the CT size-specific dose estimate (SSDE) as well as provides

MO-F-16A-06: Implementation of a Radiation Exposure Monitoring System for Surveillance of Multi-Modality Radiation Dose Data

Energy Technology Data Exchange (ETDEWEB)

Stewart, B; Kanal, K; Dickinson, R; Zamora, D [University Washington, Seattle, WA (United States)

2014-06-15

Purpose: We have implemented a commercially available Radiation Exposure Monitoring System (REMS) to enhance the processes of radiation dose data collection, analysis and alerting developed over the past decade at our sites of practice. REMS allows for consolidation of multiple radiation dose information sources and quicker alerting than previously developed processes. Methods: Thirty-nine x-ray producing imaging modalities were interfaced with the REMS: thirteen computed tomography scanners, sixteen angiography/interventional systems, nine digital radiography systems and one mammography system. A number of methodologies were used to provide dose data to the REMS: Modality Performed Procedure Step (MPPS) messages, DICOM Radiation Dose Structured Reports (RDSR), and DICOM header information. Once interfaced, the dosimetry information from each device underwent validation (first 15–20 exams) before release for viewing by end-users: physicians, medical physicists, technologists and administrators. Results: Before REMS, our diagnostic physics group pulled dosimetry data from seven disparate databases throughout the radiology, radiation oncology, cardiology, electrophysiology, anesthesiology/pain management and vascular surgery departments at two major medical centers and four associated outpatient clinics. With the REMS implementation, we now have one authoritative source of dose information for alerting, longitudinal analysis, dashboard/graphics generation and benchmarking. REMS provides immediate automatic dose alerts utilizing thresholds calculated through daily statistical analysis. This has streamlined our Closing the Loop process for estimated skin exposures in excess of our institutional specific substantial radiation dose level which relied on technologist notification of the diagnostic physics group and daily report from the radiology information system (RIS). REMS also automatically calculates the CT size-specific dose estimate (SSDE) as well as provides

Wireless remote radiation monitoring system (WRRMS). Innovative technology summary report

International Nuclear Information System (INIS)

1998-12-01

The Science Application International Corporation (SAIC) RadStar trademark wireless remote radiation monitoring system (WRRMS) is designed to provide real-time monitoring of the radiation dose to workers as they perform work in radiologically contaminated areas. WRRMS can also monitor dose rates in a room or area. The system uses radio-frequency communications to transmit dose readings from the wireless dosimeters worn by workers to a remote monitoring station that can be located out of the contaminated area. Each base station can monitor up to 16 workers simultaneously. The WRRMS can be preset to trigger both audible and visual alarms at certain dose rates. The alarms are provided to the worker as well as the base station operator. This system is particularly useful when workers are wearing personal protective clothing or respirators that make visual observation of their self-reading dosimeters (SRDs), which are typically used to monitor workers, more difficult. The base station is an IBM-compatible personal computer that updates and records information on individual workers every ten seconds. Although the equipment costs for this improved technology are higher than the SRDs (amortized at $2.54/hr versus $1.02/hr), total operational costs are actually less ($639/day versus $851/day). This is because the WRRMS requires fewer workers to be in the contaminated zone than the traditional (baseline) technology. There are also intangible benefits associated with improved worker safety and as low as reasonably achievable (ALARA) principles, making the WRRMS an attractive alternative to the baseline technology. The baseline technology measures only integrated dose and requires workers to check their own dosimeters manually during the task

Wireless remote radiation monitoring system (WRRMS). Innovative technology summary report

Energy Technology Data Exchange (ETDEWEB)

1998-12-01

The Science Application International Corporation (SAIC) RadStar{trademark} wireless remote radiation monitoring system (WRRMS) is designed to provide real-time monitoring of the radiation dose to workers as they perform work in radiologically contaminated areas. WRRMS can also monitor dose rates in a room or area. The system uses radio-frequency communications to transmit dose readings from the wireless dosimeters worn by workers to a remote monitoring station that can be located out of the contaminated area. Each base station can monitor up to 16 workers simultaneously. The WRRMS can be preset to trigger both audible and visual alarms at certain dose rates. The alarms are provided to the worker as well as the base station operator. This system is particularly useful when workers are wearing personal protective clothing or respirators that make visual observation of their self-reading dosimeters (SRDs), which are typically used to monitor workers, more difficult. The base station is an IBM-compatible personal computer that updates and records information on individual workers every ten seconds. Although the equipment costs for this improved technology are higher than the SRDs (amortized at $2.54/hr versus $1.02/hr), total operational costs are actually less ($639/day versus $851/day). This is because the WRRMS requires fewer workers to be in the contaminated zone than the traditional (baseline) technology. There are also intangible benefits associated with improved worker safety and as low as reasonably achievable (ALARA) principles, making the WRRMS an attractive alternative to the baseline technology. The baseline technology measures only integrated dose and requires workers to check their own dosimeters manually during the task.

Distributed Radiation Monitoring System for Linear Accelerators based on CAN Bus

CERN Document Server

Kozak, T; Napieralski, A

2010-01-01

Abstract—Gamma and neutron radiation is produced during the normal operation of linear accelerators like Free-Electron Laser in Hamburg (FLASH) or X-ray Free Electron Laser (X-FEL). Gamma radiation cause general degeneration of electronics devices and neutron fluence can be a reason of soft error in memories and microcontrollers. X-FEL accelerator will be built only in one tunnel, therefore most of electronic control systems will be placed in radiation environment. Exposing control systems to radiation may lead to many errors and unexpected failure of the whole accelerator system. Thus, the radiation monitoring system able to monitor radiation doses produced near controlling systems is crucial. Knowledge of produced radiation doses allows to detect errors caused by radiation, make plans of essential exchange of control systems and prevent accelerator from serious damages. The paper presents the project of radiation monitoring system able to monitor radiation environment in real time.

A national computerized system for monitoring operational radiation exposure

International Nuclear Information System (INIS)

Canipelle, A.D.

1996-01-01

In parallel to the expansion of the number of French nuclear power plant units in operation, maintenance actions have multiplied, which has meant calling upon the services of a growing number of increasingly specialized workers. It has therefore proved necessary to reinforce the radiation dose rate surveillance of these workers. As a result, certain companies decided to set up their own occupational radiation dose monitoring system, in addition to mandatory monitoring by the OPRI, using dosemeters, generally electronic or thermoluminescent film badges, supplied by the subcontractor companies or nuclear facility operators. This enables acquiring fast and accurate knowledge of the radiation doses received by the workers. For this type of surveillance to be fully efficient, a data centralization system was required, able to provide frequent, even daily readings if necessary, of the dose received during the current month or for any period of time, up to the sum of the doses accumulated over five years. (author)

RTP Radiation Monitoring System

International Nuclear Information System (INIS)

Alfred, S.L.; Mohd Fairus Abdul Farid; Ahmad Nabil Abdul Rahim; Nurhayati Ramli

2015-01-01

Radiation Monitoring System aiming to limiting dose exposed to personnel to the lowest level referring to the concept of ALARA (As Low As Reasonably Achievable). Atomic Energy Licensing (Basic Safety Radiation Protection) Regulation 2010 (Act 304) is a baseline to control employee and public radiation protection program and guideline, as well as to meet the requirement of the Occupational Safety and Health 1994 (Act 514). (author)

Development of air equivalent gamma dose monitor

International Nuclear Information System (INIS)

Alex, Mary; Bhattacharya, Sadhana; Karpagam, R.; Prasad, D.N.; Jakati, R.K.; Mukhopadhyay, P.K.; Patil, R.K.

2010-01-01

The paper describes design and development of air equivalent gamma absorbed dose monitor. The monitor has gamma sensitivity of 84 pA/R/h for 60 Co source. The characterization of the monitor has been done to get energy dependence on gamma sensitivity and response to gamma radiation field from 1 R/hr to 5000 R/hr. The gamma sensitivity in the energy range of 0.06 to 1.25MeV relative to 137 Cs nuclide was within 2.5%. The linearity of the monitor response as a function of gamma field from 10 R/h to 3.8 kR/h was within 6%. The monitor has been designed for its application in harsh environment. It has been successfully qualified to meet environmental requirements of shock. (author)

Design of a tracking device for on-line dose monitoring in hadrontherapy

Energy Technology Data Exchange (ETDEWEB)

Battistoni, G. [INFN Sezione di Milano, Milano (Italy); Collamati, F.; De Lucia, E. [Laboratori Nazionali di Frascati dell' INFN, Frascati (Italy); Faccini, R. [Dipartimento di Fisica, “La Sapienza” Università di Roma, Roma (Italy); INFN Sezione di Roma, Roma (Italy); Marafini, M. [INFN Sezione di Roma, Roma (Italy); Museo Storico della Fisica e Centro Studi e Ricerche “E. Fermi”, Roma (Italy); Mattei, I. [INFN Sezione di Milano, Milano (Italy); Muraro, S., E-mail: silvia.muraro@mi.infn.it [INFN Sezione di Milano, Milano (Italy); Paramatti, R. [INFN Sezione di Roma, Roma (Italy); Patera, V. [INFN Sezione di Roma, Roma (Italy); Museo Storico della Fisica e Centro Studi e Ricerche “E. Fermi”, Roma (Italy); Dipartimento di Scienze di Base e Applicate per Ingegneria, “La Sapienza” Università di Roma, Roma (Italy); Pinci, D. [INFN Sezione di Roma, Roma (Italy); Rucinski, A. [INFN Sezione di Roma, Roma (Italy); Dipartimento di Scienze di Base e Applicate per Ingegneria, “La Sapienza” Università di Roma, Roma (Italy); Russomando, A. [Dipartimento di Fisica, “La Sapienza” Università di Roma, Roma (Italy); INFN Sezione di Roma, Roma (Italy); Center for Life Nano Science@Sapienza, Istituto Italiano di Tecnologia, Roma (Italy); and others

2017-02-11

Hadrontherapy is a technique for cancer treatment that exploits ion beams (mostly protons and carbons). A critical issue is the accuracy that is achievable when monitoring the dose released by the beam to the tumor and to the surrounding tissues. We present the design of a tracking device, developed in the framework of the INSIDE project , capable of monitoring in real time the longitudinal profile of the dose delivered in the patient. This is possible by detecting the secondary particles produced by the interaction of the beam in the tissues. The position of the Bragg peak can be correlated to the charged particles emission point distribution measurement. The tracking device will be able to provide a fast response on the dose pattern by tracking the secondary charged fragments. The tracks are detected using 6 planes of scintillating fibers, providing the 3D coordinates of the track intersection with each plane. The fibers planes are followed by a plastic scintillator and by a small calorimeter built with a pixelated Lutetium Fine Silicate (LFS) crystal. A complete detector simulation, followed by the event reconstruction, has been performed to determine the achievable monitoring spatial resolution. - Highlights: • On-line range monitoring in hadrontherapy. • New approach: detection of charged secondary particles escaping the patient. • Correlation of longitudinal emission profile of secondaries with the beam range. • New detector integrated in a multi-modal system to be tested in clinical operation.

Monitoring of eye lens doses in radiation protection

International Nuclear Information System (INIS)

Bordy, J.M.

2015-01-01

Mainly due to the ICRP recommendation to decrease the exposure limit for eye lenses, the eye lens dosimetry has to be reconsidered. This paper gives an overview of the issues raised after this recommendation; that is to say, the choice and definition of the operational quantity to be monitored, the type testing and calibration of dosimeters aimed at measuring eyes lens 'doses', the design of existing eye lens dosimeters and their wearing conditions. Finally, a criterion to choose between a direct measurement of the personal dose equivalent at three millimeters depth, H p (3), with a dedicated dosimeter, and an indirect evaluation of H p (3) through whole-body monitoring is presented. (authors)

SU-F-P-04: Implementation of Dose Monitoring Software: Successes and Pitfalls

Energy Technology Data Exchange (ETDEWEB)

Och, J [Geisinger Medical Center, Danville, PA (United States)

2016-06-15

Purpose: to successfully install a dose monitoring software (DMS) application to assist in CT protocol and dose management. Methods: Upon selecting the DMS, we began our implementation of the application. A working group composed of Medical Physics, Radiology Administration, Information Technology, and CT technologists was formed. On-site training in the application was supplied by the vendor. The decision was made to apply the process for all the CT protocols on all platforms at all facilities. Protocols were painstakingly mapped to the correct masters, and the system went ‘live’. Results: We are routinely using DMS as a tool in our Clinical Performance CT QA program. It is useful in determining the effectiveness of revisions to existing protocols, and establishing performance baselines for new units. However, the implementation was not without difficulty. We identified several pitfalls and obstacles which frustrated progress. Including: Training deficiencies, Nomenclature problems, Communication, DICOM variability. Conclusion: Dose monitoring software can be a potent tool for QA. However, implementation of the program can be problematic and requires planning, organization and commitment.

Development of a real-time extremity dose monitor for personnel in interventional radiology

International Nuclear Information System (INIS)

Ban, Nobuhiko; Kusama, Tomoko; Adachi, Akiko

2000-01-01

Protection of personnel in interventional radiology is one of the most important issues of radiological protection in medicine. Fluoroscopically guided interventional procedures require the operation near X-ray beam, which brings a considerable hand exposure to the operators. For the purpose of effectual control of their extremity doses, we have developed a real-time extremity dose monitor which is worn on a strap around the wrist. The monitor consists of a silicon semiconductor detector, thin lithium battery and a waterproof frame with a four-digit LED display. Experiment was carried out to examine a response of the monitor to diagnostic X-rays. A practical test was also performed to evaluate usability in the actual interventional procedures. In the experiment, the extremity dose monitor was placed on an arm phantom and exposed to diagnostic X-rays. Readings of the monitor were compared to those of Capintec PS-033 shallow chamber. The monitor was highly sensitive to diagnostic X-rays. It showed a linear response down to doses of a few tens of microsieverts. For high dose-rate exposure, however, a slight decrease in the response was observed, about 10% of counting loss for 80 kV, 40 mA X-ray at one meter from the focus. With regard to energy dependence, variation was within 20% for 60 to 100 kV X-rays. The monitor showed a good angular response in general, except lateral geometry facing the far side from a detector center. In the practical test, hand exposures of medical staff were measured with the extremity dose monitor. They were also asked to fill in a questionnaire regarding size and weight of the monitor, clarity of the display and usefulness. The subjects consisted of physicians, technicians and nurses who engaged in angiography, PTCD, CT-biopsy, barium enema and so on. The readings of the monitor were less than 1 mSv in most cases while 93 mSv was recorded in an extreme case due to direct-beam exposure. In some cases, TLD rings were used together with the

Development of a real-time extremity dose monitor for personnel in interventional radiology

Energy Technology Data Exchange (ETDEWEB)

Ban, Nobuhiko; Kusama, Tomoko [Oita University of Nursing and Health Sciences, Oita (Japan); Adachi, Akiko [Oita Medical University, Oita (JP)] [and others

2000-05-01

Protection of personnel in interventional radiology is one of the most important issues of radiological protection in medicine. Fluoroscopically guided interventional procedures require the operation near X-ray beam, which brings a considerable hand exposure to the operators. For the purpose of effectual control of their extremity doses, we have developed a real-time extremity dose monitor which is worn on a strap around the wrist. The monitor consists of a silicon semiconductor detector, thin lithium battery and a waterproof frame with a four-digit LED display. Experiment was carried out to examine a response of the monitor to diagnostic X-rays. A practical test was also performed to evaluate usability in the actual interventional procedures. In the experiment, the extremity dose monitor was placed on an arm phantom and exposed to diagnostic X-rays. Readings of the monitor were compared to those of Capintec PS-033 shallow chamber. The monitor was highly sensitive to diagnostic X-rays. It showed a linear response down to doses of a few tens of microsieverts. For high dose-rate exposure, however, a slight decrease in the response was observed, about 10% of counting loss for 80 kV, 40 mA X-ray at one meter from the focus. With regard to energy dependence, variation was within 20% for 60 to 100 kV X-rays. The monitor showed a good angular response in general, except lateral geometry facing the far side from a detector center. In the practical test, hand exposures of medical staff were measured with the extremity dose monitor. They were also asked to fill in a questionnaire regarding size and weight of the monitor, clarity of the display and usefulness. The subjects consisted of physicians, technicians and nurses who engaged in angiography, PTCD, CT-biopsy, barium enema and so on. The readings of the monitor were less than 1 mSv in most cases while 93 mSv was recorded in an extreme case due to direct-beam exposure. In some cases, TLD rings were used together with the

Upgrades of DARWIN, a dose and spectrum monitoring system applicable to various types of radiation over wide energy ranges

Science.gov (United States)

Sato, Tatsuhiko; Satoh, Daiki; Endo, Akira; Shigyo, Nobuhiro; Watanabe, Fusao; Sakurai, Hiroki; Arai, Yoichi

2011-05-01

A dose and spectrum monitoring system applicable to neutrons, photons and muons over wide ranges of energy, designated as DARWIN, has been developed for radiological protection in high-energy accelerator facilities. DARWIN consists of a phoswitch-type scintillation detector, a data-acquisition (DAQ) module for digital waveform analysis, and a personal computer equipped with a graphical-user-interface (GUI) program for controlling the system. The system was recently upgraded by introducing an original DAQ module based on a field programmable gate array, FPGA, and also by adding a function for estimating neutron and photon spectra based on an unfolding technique without requiring any specific scientific background of the user. The performance of the upgraded DARWIN was examined in various radiation fields, including an operational field in J-PARC. The experiments revealed that the dose rates and spectra measured by the upgraded DARWIN are quite reasonable, even in radiation fields with peak structures in terms of both spectrum and time variation. These results clearly demonstrate the usefulness of DARWIN for improving radiation safety in high-energy accelerator facilities.

Upgrades of DARWIN, a dose and spectrum monitoring system applicable to various types of radiation over wide energy ranges

International Nuclear Information System (INIS)

Sato, Tatsuhiko; Satoh, Daiki; Endo, Akira; Shigyo, Nobuhiro; Watanabe, Fusao; Sakurai, Hiroki; Arai, Yoichi

2011-01-01

A dose and spectrum monitoring system applicable to neutrons, photons and muons over wide ranges of energy, designated as DARWIN, has been developed for radiological protection in high-energy accelerator facilities. DARWIN consists of a phoswitch-type scintillation detector, a data-acquisition (DAQ) module for digital waveform analysis, and a personal computer equipped with a graphical-user-interface (GUI) program for controlling the system. The system was recently upgraded by introducing an original DAQ module based on a field programmable gate array, FPGA, and also by adding a function for estimating neutron and photon spectra based on an unfolding technique without requiring any specific scientific background of the user. The performance of the upgraded DARWIN was examined in various radiation fields, including an operational field in J-PARC. The experiments revealed that the dose rates and spectra measured by the upgraded DARWIN are quite reasonable, even in radiation fields with peak structures in terms of both spectrum and time variation. These results clearly demonstrate the usefulness of DARWIN for improving radiation safety in high-energy accelerator facilities.

Characteristics of Noble Gas-filled Ionization Chambers for a Low Dose Rate Monitoring

International Nuclear Information System (INIS)

Kim, Han Soo; Park, Se Hwan; Ha, Jan Ho; Lee, Jae Hyung; Lee, Nam Ho; Kim, Jung Bok; Kim, Yong Kyun; Kim, Do Hyun; Cho, Seung Yeon

2007-01-01

An ionization chamber is still widely used in fields such as an environmental radiation monitoring, a Radiation Monitoring System (RMS) in nuclear facilities, and an industrial application due to its operational stability for a long period and its designs for its applications. Ionization chambers for RMS and an environmental radiation monitoring are requested to detect a low dose rate at as low as 10-2 mR/h and several 3R/h, respectively. Filling gas and its pressure are two of the important factors for an ionization chamber development to use it in these fields, because these can increase the sensitivity of an ionization chamber. We developed cylindrical and spherical ionization chambers for a low dose rate monitoring. Response of a cylindrical ionization chamber, which has a 1 L active volume, was compared when it was filled with Air, Ar, and Xe gas respectively. Response of a spherical ionization chamber was also compared in the case of 9 atm and 25 atm filling-pressures. An inter-comparison with a commercially available high pressure Ar ionization chamber and a fabricated ionization chamber was also performed. A High Pressure Xenon (HPXe) ionization chamber, which was configured with a shielding mesh to eliminate an induced charge of positive ions, was fabricated both for the measurement of an environmental dose rate and for the measurement of an energy spectrum

Radioactive source monitoring system based on RFID and GPRS

International Nuclear Information System (INIS)

He Haiyang; Zhou Hongliang; Zhang Hongjian; Zhang Sheng; Zhou Junru; Weng Guojie

2011-01-01

Nuclear radiation produced by radioactive source is harmful to the health of human body, and the lost and theft of radioactive source will cause environmental pollution and social panic. In order to solve the abnormal leaks, accidental loss, theft and other problems of the radioactive source, a radioactive source monitoring system based on RFID, GPS, GPRS and GSM technology is put forward. Radiation dose detector and GPS wireless location module are used to obtain the information of radiation dose and location respectively, RFID reader reads the status of a tag fixed on the bottom of the radioactive source. All information is transmitted to the remote monitoring center via GPRS wireless transmission. There will be an audible and visual alarm when radiation dose is out of limits or the state of radioactive source is abnormal, and the monitoring center will send alarming text messages to the managers through GSM Modem at the same time. Thus, the functions of monitoring and alarming are achieved. The system has already been put into operation and is being kept in functional order. It can provide stable statistics as well as accurate alarm, improving the supervision of radioactive source effectively. (authors)

Development of web based system for internal monitoring programme

Energy Technology Data Exchange (ETDEWEB)

Lima, Vanessa R. de; Rodrigues Junior, Orlando; Todo, Alberto S. [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)]. E-mail: vrlima@ipen.br; rodrijr@ipen.br; astodo@ipen.br

2007-07-01

The purposes of monitoring in general are to verify and to document that each worker is protected adequately against risks from radionuclide intakes and the protection complies with legal requirements. Therefore, it forms part of the overall radiation protection programme, which starts with an assessment to identify work situations in which there is a risk of internal contamination of workers and to quantify the likely intake of radioactive material and the resulting committed effective dose. As a part of a continuous improvement of the monitoring programme for occupationally exposed workers at IPEN, it is being developed a Web based system to access the internal dosimetry database. The system was implemented using Hypertext Preprocessor, PHP, and a PostgreSQL database. This system will introduce a new paradigm in the routine of the internal dosimetry service, providing a fast access to the information among the measurement laboratories staff, dose evaluation group and the radiation protection supervisor. The database maintains information about worker identification, physical and chemical characteristics of the radionuclide, type of monitoring, measurement data and the dose. Moreover, this information will be readily available to provide support for regulatory compliance and quality control requirements. (author)

Monitoring the eye lens: which dose quantity is adequate?

International Nuclear Information System (INIS)

Behrens, R; Dietze, G

2010-01-01

Recent epidemiological studies suggest a rather low dose threshold (below 0.5 Gy) for the induction of a cataract of the eye lens. Some other studies even assume that there is no threshold at all. Therefore, protection measures have to be optimized and current dose limits for the eye lens may be reduced in the future. The question of which personal dose equivalent quantity is appropriate for monitoring the dose to the eye lens arises from this situation. While in many countries dosemeters calibrated in terms of the dose equivalent quantity H p (0.07) have been seen as being adequate for monitoring the dose to the eye lens, this might be questionable in the case of reduced dose limits and, thus, it may become necessary to use the dose equivalent quantity H p (3) for this purpose. To discuss this question, the dose conversion coefficients for the equivalent dose of the eye lens (in the following eye lens dose) were determined for realistic photon and beta radiation fields and compared with the values of the corresponding conversion coefficients for the different operational quantities. The values obtained lead to the following conclusions: in radiation fields where most of the dose comes from photons, especially x-rays, it is appropriate to use dosemeters calibrated in terms of H p (0.07) on a slab phantom, while in other radiation fields (dominated by beta radiation or unknown contributions of photon and beta radiation) dosemeters calibrated in terms of H p (3) on a slab phantom should be used. As an alternative, dosemeters calibrated in terms of H p (0.07) on a slab phantom could also be used; however, in radiation fields containing beta radiation with the end point energy near 1 MeV, an overestimation of the eye lens dose by up to a factor of 550 is possible.

The D1 method: career dose estimation from a combination of historical monitoring data and a single year's dose data

International Nuclear Information System (INIS)

Sont, W.N.

1995-01-01

A method is introduced to estimate career doses from a combination of historical monitoring data and a single year's dose data. This method, called D1 eliminates the bias arising from incorporating historical dose data from times when occupational doses were generally much higher than they are today. Doses calculated by this method are still conditional on the preservation of the status quo in the effectiveness of radiation protection. The method takes into account the variation of the annual dose, and of the probability of being monitored, with the time elapsed since the start of a career. It also allows for the calculation of a standard error of the projected career dose. Results from recent Canadian dose data are presented. (author)

Characteristics and verification of a car-borne survey system for dose rates in air: KURAMA-II

International Nuclear Information System (INIS)

Tsuda, S.; Yoshida, T.; Tsutsumi, M.; Saito, K.

2015-01-01

The car-borne survey system KURAMA-II, developed by the Kyoto University Research Reactor Institute, has been used for air dose rate mapping after the Fukushima Dai-ichi Nuclear Power Plant accident. KURAMA-II consists of a CsI(Tl) scintillation detector, a GPS device, and a control device for data processing. The dose rates monitored by KURAMA-II are based on the G(E) function (spectrum-dose conversion operator), which can precisely calculate dose rates from measured pulse-height distribution even if the energy spectrum changes significantly. The characteristics of KURAMA-II have been investigated with particular consideration to the reliability of the calculated G(E) function, dose rate dependence, statistical fluctuation, angular dependence, and energy dependence. The results indicate that 100 units of KURAMA-II systems have acceptable quality for mass monitoring of dose rates in the environment. - Highlights: • KURAMA-II is a car-borne survey system developed by Kyoto University. • A spectrum-dose conversion operator for KURAMA-II was calculated and examined. • We examined the radiation characteristics of KURAMA-II such as energy dependence. • KURAMA-II has acceptable quality for environmental mass dose rate monitoring

Radiation monitoring system for astronauts

International Nuclear Information System (INIS)

Thomson, I.; MacKay, G.; Ng, A.; Tomi, L.

1996-01-01

Astronauts in space are constantly under the bombardment of radiation particles from trapped electrons, and trapped proton. In addition, cosmic rays, while penetrating the spacecraft shell, generate secondary radiation of neutrons. As astronauts' stay in space is getting longer, the need for a real-time radiation monitoring device has become critical. Thermoluminescent dosemeter (TLD), used onboard both the MIR and the Space Transportation System (STS), cannot provide real-time dose reading. This paper describes a real-time direct read-out device, currently under development, which can measure skin, eye, and Blood Forming Organ (BFO) doses separately. (author)

Development of radiation monitoring and visualization systems for Fukushima. GPS monitoring system, Dose3DMap system, and LED-coupled scintillating fiber detector

International Nuclear Information System (INIS)

Nakao, Noriaki; Kosako, Kazuaki; Kinoshita, Norikazu; Kawaguchi, Masato

2016-01-01

Lands that were contaminated with radioactive elements following the Fukushima Daiichi Nuclear Power Plant accident in 2011 have been decontaminated, and the construction of an interim storage facility for radioactive waste is planned. A GPS monitoring system was developed to concomitantly determine a location and measure the radiation level at the location. Moreover, a mapping system that produces radiation maps at the measurement locations and also predicts post-decontamination radiation maps using the compiled Monte Carlo simulation program was constructed. These systems were used for decontamination planning and estimation of the decontamination effect. An LED-coupled scintillating fiber detector was developed for visually monitoring radiation in real time at the interim storage facility. The LEDs display different colors corresponding to different radiation levels at the measurement locations along the fiber detector, the maximum length of which is 50 m. Thus, the radiation levels at all positions along the length of the detector can be visually monitored in real time. Moreover, it is useful for radiation safety and for risk communication with radiation workers and residents close to the site. (author)

A real-time virtual delivery system for photon radiotherapy delivery monitoring

Directory of Open Access Journals (Sweden)

Feng Shi

2014-03-01

Full Text Available Purpose: Treatment delivery monitoring is important for radiotherapy, which enables catching dosimetric error at the earliest possible opportunity. This project develops a virtual delivery system to monitor the dose delivery process of photon radiotherapy in real-time using GPU-based Monte Carlo (MC method.Methods: The simulation process consists of 3 parallel CPU threads. A thread T1 is responsible for communication with a linac, which acquires a set of linac status parameters, e.g. gantry angles, MLC configurations, and beam MUs every 20 ms. Since linac vendors currently do not offer interface to acquire data in real time, we mimic this process by fetching information from a linac dynalog file at the set frequency. Instantaneous beam fluence map (FM is calculated based. A FM buffer is also created in T1 and the instantaneous FM is accumulated to it. This process continues, until a ready signal is received from thread T2 on which an in-house developed MC dose engine executes on GPU. At that moment, the accumulated FM is transferred to T2 for dose calculations, and the FM buffer in T1 is cleared. Once the dose calculation finishes, the resulting 3D dose distribution is directed to thread T3, which displays it in three orthogonal planes in color wash overlaid on the CT image. This process continues to monitor the 3D dose distribution in real-time.Results: An IMRT and a VMAT cases used in our patient-specific QA are studied. Maximum dose differences between our system and treatment planning system are 0.98% and 1.58% for the IMRT and VMAT cases, respectively. The update frequency is >10Hz and the relative uncertainty level is 2%.Conclusion: By embedding a GPU-based MC code in a novel data/work flow, it is possible to achieve real-time MC dose calculations to monitor delivery process.------------------------------Cite this article as: Shi F, Gu X, Graves YJ, Jiang S, Jia X. A real-time virtual delivery system for photon radiotherapy delivery

Web system for dosimetric data management of internal monitoring programme at IPEN

International Nuclear Information System (INIS)

Lima, Vanesa R. de; Rodriguez Junior, Orlando; Todo, Alberto S.

2008-01-01

Full text: The internal monitoring programme are carried out for the occupationally exposed workers that develop activities in the radioisotope production plant, fuel cycle facilities, waste management installations, cyclotron and the reactor facility at Institute of Nuclear Energy and Research (IPEN). According to the National Nuclear Energy Commission (CNEN), Regulation NN-3.01, the dose of each worker should be maintained at least for a period of 30 years. With this purpose, an online system, called 'IntDosWeb', was developed with the objective of the management for data dosimetric of internal monitoring programme. The system IntDosWeb, based on free software, was developed in programming language PHP and environment database PostgreSQL. This system is to be available at the local net, Intranet. The database maintains information about identification of the worker that handles non-sealed radioactive sources, physical and chemical characteristics of the radionuclides, monitoring types, measurement data and the dose. This system is able to generate annual reports of the individuals and the historical dose. Several simulation cases have been put into effect to check the on-line software functional capabilities. The users can access the dosimetric information according to following database field: monitoring period, monitoring type, intake pattern, radionuclide type and monitoring data from a specific installation or from each worker. The system was tested in the routinely service of internal dosimetry at IPEN. The rastreability of the information made in the internal monitoring programme was a success and also guaranteeing the reliability and integrity of the stored information. The IntDosWeb was shown as a helpful tool for analysis of the committed effective dose in the radiation protection programme, besides obeying the legal demands of the Brazilian Regulatory Commission. (author)

Bulk laundry monitoring system

International Nuclear Information System (INIS)

Thakur, Vaishali M.; Jain, Amit; Verma, Amit; Anilkumar, S.; Babu, D.A.R.; Sharma, D.N.; Rande, N.R.; Singh, B.N.

2012-01-01

Protective wear (like boiler suits, hand gloves etc.) is essential while handling radioactive material in plants/laboratories. During the course of work, it is quite possible that protective wear may get contaminated. These protective wears are packed in laundry bags and send to Decontamination Centre (DC). There is a need for monitoring the laundry bags at the time of receipt, as well as before dispatch to respective locations to comply with AERB guidelines, To avoid cross contamination during wash cycle, contaminated bags (> 0.5 mR/h on surface) need to be segregated. Present paper describes the development of such system for monitoring surface dose rate on bags at the time of receipt. The system installed at ETP after calibration, effectively segregates the contaminated bags from the rest and prevents from cross contamination during wash cycle. Reduction in man-rem consumption due to semi automatic monitoring. Improved sensitivity due to good geometry, long counting time, background and attenuation corrections. Optimum utilization of decontamination chemicals based on level of contamination and keeping track of its inventory. Generation of decontamination process data base for improvement

Design of readout electronics for BES III online dose rate monitoring and protection system

International Nuclear Information System (INIS)

Yang Shiming; Gong Guanghua; Shao Beibei; Li Jin

2006-01-01

To protect the beam pipe of BES III, Si PIN diodes will be used as detectors to monitor the dose rate level near the IP area. Analog to digital conversion is selected to read out the current signals of Si PIN diodes. Several low current amplifying and measuring methods are compared, mainly describing the theory of operation, software and hardware design and performance of the A/D conversion circuit. (authors)

Monitor units are not predictive of neutron dose for high-energy IMRT

Directory of Open Access Journals (Sweden)

Hälg Roger A

2012-08-01

Full Text Available Abstract Background Due to the substantial increase in beam-on time of high energy intensity-modulated radiotherapy (>10 MV techniques to deliver the same target dose compared to conventional treatment techniques, an increased dose of scatter radiation, including neutrons, is delivered to the patient. As a consequence, an increase in second malignancies may be expected in the future with the application of intensity-modulated radiotherapy. It is commonly assumed that the neutron dose equivalent scales with the number of monitor units. Methods Measurements of neutron dose equivalent were performed for an open and an intensity-modulated field at four positions: inside and outside of the treatment field at 0.2 cm and 15 cm depth, respectively. Results It was shown that the neutron dose equivalent, which a patient receives during an intensity-modulated radiotherapy treatment, does not scale with the ratio of applied monitor units relative to an open field irradiation. Outside the treatment volume at larger depth 35% less neutron dose equivalent is delivered than expected. Conclusions The predicted increase of second cancer induction rates from intensity-modulated treatment techniques can be overestimated when the neutron dose is simply scaled with monitor units.

Creation and clinical application of real-time dose monitor using dose area product meter

International Nuclear Information System (INIS)

Matsubara, Kosuke; Uoyama, Yoshinori; Iida, Hiroji; Mizushima, Takashi

2004-01-01

The management of patient dose has become more of an issue in recent years. Dose can be determined non-invasively and in real time through the use of a dose area product meter, but it is the area dose value that is obtained. Therefore, we created a program that estimates entrance skin dose (ESD) in real time from area dose values obtained during procedures. We used Microsoft Visual C++ 6.0 (Standard Edition) for the programming language and C language for the programming environment. The value was a maximum 285.4 mGy at ileus tube insertion when measuring ESD for radiography of the digestive organ and non-vascular type interventional radiology (IVR) using the created program and seeking the average according to the procedures. The program that we created can be considered valid for monitoring ESD correctly and in real time. (author)

SSDL quality assurance for environmental dose/dose rate monitoring of photon radiation

International Nuclear Information System (INIS)

1987-01-01

Member states of IAEA have recently approved an expanded Nuclear Safety Programme and two International Conventions have been signed. One concerns early notification of a nuclear accident, and the other concerns assistance in the case of a nuclear accident or radiological emergency. In the course of the implementation of these conventions an international system will be established by the Agency for the reception and dissemination of data following a nuclear accident. Such data should include the results of radiation measurements obtained by radiation monitoring. These data must be reliable, and comparable. This assures that numerical values of measured quantities obtained at different times, sites and countries, and with different instruments, can be compared in order that the competent authorities may draw conclusions. Such measurements may also have legal consequences. This implies that the instruments used for the measurement should comply with the relevant international specifications, and that the readings of these instruments be traceable to the international measurement system. At a meeting of an expert working group on International Cooperation in Nuclear Safety and Radiation Protection held in November 1986, a proposal to produce a technical document on ''The role of SSDLs in the quality assurance programme relating to the use of dose and dose rate meters for personal and environmental measurements'' received high priority, and at a subsequent meeting of the Board of Governors the proposal was approved. Prior to these proposals the SSDL Scientific Committee at its annual meeting in May 1986 also advised the IAEA to promote measures to ensure world wide reliability and traceability of dose measurements in the field of radiation protection. On 26-30 January 1987 an Advisory Group Meeting on ''The role of SSDLs in the dosimetry of unintentional radiation exposures'' was organized by the IAEA. This Advisory Group assisted the Agency in the formulation of a

Status of eye lens radiation dose monitoring in European hospitals

International Nuclear Information System (INIS)

Carinou, Eleftheria; Ginjaume, Merce; O’Connor, Una; Kopec, Renata; Sans Merce, Marta

2014-01-01

A questionnaire was developed by the members of WG12 of EURADOS in order to establish an overview of the current status of eye lens radiation dose monitoring in hospitals. The questionnaire was sent to medical physicists and radiation protection officers in hospitals across Europe. Specific topics were addressed in the questionnaire such as: knowledge of the proposed eye lens dose limit; monitoring and dosimetry issues; training and radiation protection measures. The results of the survey highlighted that the new eye lens dose limit can be exceeded in interventional radiology procedures and that eye lens protection is crucial. Personnel should be properly trained in how to use protective equipment in order to keep eye lens doses as low as reasonably achievable. Finally, the results also highlighted the need to improve the design of eye dosemeters in order to ensure satisfactory use by workers. (paper)

Low dose monitoring by double implant technique in IC fabrication

International Nuclear Information System (INIS)

Ahmad, I.B.; Weidemann, J.

1995-01-01

The utilisation of low dose implant monitoring (using Boron) in a manufacturing line has been discussed. The utilisation of phosphorus ions as the second implant dose were also studied as comparison. The technique relies on the fact that the sheet resistant of doped layer will increase significantly when damaged by relatively low implant dose. The technique is very sensitive and applicable for adjusting the channel dose so that an accurate threshold voltage in MOS device could be achieved

Area monitoring of ambient dose rates in parts of South-Western Nigeria using a GPS-integrated radiation survey meter

International Nuclear Information System (INIS)

Okeyode, I.C.; Rabiu, J.A.; Alatise, O.O.; Makinde, V.; Akinboro, F.G.; Mustapha, A.O.; Al-Azmi, D.

2017-01-01

A radiation monitoring system comprising a Geiger-Muller counter connected to a smart phone via Bluetooth was used for a dose rate survey in some parts of south-western Nigeria. The smart phone has the Geographical Positioning System, which provides the navigation information and saves it along with the dose rate data. A large number of data points was obtained that shows the dose rate distribution within the region. The results show that the ambient dose rates in the region range from 60 to 520 nSv -1 and showed a bias that is attributable to the influence of geology on the ambient radiation dose in the region. The geology influence was demonstrated by superimposing the dose rate plot and the geological map of the area. The potential applications of the device in determining baseline information and in area monitoring, e.g. for lost or abandoned sources, radioactive materials stockpiles, etc., were discussed in the article, particularly against the background of Nigeria's plan to develop its nuclear power program. (authors)

Development of Web based system for individual internal monitoring programme

International Nuclear Information System (INIS)

Lima, Vanessa Rogeria de

2007-01-01

The purposes of the internal monitoring, in general, are to verify and document that each worker is protected adequately against risks from radionuclide intakes and the protection complies with legal requirements. Therefore, an overall radiation protection programme, starts with an assessment to identify work situations in which there is a risk of internal contamination of workers and to quantify the likely intake of radioactive material and the resulting committed effective dose. As a part of a continuous improvement of the monitoring programme for occupationally exposed workers at IPEN, it is being developed a Web based system to access the internal dosimetry database. The system was implemented using Hypertext Preprocessor, PHP, and a PostgreSQL database. This system will introduce a new paradigm in the routine of the internal dosimetry service, providing a fast access to the information among the measurement laboratories staff, dose evaluation group and the radiation protection supervisor. The database maintains information about worker identification, physical and chemical characteristics of the radionuclide, type of monitoring, measurement data and the dose. Moreover, this information will be readily available to provide support for regulatory compliance and quality control requirements. (author)

Centralized environmental radiation monitoring system in JAERI

International Nuclear Information System (INIS)

Katagiri, H.; Kobalyashi, H.

1993-01-01

JAERI has continued the environmental radiation background survey and monitoring to ensure the safety of the peoples around the institute since one year before the first criticality of JRR-1 (Japan Research Reactor No.1) in August 1957. Air absorbed doses from β and γ radiation, α and β radioactivity in air and the radioactivities in environmental samples were the monitoring items. For the monitoring of β and γ radiation and α and β radioactivity in air, monitoring station and the centralized automatic environmental radiation monitoring system applying a computer were established as a new challenging monitoring system for nuclear facility, which was the first one not only in Japan but also in the would in 1960 and since then the system has been renewed two times (in 1973 and 1988) by introducing the latest technology in the fields of radiation detection and computer control at each stage. Present system renewed in 1988 was designed to prevent the interruption of monitoring due to computer troubles, communication troubles and power failures especially an instant voltage drop arisen from thunder by reflecting the experiences through the operation and maintenance of the former system. Dual telemeters whose power is constantly supplied via batteries (capable of 10 min monitoring after power failure) are equipped in the monitoring center to cope with telemeter troubles, which has operated successfully without any suspension being attributable to the power failures and telemeter troubles

Radiation monitoring and beam dump system of the OPAL silicon microvertex detector

CERN Document Server

Braibant, S

1997-01-01

The OPAL microvertex silicon detector radiation monitoring and beam dump system is described. This system was designed and implemented in order to measure the radiation dose received at every beam crossing and to induce a fast beam dump if the radiation dose exceeds a given threshold.

Two years experience with a computer-assisted monitoring and recording system used in gynecological afterloading therapy

International Nuclear Information System (INIS)

Kaulich, T.W.; Boedi, R.; Nuesslin, F.; Hirnle, P.

1990-01-01

A computer program running on a simple desk-calculator has been developed for monitoring and recording gynecological high-dose afterloading therapy. For treatment monitoring the multiple-probe AM6-system (PTW-Freiburg) is used which allows for dose measurements in the urinary bladder and the rectum. The probe signals are processed on line in order to indicate the actual dose at the measuring points. After completing the irradiation the treatment is documented. Performing fractionated treatment the measuring data are stored in the computer memory for calculating total accumulated dose. The above-described monitoring- and protocolling system has proven its usefulness during two years of clinical work. (orig.) [de

Positron emission tomography for the dose monitoring of intra-fractionally moving targets in ion beam therapy

International Nuclear Information System (INIS)

Stuetzer, Kristin

2014-01-01

Ion beam therapy (IBT) is a promising treatment option in radiotherapy. The characteristic physical and biological properties of light ion beams allow for the delivery of highly tumor conformal dose distributions. Related to the sparing of surrounding healthy tissue and nearby organs at risk, it is feasible to escalate the dose in the tumor volume to reach higher tumor control and survival rates. Remarkable clinical outcome was achieved with IBT for radio-resistant, deep-seated, static and well fixated tumor entities. Presumably, more patients could benefit from the advantages of IBT if it would be available for more frequent tumor sites. Those located in the thorax and upper abdominal region are commonly subjected to intra-fractional, respiration related motion. Different motion-compensated dose delivery techniques have been developed for active field shaping with scanned pencil beams and are at least available under experimental conditions at the GSI Helmholtzzentrum fuer Schwerionenforschung (GSI) in Darmstadt, Germany. Since minor unexpected anatomical changes e.g. related to patient mispositioning, tumour shrinkage or tissue swelling could already lead to remarkable deviations between planned and delivered dose distribution, a valuable dose monitoring system is desired for IBT. So far, positron emission tomography (PET) is the only in vivo, in situ and non-invasive qualitative dose monitoring method applied under clinical conditions. Conclusions about the delivered dose distribution can be drawn indirectly from a comparison between two β + -activity distributions: the measured one and an expected one generated by a Monte-Carlo simulation. Dedicated phantoms mainly made up of polymethyl methacrylate (PMMA) and a motion table for regular one-dimensional (1D) motion patterns have been designed and manufactured for the experiments. Furthermore, the general applicability of the 4D MLEM algorithm for more complex motion patterns has been demonstrated by the

Monitoring and radiation dose estimation for internal contamination of occupational workers

Energy Technology Data Exchange (ETDEWEB)

Kol, R; Laichter, Y [Israel Atomic Energy Commission, Beersheba (Israel). Nuclear Research Center-Negev

1996-12-01

The assessment of interval radiation doses due to intake of radionuclides differs totally from external dosimetry. External dosimetry is relatively straight forward: Workers are equipped with appropriate dosimeters that give the dose upon direct reading. Internal dosimetry is actually an assessment of the dose based on results of personnel and environmental monitoring (authors).

The wireless sensor network monitoring system for regional environmental nuclear radiation

International Nuclear Information System (INIS)

Liu Chong; Liu Dao; Wang Yaojun; Xie Yuxi; Song Lingling

2012-01-01

The wireless sensor network (WSN) technology has been utilized to design a new regional environmental radiation monitoring system based on the wireless sensor networks to meet the special requirements of monitoring the nuclear radiation in certain regions, and realize the wireless transmission of measurement data, information processing and integrated measurement of the nuclear radiation and the corresponding environmental parameters in real time. The system can be applied to the wireless monitoring of nuclear radiation dose in the nuclear radiation environment. The measured data and the distribution of radiation dose can be vividly displayed on the graphical interface in the host computer. The system has functioned with the wireless transmission and control, the data storage, the historical data inquiry, the node remote control. The experimental results show that the system has the advantages of low power consumption, stable performance, network flexibility, range of measurement and so on. (authors)

The current situation of personal dose monitoring in Chinese medicine radiation and undamaged detection

International Nuclear Information System (INIS)

Zhang Liangan; Zhang Wenyi; Yuan Shuyu; Song Shijun; Chang Hexin; Sun Kai

1993-01-01

The situation of personal dose monitoring in γ(X) external exposure in China is mainly outlined. Thermoluminescent dosimetry (TLD) was adopted for personal dose measurement of the radiation workers. The computer software and data base for the work have been developed and applied. National intercomparison of TLD, monitoring control of personal dose monitoring in field, and technical training were carried out for quality control. In China, the dominant occupational exposures is X-ray diagnosis and it increases year by year, the highest values is about 22.6%. The highest values of annual collective dose and annual average of individual dose (AAID) are 272.8 man·Sv and 3.21 mSv respectively. This work shows that the fraction of the population receiving high dose is decreased with time rapidly. The situation for whole occupational exposures is also described. (3 tabs.)

Development of the Guardian environmental monitoring system

International Nuclear Information System (INIS)

Gould, J.L.; Thompson, I.M.G.

1982-01-01

The report describes the Guardian Environmental Monitoring System, developed jointly by the CEGB's Berkeley Nuclear Laboratories (BNL) and GEC Energy Systems Limited (ESL). The basic battery operated instrument was developed by BNL for the measurement of any nuclear facility contribution to the overall environmental dose. It uses an energy compensated Geiger counter to provide a continuous record for over a month of dose rates from 1 μR h -1 (10nGy h -1 ). Results are presented of initial development trials and of an intercomparison with the USA Environmental Measurement Laboratory. The Guardian system, however, was developed, not only to meet the CEGB requirements for a recording monitor, but also to meet the requirements of US Regulatory Commission Guide RG 1.97, introduced as a result of the accident at Three Mile Island. This system, by using two energy compensated Geiger counters has a range from 1μRh -1 up to 10Rh -1 (approximately equal to 100mGyh -1 ), and the associated electronics provides automatic range changing, including fast response to ramp exposure rate changes, alarm and test facilities and telemetry by line or radio to a central station. (author)

Radiation doses in alternative commercial high-level waste management systems

International Nuclear Information System (INIS)

Schneider, K.J.; Pelto, P.J.; Lavender, J.C.; Daling, P.M.; Fecht, B.A.

1986-01-01

In the commercial high-level waste management system, potential changes are being considered that will augment the benefits of an integral monitored retrievable storage (MRS) facility. The US Department of Energy (DOE) has recognized that alternative options could be implemented in the authorized waste management system (i.e., without an integral MRS facility) to potentially achieve some of the same beneficial effects of the integral MRS system. This paper summarizes those DOE-sponsored analyses related to radiation doses resulting from changes in the waste management system. This report presents generic analyses of aggregated radiation dose impacts to the public and occupational workers, of nine postulated changes in the operation of a spent-fuel management system without an MRS facility

Contrast monitoring techniques in CT pulmonary angiography: An important and underappreciated contributor to breast dose

Energy Technology Data Exchange (ETDEWEB)

Mitchell, D.P., E-mail: dpmmitchell@gmail.com; Rowan, M., E-mail: mrowan@mater.ie; Loughman, E., E-mail: eloughman@mater.ie; Ridge, C.A., E-mail: cridge@mater.ie; MacMahon, P.J., E-mail: pmacmahon@mater.ie

2017-01-15

Objective: The aims of our study were to evaluate the contribution of contrast-monitoring techniques to breast dose in pregnant and non-pregnant women, and to investigate the effect of a reduced peak kilovoltage (kV) monitoring scan protocol on breast dose and Computed Tomography Pulmonary Angiography (CTPA) diagnostic quality. Materials and methods: Single center retrospective study of 221 female patients undergoing a reduced kV 80 kV contrast-monitoring CTPA protocol compared to 281 patients using the conventional 120 kV contrast-monitoring protocol (Siemens Somatom Definition AS + ). 99 pregnant patients analyzed separately. ImPACT dosimetry software was used to calculate dose. Group subsets were evaluated to assess CTPA diagnostic quality. Results: The contrast-monitoring component of a CTPA study constituted 27% of the overall breast dose when using a standard 120 kV protocol compared to only 7% of the overall breast dose in the 80 kV study group. The dose to the breast from the contrast-monitoring component alone was reduced by 79% in the non-pregnant patients (0.36mGy ± 0.37 versus 1.7mGy ± 1.02; p < 0.001), and by 88% in the pregnant population (0.25 mGy ± 0.67 versus 2.24mGy ± 1.61; p < 0.001). There was no statistical difference in CTPA diagnostic quality or timing. Conclusion: Despite a short scan length and relatively small DLP, contrast-monitoring techniques (test-bolus or bolus-tracked) set at 120 kV can account for 27% of the overall breast dose accrued from a CTPA study. By decreasing the kilovoltage of the contrast-monitoring component, a significant reduction in breast dose for pregnant and non-pregnant female patients can be achieved without affecting CTPA quality or timing.

Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

Energy Technology Data Exchange (ETDEWEB)

Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I. [National Institute of Cryogenics and Isotopes Technologies, Ramnicu Valcea (Romania)

2006-07-01

The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

Radiological safety system based on real-time tritium-in-air monitoring in room and effluents

International Nuclear Information System (INIS)

Bidica, N.; Sofalca, N.; Balteanu, O.; Stefan, I.

2006-01-01

The conceptual design of the radiological safety system based on real time-in-air monitoring in room and effluents is intended to provide the maximum achievable safety level, basing no the ALARA concept. the capabilities of this system are not only to inform any time personnel about tritium in air concentration level, but it will be able to: initiate the shut down procedure and drain off the plant, as well to start the Air cleaning System when the tritium-in-air concentration exceed pre-established threshold; estimate tritium effective dose rate before starting an activity into the monitored area, or during this activity, or soon as the activity was finished; estimate tritium effective dose and instantly record and update individual effective doses, using a special computer application called 'dose record'; lock access into the radiological area for individuals when tritium dose rate in the monitoring area will exceed the pre-established thresholds, or when any individual dose data provided by 'dose records' application ask for, or for other protection consideration; calculate the total tritium activity released to the environment (per day, week, or month). (N.C.)

Environmental monitoring system with TLD

International Nuclear Information System (INIS)

Aguerre, L.; Carelli, J.; Gregori, B.

2006-01-01

Presently work the methodology used by the Laboratory of Thermoluminescent Dosimetry (TLD) of the Nuclear Regulatory Authority (RNA) to gauge it system of environmental monitoring in function of the media absorbed dose rate in free air and the environmental dose equivalent, H * (10), according to the recommendation ICRU Report 47 is described. It was studied the response of the environmental dosemeter (DA) in fields of photonic radiation of energies W60, Wl 10, W200 and 137 Cs. The irradiations were carried out following the recommendations of the standard ISO:4037. It was analyzed the response in the DA of the detectors LiF: Mg, Ti and CaF 2 : Dy for the different radiation qualities and the relative response at 137 Cs of both. The methodology used in the evaluation of the dose includes: the correction of the readings of both detectors by fading, gotten experimentally, the witness of transfers, the energy answer and the value of the zero. The dose is calculated applying the average pondered in uncertainty of the dose obtained for each type of detector. Its were analyzed and calculated the uncertainties that affect to the measurement following the recommendation of the Argentine standard IRAM 35050. The detection limit of the absorbed dose rate in free air of this system it is 3.5 n Gy/h for a period of sampling of 3 months. With this detection limit environmental dose equivalent rates of the order of 70 n Sv/h are measured with an expanded uncertainty of the order of 10% with a cover factor k = 2. (Author)

The regulatory system of monitoring workers in Germany for intakes of radioactivity

International Nuclear Information System (INIS)

Dalheimer, A.; Henrichs, K.

1996-01-01

In Germany, the working group 'Incorporation Monitoring' of the German-Swiss Radiation Protection Association defined a new standard for the monitoring of workers occupationally exposed to radioactive material. During the last two years this draft has been accepted by the German government in the form of three guidelines. The purpose of the approach was the installation of a consistent state-of-the-art system: defining clear criteria for the necessity of routine and special monitoring programs, giving guidelines for monitoring programs ensuring that dose assessments are as reliable as necessary with the lowest possible expenses, standardizing as far as possible the procedures of dose assessments, and guaranteeing the necessary quality standards. The scientific basis of this regulatory system are the publications 30 and 54 of lCRP. (author)

Radiological safety system based on real-time tritium-in-air monitoring indoor and in effluents

International Nuclear Information System (INIS)

Bidica, Nicolae; Sofalca, Nicolae; Balteanu, Ovidiu-Ioan; Stefan, Ioana-Iuliana

2007-01-01

In this paper we describe an improved real-time tritium monitoring system designed for Heavy Water Detritiation Pilot Plant of National Institute for Cryogenics and Isotopes Separation, Rm. Valcea, Romania. The system consists of three fixed tritium-in-air monitors which measure continuously tritium-in-air concentration (in both species: vapour and gas) in working areas and gaseous effluents. Portable tritium monitors with ionization chamber, and tritium-in-air collector combined with liquid scintillation counter method are also used to supplement fixed instrument measurements. The main functions of tritium monitoring system are: to measure tritium-in air concentration in working areas and gaseous effluents; to alarm the personnel if tritium concentration thresholds are exceeded; to integrate tritium activity released to the environment during a week and to cut off normal ventilation when the activity threshold is exceeded and start the air cleaning system. Now, several especial functions have been added, so that by using appropriate conversion factors, the tritium monitoring system is able to estimate the effective dose rate before starting an activity into the monitored area, during this activity, or soon as the activity was finished. Another new function has been added by coupling tritium-in-air monitoring system with control access system. This is very useful for quick estimation of tritium doses. For routine dosimetric survey, one the internal dose for individuals by measuring tritium in urine is estimated. With all these features our tritium monitoring system is really a safety system for personnel and for environment. (authors)

Implementation of dose management system at radiation protection board of Ghana Atomic Energy Commission

International Nuclear Information System (INIS)

Hasford, F.; Amoako, J. K.; Darko, E. O.; Emi-reynolds, G.; Sosu, E. K.; Otoo, F.; Asiedu, G. O.

2012-01-01

The dose management system (DMS) is a computer software developed by the International Atomic Energy Agency for managing data on occupational exposure to radiation sources and intake of radionuclides. It is an integrated system for the user-friendly storage, processing and control of all existing internal and external dosimetry data. The Radiation Protection Board (RPB) of the Ghana Atomic Energy Commission has installed, customised, tested and using the DMS as a comprehensive DMS to improve personnel and area monitoring in the country. Personnel dose records from the RPBs database from 2000 to 2009 are grouped into medical, industrial and education/research sectors. The medical sector dominated the list of monitored institutions in the country over the 10 y period representing ∼87 %, while the industrial and education/research sectors represent ∼9 and ∼4 %, respectively. The number of monitored personnel in the same period follows a similar trend with medical, industrial and education/research sectors representing ∼74, ∼17 and ∼9 %, respectively. Analysis of dose data for 2009 showed that there was no instance of a dose above the annual dose limit of 20 mSv, however, 2.7 % of the exposed workers received individual annual doses >1 mSv. The highest recorded individual annual dose and total collective dose in all sectors were 4.73 mSv and 159.84 man Sv, respectively. Workers in the medical sector received higher individual doses than in the other two sectors, and average dose per exposed worker in all sectors is 0.25 mSv. (authors)

The importance of on-line monitoring systems within the environmental monitoring program of the Karlsruhe Nuclear Research Center

International Nuclear Information System (INIS)

Koenig, L.A.; Winter, M.; Schmitt, A.

1980-10-01

The two on-line monitoring systems used in KfK environmental monitoring should be taken as measures of accident precaution and they are restricted to measurement of gamma local dose rates and of the (β + γ)-radiation levels. One of the systems serves to monitor the KfK operational area, the second serves to monitor the surrounding communities up to a radius of 8 km. By use of two different types of detectors the first system covers a range of measurement of 10 μrem/h to 1000 rem/h. By the second system only increases in the radiation level can be detected. It allows to record accidents in which countermeasures must be taken very urgently. The two monitoring systems are described which have been operated and partly been developed at the KfK. The possibilities and limits of using them for environmental monitoring are discussed. (orig./HP) [de

Response of radiation monitors for ambient dose equivalent, H*(10)

International Nuclear Information System (INIS)

Grecco, Claudio Henrique dos Santos

2001-01-01

Radiation monitors are used all over the world to evaluate if places with presence of ionising radiation present safe conditions for people. Radiation monitors should be tested according to international or national standards in order to be qualified for use. This work describes a methodology and procedures to evaluate the energy and angular responses of any radiation monitor for ambient dose equivalent, H*(10), according to the recommendations of ISO and IEC standards. The methodology and the procedures were applied to the Monitor Inteligente de Radiacao MIR 7026, developed by the Instituto em Engenharia Nuclear (IEN), to evaluate and to adjust its response for H*(10), characterizing it as an ambient dose equivalent meter. The tests were performed at the Laboratorio Nacional de Metrologia das Radiacoes Ionizantes (LNMRI), at Instituto de Radioprotecao e Dosimetria (IRD), and results showed that the Monitor Inteligente de Radiacao MIR 7026 can be used as an EI*(10) meter, in accordance to the IEC 60846 standard requirements. The overall estimated uncertainty for the determination of the MIR 7026 response, in all radiation qualities used in this work, was 4,5 % to a 95 % confidence limit. (author)

Web based dosimetry system for reading and monitoring dose through internet access

International Nuclear Information System (INIS)

Perle, S.C.; Bennett, K.; Kahilainen, J.; Vuotila, M.

2010-01-01

The Instadose TM dosemeter from Mirion Technologies is a small, rugged device based on patented direct ion storage technology and is accredited by the National Voluntary Laboratory Accreditation Program (NVLAP) through NIST, bringing radiation monitoring into the digital age. Smaller than a flash drive, this dosemeter provides an instant read-out when connected to any computer with internet access and a USB connection. Instadose devices provide radiation workers with more flexibility than today's dosemeters. Non Volatile Analog Memory Cell surrounded by a Gas Filled Ion Chamber. Dose changes the amount of Electric Charge in the DIS Analog Memory. The total charge storage capacity of the memory determines the available dose range. The state of the Analog Memory is determined by measuring the voltage across the memory cell. AMP (Account Management Program) provides secure real time access to account details, device assignments, reports and all pertinent account information. Access can be restricted based on the role assignment assigned to an individual. A variety of reports are available for download and customizing. The Advantages of the Instadose dosemeter are: - Unlimited reading capability, - Concerns about a possible exposure can be addressed immediately, - Re-readability without loss of exposure data, with cumulative exposure maintained. (authors)

Web based dosimetry system for reading and monitoring dose through internet access

Energy Technology Data Exchange (ETDEWEB)

Perle, S.C.; Bennett, K.; Kahilainen, J.; Vuotila, M. [Mirion Technologies (United States); Mirion Technologies (Finland)

2010-07-01

The Instadose{sup TM} dosemeter from Mirion Technologies is a small, rugged device based on patented direct ion storage technology and is accredited by the National Voluntary Laboratory Accreditation Program (NVLAP) through NIST, bringing radiation monitoring into the digital age. Smaller than a flash drive, this dosemeter provides an instant read-out when connected to any computer with internet access and a USB connection. Instadose devices provide radiation workers with more flexibility than today's dosemeters. Non Volatile Analog Memory Cell surrounded by a Gas Filled Ion Chamber. Dose changes the amount of Electric Charge in the DIS Analog Memory. The total charge storage capacity of the memory determines the available dose range. The state of the Analog Memory is determined by measuring the voltage across the memory cell. AMP (Account Management Program) provides secure real time access to account details, device assignments, reports and all pertinent account information. Access can be restricted based on the role assignment assigned to an individual. A variety of reports are available for download and customizing. The Advantages of the Instadose dosemeter are: - Unlimited reading capability, - Concerns about a possible exposure can be addressed immediately, - Re-readability without loss of exposure data, with cumulative exposure maintained. (authors)

Accuracy of neutron dose evaluation in the area monitoring for LHD experiments

CERN Document Server

Yamanishi, H; Uda, T; Tanahashi, S; Saitou, M; Handa, H

2000-01-01

The error in the evaluation of neutron dose during calculation of the neutron field around the large helical device (LHD) in D-D operation is discussed. The expected neutron dose at each monitoring point was derived from the dose conversion factor and neutron fluence data, which was calculated with the radiation transport code DOT-3.5. In contrast, the detected dose at the neutron counter was obtained from the fluence data and the detector response given by calculation with MCNP-4b. The neutron counter used in these calculations consisted of a helium-3 proportional counter with a cylindrical polyethylene moderator. According to the results of the calculations, the ratio of the detected dose to the expected dose was found to lie in the range 1.0-3.0 on the outdoor monitoring points. Since the response of a single neutron counter may lead to inconsistencies in the dose conversion factor, we attempted to minimize these inconsistencies by using a pair of counters with moderators of different thickness. The ratio ...

Clinical evaluation of a dose monitoring software tool based on Monte Carlo Simulation in assessment of eye lens doses for cranial CT scans

Energy Technology Data Exchange (ETDEWEB)

Guberina, Nika; Suntharalingam, Saravanabavaan; Nassenstein, Kai; Forsting, Michael; Theysohn, Jens; Wetter, Axel; Ringelstein, Adrian [University Hospital Essen, Institute of Diagnostic and Interventional Radiology and Neuroradiology, Essen (Germany)

2016-10-15

The aim of this study was to verify the results of a dose monitoring software tool based on Monte Carlo Simulation (MCS) in assessment of eye lens doses for cranial CT scans. In cooperation with the Federal Office for Radiation Protection (Neuherberg, Germany), phantom measurements were performed with thermoluminescence dosimeters (TLD LiF:Mg,Ti) using cranial CT protocols: (I) CT angiography; (II) unenhanced, cranial CT scans with gantry angulation at a single and (III) without gantry angulation at a dual source CT scanner. Eye lens doses calculated by the dose monitoring tool based on MCS and assessed with TLDs were compared. Eye lens doses are summarized as follows: (I) CT angiography (a) MCS 7 mSv, (b) TLD 5 mSv; (II) unenhanced, cranial CT scan with gantry angulation, (c) MCS 45 mSv, (d) TLD 5 mSv; (III) unenhanced, cranial CT scan without gantry angulation (e) MCS 38 mSv, (f) TLD 35 mSv. Intermodality comparison shows an inaccurate calculation of eye lens doses in unenhanced cranial CT protocols at the single source CT scanner due to the disregard of gantry angulation. On the contrary, the dose monitoring tool showed an accurate calculation of eye lens doses at the dual source CT scanner without gantry angulation and for CT angiography examinations. The dose monitoring software tool based on MCS gave accurate estimates of eye lens doses in cranial CT protocols. However, knowledge of protocol and software specific influences is crucial for correct assessment of eye lens doses in routine clinical use. (orig.)

Clinical evaluation of a dose monitoring software tool based on Monte Carlo Simulation in assessment of eye lens doses for cranial CT scans

International Nuclear Information System (INIS)

Guberina, Nika; Suntharalingam, Saravanabavaan; Nassenstein, Kai; Forsting, Michael; Theysohn, Jens; Wetter, Axel; Ringelstein, Adrian

2016-01-01

The aim of this study was to verify the results of a dose monitoring software tool based on Monte Carlo Simulation (MCS) in assessment of eye lens doses for cranial CT scans. In cooperation with the Federal Office for Radiation Protection (Neuherberg, Germany), phantom measurements were performed with thermoluminescence dosimeters (TLD LiF:Mg,Ti) using cranial CT protocols: (I) CT angiography; (II) unenhanced, cranial CT scans with gantry angulation at a single and (III) without gantry angulation at a dual source CT scanner. Eye lens doses calculated by the dose monitoring tool based on MCS and assessed with TLDs were compared. Eye lens doses are summarized as follows: (I) CT angiography (a) MCS 7 mSv, (b) TLD 5 mSv; (II) unenhanced, cranial CT scan with gantry angulation, (c) MCS 45 mSv, (d) TLD 5 mSv; (III) unenhanced, cranial CT scan without gantry angulation (e) MCS 38 mSv, (f) TLD 35 mSv. Intermodality comparison shows an inaccurate calculation of eye lens doses in unenhanced cranial CT protocols at the single source CT scanner due to the disregard of gantry angulation. On the contrary, the dose monitoring tool showed an accurate calculation of eye lens doses at the dual source CT scanner without gantry angulation and for CT angiography examinations. The dose monitoring software tool based on MCS gave accurate estimates of eye lens doses in cranial CT protocols. However, knowledge of protocol and software specific influences is crucial for correct assessment of eye lens doses in routine clinical use. (orig.)

10 CFR 20.1502 - Conditions requiring individual monitoring of external and internal occupational dose.

Science.gov (United States)

2010-01-01

... external and internal occupational dose. Each licensee shall monitor exposures to radiation and radioactive... 10 Energy 1 2010-01-01 2010-01-01 false Conditions requiring individual monitoring of external and internal occupational dose. 20.1502 Section 20.1502 Energy NUCLEAR REGULATORY COMMISSION STANDARDS FOR...

Radiation exposure control by estimation of multiplication factors for online remote radiation monitoring systems at vitrification plant

International Nuclear Information System (INIS)

Deokar, U.V.; Kulkarni, V.V.; Khot, A.R.; Mathew, P.; Kamlesh; Purohit, R.G.; Sarkar, P.K.

2012-01-01

Vitrification Plant is commissioned for vitrification of high level liquid waste (HLW) generated in nuclear fuel cycle operations by using Joule Heated Ceramic Melter first time in India. Exposure control is a major concern in operating plant. Therefore in addition to installed monitors, we have developed online remote radiation monitoring system to minimize number of entries in amber areas and to reduce the exposure to the surveyor and operator. This also helped in volume reduction of secondary waste. The reliability and accuracy of the online monitoring system is confirmed with actual measurements and by theoretical shielding calculations. The multiplication factors were estimated for remote on line monitoring of Melter Off Gas (MOG) filter, Hood filter, three exhaust filter banks, and over-pack monitoring. This paper summarizes - how the online remote monitoring system helped in saving of 128.52 person-mSv collective dose (14.28% of budgeted dose). The system also helped in the reduction of 2.6 m 3 of Cat-I waste. Our online remote monitoring system has helped the plant management to plan in advance for replacement of these filters, which resulted in considerable saving in collective dose and secondary waste

Implication of new CEC recommendations for individual monitoring for external radiation doses to the skin and the extremities

International Nuclear Information System (INIS)

Christensen, P.; Julius, H.W.; Marshall, T.O.

1991-01-01

A drafting group consisting of the above authors has assisted the CEC in revising the CEC document Technical Recommendations for Monitoring the Exposure to Individuals to External Radiation, EUR 5287, published in 1975. The paper highlights sections of the revised version relating particularly to irradiation of the skin and the extremities and focusses on problems connected to exposure to weakly penetrating radiations. Concepts of individual monitoring for external radiation exposures to the skin of the whole body and to the extremities are discussed and guidance is given as regards dose quantities and dosemeter calibration procedures. A method of quantifying the overall accuracy of the dose measurements as a result of the various uncertainty components connected with the dosimetry system is suggested and requirements on the accuracy of the dose measurements complying with the ICRP requirements on overall accuracy for individual monitoring are specified. Moreover, implications of the accuracy requirements for the design and type testing of the dosemeter are discussed. (author)

Elementary introduction for personal dose monitoring

International Nuclear Information System (INIS)

Bai Guang

2004-01-01

According to national laws and regulations, personnel who work with radiation must wear personal dosimeters and receive personal dose monitoring (PDM) provided by professional establishments, which are qualified for this purpose and certificated by the authorities. In this paper, the author gives a brief discussion concerning the Regulations & Purpose of PDM and the historical lessons in accident exposure without PDM. At last, it is pointed out that the PDM provided by the third-party commercial organizations is becoming the trend in this field. (author)

Dose monitoring in radiology departments. Status quo and future perspectives; Dosismonitoring in der Radiologie. Status quo und Zukunftsperspektiven

Energy Technology Data Exchange (ETDEWEB)

Boos, J. [Harvard Medical School, Boston, MA (United States). Dept. of Radiology; Duesseldorf Univ. (Germany). Inst. fuer Diagnostische und Interventionelle Radiologie; Meineke, A. [Cerner Healthcare Services, Idstein (Germany); Bethge, O.T.; Antoch, G.; Kroepil, P. [Duesseldorf Univ. (Germany). Inst. fuer Diagnostische und Interventionelle Radiologie

2016-05-15

The number of computed tomography examinations has continuously increased over the last decades and accounts for a major part of the collective radiation dose from medical investigations. For purposes of quality assurance in modern radiology a systematic monitoring and analysis of dose related data from radiological examinations is mandatory. Various ways of collecting dose data are available today, for example the Digital Imaging and Communication in Medicine - Structured Report (DICOM-SR), optical character recognition and DICOM-modality performed procedure steps (MPPS). The DICOM-SR is part of the DICOM-standard and provides the DICOM-Radiation Dose Structured Report, which is an easily applicable and comprehensive solution to collect radiation dose parameters. This standard simplifies the process of data collection and enables comprehensive dose monitoring. Various commercial dose monitoring software devices with varying characteristics are available today. In this article, we discuss legal obligations, various ways to monitor dose data, current dose monitoring software solutions and future perspectives in regard to the EU Council Directive 2013/59/EURATOM.

Automatic radiation dose monitoring for CT of trauma patients with different protocols: feasibility and accuracy

International Nuclear Information System (INIS)

Higashigaito, K.; Becker, A.S.; Sprengel, K.; Simmen, H.-P.; Wanner, G.; Alkadhi, H.

2016-01-01

Aim: To demonstrate the feasibility and accuracy of automatic radiation dose monitoring software for computed tomography (CT) of trauma patients in a clinical setting over time, and to evaluate the potential of radiation dose reduction using iterative reconstruction (IR). Materials and methods: In a time period of 18 months, data from 378 consecutive thoraco-abdominal CT examinations of trauma patients were extracted using automatic radiation dose monitoring software, and patients were split into three cohorts: cohort 1, 64-section CT with filtered back projection, 200 mAs tube current–time product; cohort 2, 128-section CT with IR and identical imaging protocol; cohort 3, 128-section CT with IR, 150 mAs tube current–time product. Radiation dose parameters from the software were compared with the individual patient protocols. Image noise was measured and image quality was semi-quantitatively determined. Results: Automatic extraction of radiation dose metrics was feasible and accurate in all (100%) patients. All CT examinations were of diagnostic quality. There were no differences between cohorts 1 and 2 regarding volume CT dose index (CTDI_v_o_l; p=0.62), dose–length product (DLP), and effective dose (ED, both p=0.95), while noise was significantly lower (chest and abdomen, both −38%, p<0.017). Compared to cohort 1, CTDI_v_o_l, DLP, and ED in cohort 3 were significantly lower (all −25%, p<0.017), similar to the noise in the chest (–32%) and abdomen (–27%, both p<0.017). Compared to cohort 2, CTDI_v_o_l (–28%), DLP, and ED (both –26%) in cohort 3 was significantly lower (all, p<0.017), while noise in the chest (+9%) and abdomen (+18%) was significantly higher (all, p<0.017). Conclusion: Automatic radiation dose monitoring software is feasible and accurate, and can be implemented in a clinical setting for evaluating the effects of lowering radiation doses of CT protocols over time. - Highlights: • Automatic dose monitoring software can be

Personal dose monitoring in hospitals: Global assessment, critical applications and future needs

International Nuclear Information System (INIS)

Covens, P.; Berus, D.; Buls, N.; Clerinx, P.; Vanhavere, F.

2007-01-01

It is known that medical applications using ionising radiation are wide spread and still increasing. Physicians, technicians, nurses and others constitute the largest group of workers occupationally exposed to man-made sources of radiation. Many hospital workers are consequently subjected to routine monitoring of professional radiation exposures. in the university hospital, UZ Brussel, 600 out of 4000 staff members are daily monitored for external radiation exposures. The most obvious applications of ionising radiation are diagnostic radiology, diagnostic or therapeutic use of radionuclides in nuclear medicine and external radiation therapy or brachytherapy in radiotherapy departments. Other important applications also include various procedures in interventional radiology (IR), in vitro biomedical research and radiopharmaceutical production around cyclotrons. Besides the fact that many of the staff members, involved in these applications, are not measurably exposed, detailed studies were carried out at workplaces where routine dose monitoring encounters difficulties and for some applications where relatively high occupational exposures can be found. most of the studies are concentrated around nuclear medicine applications and IR. They contain assessments of both effective dose and doses at different parts of the body. The results contribute to better characterisation of the different workplaces in a way that critical applications can be identified. Moreover, conclusions point out future needs for practical routine dose monitoring and optimisation of radiation protection. (authors)

RFID based TLD monitoring system - a prospective development

International Nuclear Information System (INIS)

Jeevanram, S.S.; Pawar, S.T.; Mahule, K.N.; Rath, D.P.

2008-01-01

Thermo Luminescence Dosimetry (TLD) is an established method of monitoring the radiation dose received by workers in radiation environments. In Radiometallurgy Laboratory, BARC, the TLD movement inside a nuclear facility is completely carried out by a radiation worker. However, there is a chance that the TLDs may get lost in laboratories or some places without the knowledge of the concerned TLD user or health physicist. It may later lead to a false effective dose. Effort is being done to initiate a RFID based TLD monitoring system so that the use of TLD can be acknowledged through a self operating software which can prevent misuse of the detector. A novel method of improving the administrative control through Radio Frequency Identification (RFID) based monitoring to avoid such inadvertent misplacement of TLD, is in progress. This paper discusses the method and techniques through which administrative control can be exercised to reduce the number of such in explainable exposures. (author)

REMIT, Radiation Exposure Monitoring and Information Transmittal System

International Nuclear Information System (INIS)

Cale, R.; Clark, T.; Dixson, P.; Hagemeyer, D.; Hardwick, C.; Pippen, H.

1997-01-01

1 - Description of program or function: The Radiation Exposure Monitoring and Information Transmittal (REMIT) system is designed to assist U.S. Nuclear Regulatory Commission (NRC) licensees in meeting the reporting requirements of the Revised 10 CFR Part 20 and in agreement with the guidance contained in Regulatory Guide 8.7, Rev.1, Instructions for Recording and Reporting Occupational Exposure Data. REMIT is a personal computer (PC) -based menu driven system that facilitates the manipulation of data base files to record and report radiation exposure information. REMIT is designed to be user-friendly and contains the full text of Regulatory Guide 8.7, Rev.1, on-line as well as context-sensitive help throughout the program. The user can enter data directly from NRC Form 5s or Form 4s. REMIT allows the user to view the individual's exposure in relation to regulatory or administrative limits and will alert the user to exposures in excess of these limits. The system also provides for the calculation and summation of dose from intakes and the determination of the dose to the maximally exposed extremity for the monitoring year. REMIT can produce NRC Form 5s and 4s in paper and electronic format and can import/export data from ASCII and data base files. 2 - Method of solution: REMIT makes use of the dose conversion factors from EPA Report 11 Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submission, and Ingestion, to calculate the Committed Dose Equivalent to the maximally exposed organ and the committed Effective Dose Equivalent from intakes measured in micro-curies. REMIT also estimates the amount (in micrograms) of uranium intake from the activity entered in micro-curies. This calculation is based on the specific activities of the uranium isotopes. 3 - Restrictions on the complexity of the problem: REMIT is a single- user system that only runs on IBM compatible PC systems under DOS and supports only Hewlett

Comparisons between direct ion storage and thermoluminescence dosimetry individual monitoring systems, and internet reporting

International Nuclear Information System (INIS)

Kiuru, A.; Kahilainen, J.; Hyvoenen, H.; Vartiainen, E.

2001-01-01

A new electronic direct ion storage (DIS) dosemeter allows accumulated personal dose equivalent H p (d) at depths of 10 mm and 0.07 mm to be monitored in a few seconds by inserting the dosemeter into a local reader without deleting the accumulated dose. The DIS system meets general requirements on individual monitoring of hospital personnel using ionising radiation. It differs greatly from off-line thermoluminescence dosimetry systems and offers many additional benefits. The non-volatile reading takes only 5 s, is taken as often as needed, and the data are collected into a dose database, where background radiation is subtracted. Individual personnel doses are reported in Intranet as well as on the Internet at regular intervals to the National Regulatory Authorities. (author)

A microprocessor based area monitor system for neutron and gamma radiation

International Nuclear Information System (INIS)

Wilhelm, R.; Heusser, G.

1980-01-01

The conventional electronics of the area monitors at the MPI-Heidelberg accelerators have been replaced by a microprocessor system consisting of individual detector-microprocessors and a central microcomputer. The detector microprocessors convert the count rates of BF3 and GM counter tubes into dose rates and control three different radiation thresholds (failure, low and high level). Different warning signals are operated directly by the detector processors, whereas the dose rates are transferred to the central microcomputer. Here the data are processed for recording on tape and displaying on TV monitors. The detector as well as the central processors have been developed on the basis of a 16-bit microprocessor. In the control rooms the dose rates of the individual monitors are displayed and on an indicator board showing the different locations, the high radiation level and the state of the doors (open, locked, and closed, locked but open) are sianaled by different LED. If a high radiation threshold is surpassed, the doors adjacent to that area can be locked either by switches on the indicator board or automatically. Within the experimental area, the low and high radiation level is indicated by acoustic and light signals. The whole concept permits keeping the absorbed doses of the personnel as low as possible without affecting the flexibility of the experimental operations. The independence of the microprocessor driven area monitors guarantees a high reliability. Compared to conventional electronics the advantages of the system are its reliability and cost. (Author)

SU-F-R-11: Designing Quality and Safety Informatics Through Implementation of a CT Radiation Dose Monitoring Program

International Nuclear Information System (INIS)

Wilson, JM; Samei, E

2016-01-01

Purpose: Recent legislative and accreditation requirements have driven rapid development and implementation of CT radiation dose monitoring solutions. Institutions must determine how to improve quality, safety, and consistency of their clinical performance. The purpose of this work was to design a strategy and meaningful characterization of results from an in-house, clinically-deployed dose monitoring solution. Methods: A dose monitoring platform was designed by our imaging physics group that focused on extracting protocol parameters, dose metrics, and patient demographics and size. Compared to most commercial solutions, which focus on individual exam alerts and global thresholds, the program sought to characterize overall consistency and targeted thresholds based on eight analytic interrogations. Those were based on explicit questions related to protocol application, national benchmarks, protocol and size-specific dose targets, operational consistency, outliers, temporal trends, intra-system variability, and consistent use of electronic protocols. Using historical data since the start of 2013, 95% and 99% intervals were used to establish yellow and amber parameterized dose alert thresholds, respectively, as a function of protocol, scanner, and size. Results: Quarterly reports have been generated for three hospitals for 3 quarters of 2015 totaling 27880, 28502, 30631 exams, respectively. Four adult and two pediatric protocols were higher than external institutional benchmarks. Four protocol dose levels were being inconsistently applied as a function of patient size. For the three hospitals, the minimum and maximum amber outlier percentages were [1.53%,2.28%], [0.76%,1.8%], [0.94%,1.17%], respectively. Compared with the electronic protocols, 10 protocols were found to be used with some inconsistency. Conclusion: Dose monitoring can satisfy requirements with global alert thresholds and patient dose records, but the real value is in optimizing patient

SU-F-R-11: Designing Quality and Safety Informatics Through Implementation of a CT Radiation Dose Monitoring Program

Energy Technology Data Exchange (ETDEWEB)

Wilson, JM [Clinical Imaging Physics Group and Carl E. Ravin Advanced Imaging Laboratories, Department of Radiology, Duke University Medical Center, Durham, NC (United States); Samei, E [Clinical Imaging Physics Group and Carl E. Ravin Advanced Imaging Laboratories, Department of Radiology, Duke University Medical Center, Durham, NC (United States); Departments of Physics, Electrical and Computer Engineering, and Biomedical Engineering, and Medical Physics Graduate Program, Duke University, Durham, NC (United States)

2016-06-15

Purpose: Recent legislative and accreditation requirements have driven rapid development and implementation of CT radiation dose monitoring solutions. Institutions must determine how to improve quality, safety, and consistency of their clinical performance. The purpose of this work was to design a strategy and meaningful characterization of results from an in-house, clinically-deployed dose monitoring solution. Methods: A dose monitoring platform was designed by our imaging physics group that focused on extracting protocol parameters, dose metrics, and patient demographics and size. Compared to most commercial solutions, which focus on individual exam alerts and global thresholds, the program sought to characterize overall consistency and targeted thresholds based on eight analytic interrogations. Those were based on explicit questions related to protocol application, national benchmarks, protocol and size-specific dose targets, operational consistency, outliers, temporal trends, intra-system variability, and consistent use of electronic protocols. Using historical data since the start of 2013, 95% and 99% intervals were used to establish yellow and amber parameterized dose alert thresholds, respectively, as a function of protocol, scanner, and size. Results: Quarterly reports have been generated for three hospitals for 3 quarters of 2015 totaling 27880, 28502, 30631 exams, respectively. Four adult and two pediatric protocols were higher than external institutional benchmarks. Four protocol dose levels were being inconsistently applied as a function of patient size. For the three hospitals, the minimum and maximum amber outlier percentages were [1.53%,2.28%], [0.76%,1.8%], [0.94%,1.17%], respectively. Compared with the electronic protocols, 10 protocols were found to be used with some inconsistency. Conclusion: Dose monitoring can satisfy requirements with global alert thresholds and patient dose records, but the real value is in optimizing patient

Information system of partial monitoring system 'Radioactivity of the environment'

International Nuclear Information System (INIS)

Melicherova, T.

2007-01-01

Slovak Hydrometeorological Institute (SHMI) is operator of radiation monitoring from 1963. At present SHMI operates in its monitoring network 23 detectors GammaTracer fy Genitron, one mobile detector and one standby detector. Radiation data (dose rate in the unit nSv/h) from detectors in the automated meteorological stations are transmitted by data-logger and private institute network to National Telecommunication Centre in Bratislava. The data from MSS (message switch system) are inserted into the database. The 1 hours and 24 hours averages are computed on the server automatically. Delay between time of measurements and time of inserting data to database is only 10 min. Radiation files from SHMI network are on-line transmitted to information system of Nuclear Regulatory Authority of the Slovak Republic and to information system of Slovak Army. Transmission to to Crisis Centre of Civil Protection is under reconstruction at present. Database contains one table for radiation data and several tables for configurations, catalogues of stations and additional tables. Database works in environment client-server. On client PC runs the user front-end application. This application provides to display the data using many filters, to display tables with configurations concerning technical equipment, to display maps, graphs, etc. There is the possibility to store data into the archives, to make reports and to analyse data in the environment of professional statistical software. Precipitations values from meteorological stations were integrated do the information system of radiation monitoring for better interpretation of gamma dose rate values. SHMI cooperates in the radiation data exchange with European Commission Joint Research Centre in Ispra, Radiation Warning Centre in Vienna and Meteoservice Budapest. (author)

Using Six Sigma to improve once daily gentamicin dosing and therapeutic drug monitoring performance.

LENUS (Irish Health Repository)

Egan, Sean

2012-08-07

BACKGROUND: Safe, effective therapy with the antimicrobial gentamicin requires good practice in dose selection and monitoring of serum levels. Suboptimal therapy occurs with breakdown in the process of drug dosing, serum blood sampling, laboratory processing and level interpretation. Unintentional underdosing may result. This improvement effort aimed to optimise this process in an academic teaching hospital using Six Sigma process improvement methodology. METHODS: A multidisciplinary project team was formed. Process measures considered critical to quality were defined, and baseline practice was examined through process mapping and audit. Root cause analysis informed improvement measures. These included a new dosing and monitoring schedule, and standardised assay sampling and drug administration timing which maximised local capabilities. Three iterations of the improvement cycle were conducted over a 24-month period. RESULTS: The attainment of serum level sampling in the required time window improved by 85% (p≤0.0001). A 66% improvement in accuracy of dosing was observed (p≤0.0001). Unnecessary dose omission while awaiting level results and inadvertent disruption to therapy due to dosing and monitoring process breakdown were eliminated. Average daily dose administered increased from 3.39 mg\\/kg to 4.78 mg\\/kg\\/day. CONCLUSIONS: Using Six Sigma methodology enhanced gentamicin usage process performance. Local process related factors may adversely affect adherence to practice guidelines for gentamicin, a drug which is complex to use. It is vital to adapt dosing guidance and monitoring requirements so that they are capable of being implemented in the clinical environment as a matter of routine. Improvement may be achieved through a structured localised approach with multidisciplinary stakeholder involvement.

Online monitoring of absorbed dose in undulator magnets with RADFET dosimeters at FERMI@Elettra

International Nuclear Information System (INIS)

Fröhlich, L.; Casarin, K.; Quai, E.; Holmes-Siedle, A.; Severgnini, M.; Vidimari, R.

2013-01-01

The FERMI@Elettra free-electron laser, based on a 1.3 GeV electron linac, requires the monitoring of radiation doses up to a few kGy for the protection of sensitive equipment such as permanent magnet undulators. A new dosimetry system DOSFET-L01, employing an array of RADFETs spread throughout the accelerator, was developed. So far, the system has performed flawlessly for almost two years, taking one dose reading per minute around the clock. The REM RFT-300 sensors were set in zero-bias mode, i.e. with all electrodes grounded during exposure. This choice of mode allows the measurement of a high range of integrated doses – up to a few kGy. The paper describes the new read-out system and its application, calibration measurements in cobalt-60 and 6 MeV bremsstrahlung radiation sources giving rise to a novel response function, and new data on “fade” under the zero-bias mode of use for over 300 days at room temperature. Regular readings from 28 RADFETs placed within seven undulators over the first 20 months of operation of the accelerator demonstrate how the system tracks and locates periods of high and low dose rate and thereby contributes to the protection from beam loss. The readings from the RADFET system are found to be in good agreement with Gafchromic EBT2 film dosimeters. Based on the results reported, the choice of bias mode may be revised so as to reduce fade and improve the accuracy conferred by a positive-bias mode. -- Highlights: ► We developed a system for online dosimetry with RADFET sensors under zero bias. ► The system is calibrated for doses up to 10 kGy with REM RFT-300 sensors. ► We collected data on fade for over 300 days from irradiation. ► We present undulator dose measurements for 20 months of operation of FERMI@Elettra. ► Dose measurements are in good agreement with chemical film dosimeters

Glass badge dosimetry system for large scale personal monitoring

International Nuclear Information System (INIS)

Norimichi Juto

2002-01-01

Glass Badge using silver activated phosphate glass dosemeter was specially developed for large scale personal monitoring. And dosimetry systems such as an automatic leader and a dose equipment calculation algorithm were developed at once to achieve reasonable personal monitoring. In large scale personal monitoring, both of precision for dosimetry and confidence for lot of personal data handling become very important. The silver activated phosphate glass dosemeter has basically excellent characteristics for dosimetry such as homogeneous and stable sensitivity, negligible fading and so on. Glass Badge was designed to measure 10 keV - 10 MeV range of photon. 300 keV - 3 MeV range of beta, and 0.025 eV - 15 MeV range of neutron by included SSNTD. And developed Glass Badge dosimetry system has not only these basic characteristics but also lot of features to keep good precision for dosimetry and data handling. In this presentation, features of Glass Badge dosimetry systems and examples for practical personal monitoring systems will be presented. (Author)

Online dose rate monitoring: Better information by using the IRMA concept (Integral Radiological Multidetector Arrays)

International Nuclear Information System (INIS)

Genrich, V.

1989-01-01

A new GM detector system has been developed for online environmental monitoring. The approach is unorthodox, but simple: A) Take a set of radiological probes and feed all their information to an 'intelligent' front-end. B) Elaborate some algorithms, so that the system will give out just one gamma dose rate (running over more than nine decades). C) If necessary, associate some additional sensors, and the system will exhibit better discriminating qualities for the detection of artificial nuclides in the environment. (orig.)

[A novel serial port auto trigger system for MOSFET dose acquisition].

Science.gov (United States)

Luo, Guangwen; Qi, Zhenyu

2013-01-01

To synchronize the radiation of microSelectron-HDR (Nucletron afterloading machine) and measurement of MOSFET dose system, a trigger system based on interface circuit was designed and corresponding monitor and trigger program were developed on Qt platform. This interface and control system was tested and showed stable operate and reliable work. This adopted serial port detect technique may expand to trigger application of other medical devices.

Provision of dosimeters by official monitoring services for eye lens dose estimation

International Nuclear Information System (INIS)

Engelhardt, J.; Martini, E.

2013-01-01

Recent epidemiological studies are implying that the radio sensitivity of the eye lens is much higher than supposed in the past. International recommendations and standards demand to lower down the annual limit of the eye lens organ dose to 20 mSv. Since about 10 years German monitoring services offer partial-body dosimeters fixed on the head or on glasses for monitoring the eye lens dose. These dosimeters are optimized to measure the (surface) personal dose equivalent H p (0,07) from 0,5 mSv up to 10 Sv, which clearly overestimate the organ dose of the eye lens. With special features like different calibrations partial-body dosimeters should be applicable for legal dosimetry to avoid the development of special H p (3) dosimeters. Accepting the right way for wearing these dosimeters it is important to get the right results. Practical experiences are shown with measuring results and the difficulties of rounding the exact measuring values to discrete dose steps. Closing this article we point to still missing legal basis and open questions regarding to type testing procedures. (orig.)

Radiation Exposure Monitoring and Information Transmittal (REMIT) system

International Nuclear Information System (INIS)

Cale, R.; Clark, T.; Dixson, R.; Hagemeyer, D.

1993-06-01

The Radiation Exposure Monitoring and Information Transmittal (REMIT) system is designed to assist US Nuclear Regulatory Commission (NRC)licensees in meeting the reporting requirements of the revised 10 CFR 20 and in agreement with the guidance contained in R.G. 8.7, Rev. 1, ''Instructions for Recording and Reporting Occupational Exposure Data.'' REMIT is a personal computer (PC) based menu driven system that facilitates the manipulation of data base files to record and report radiation exposure information. REMIT is designed to be user-friendly and contains the full text of R. G. 8.7, Rev. 1, on-line as well as context-sensitive help throughout the program. The user can enter data directly from NRC Forms 4 or 5, REMIT allows the user to view the individual's exposure in relation to regulatory or administrative limits and alerts the user to exposures in excess of these limits. The system also provides for the calculation and summation of dose from intakes and the determination of the dose to the maximally exposed extremity for the monitoring year. REMIT can produce NRC Forms 4 and 5 in paper and electronic format and can import/export data from ASCII and data base files

Radiologic Monitoring of Faculty and Staff in an Electrophysiology Lab Using a Real-Time Dose Monitoring System

Science.gov (United States)

Chardenet, Kathleen A.

2016-01-01

Purpose: A real-time dose management system was used to determine if radiation exposure levels would decrease when providers were privy to their real-time radiation exposure levels. Six aggregate categories of providers were first blinded (phase 1) and subsequently made aware of their radiation exposure levels during electrophysiology procedures…

An automatic dose verification system for adaptive radiotherapy for helical tomotherapy

International Nuclear Information System (INIS)

Mo, Xiaohu; Chen, Mingli; Parnell, Donald; Olivera, Gustavo; Galmarini, Daniel; Lu, Weiguo

2014-01-01

Purpose: During a typical 5-7 week treatment of external beam radiotherapy, there are potential differences between planned patient's anatomy and positioning, such as patient weight loss, or treatment setup. The discrepancies between planned and delivered doses resulting from these differences could be significant, especially in IMRT where dose distributions tightly conforms to target volumes while avoiding organs-at-risk. We developed an automatic system to monitor delivered dose using daily imaging. Methods: For each treatment, a merged image is generated by registering the daily pre-treatment setup image and planning CT using treatment position information extracted from the Tomotherapy archive. The treatment dose is then computed on this merged image using our in-house convolution-superposition based dose calculator implemented on GPU. The deformation field between merged and planning CT is computed using the Morphon algorithm. The planning structures and treatment doses are subsequently warped for analysis and dose accumulation. All results are saved in DICOM format with private tags and organized in a database. Due to the overwhelming amount of information generated, a customizable tolerance system is used to flag potential treatment errors or significant anatomical changes. A web-based system and a DICOM-RT viewer were developed for reporting and reviewing the results. Results: More than 30 patients were analysed retrospectively. Our in-house dose calculator passed 97% gamma test evaluated with 2% dose difference and 2mm distance-to-agreement compared with Tomotherapy calculated dose, which is considered sufficient for adaptive radiotherapy purposes. Evaluation of the deformable registration through visual inspection showed acceptable and consistent results, except for cases with large or unrealistic deformation. Our automatic flagging system was able to catch significant patient setup errors or anatomical changes. Conclusions: We developed an automatic

Issues of assessment of doses from natural sources in working conditions: implications for the unified state system of individual dose monitoring

Directory of Open Access Journals (Sweden)

T. A. Kormanovskaya

2017-01-01

Full Text Available The aims of the work are: 1 an analysis of information on radiation doses from natural sources of ionizing radiation of employees of enterprises in some industries of the Russian Federation and 2 an assessment of the state of registration of doses from natural sources in working conditions in the Unified System of Individual Dose Control. Materials and methods. The analysis was performed on the results of the operation of the Federal database of radiation doses of the population due to natural and artificial radiation background in 2013–2015 on the basis of the forms of the Federal statistical observation No. 4-DOZ in terms of collecting information on the radiation doses of workers in some non-nuclear industries due to natural sources of ionizing radiation. Results. Analysis of enterprises in 17 industries in 23 regions of Russia connected with the specificity of production processes showed cases of natural exposure of workers at the dose level exceeding 5 mSv/year. We have identified those branches of industry, for which the doses were close to 5 mSv/year.Examples of reducing the radiation doses by reducing the time spent by workers in workplaces with high levels of radiation are given. The problems of insufficient representativeness of the sample data are due to the lack of interaction of the management of industrial enterprises with the bodies of the Rospotrebnadzor. The obtained data allow speaking about the problem of assessing the quality of radiation control in the organizations where additional exposure of workers from natural radiation sources is expected. It is necessary to create a system of regulatory and procedural documents to solve the problem at the national level.

Analysis of radiation doses from operation of postulated commercial spent fuel transportation systems: Analysis of a system containing a monitored retrievable storage facility

International Nuclear Information System (INIS)

Smith, R.I.; Daling, P.M.; Faletti, D.W.

1992-04-01

This addendum report extends the original study of the estimated radiation doses to the public and to workers resulting from transporting spent nuclear fuel from commercial nuclear power reactor stations through the federal waste management system (FWMS), to a system that contains a monitored retrievable storage (MRS) facility. The system concepts and designs utilized herein are consistent with those used in the original study (circa 1985--1987). Because the FWMS design is still evolving, the results of these analyses may no longer apply to the design for casks and cask handling systems that are currently being considered. Four system scenarios are examined and compared with the reference No-MRS scenario (all spent fuel transported directly from the reactors to the western repository in standard-capacity truck and rail casks). In Scenarios 1 and 2, an MRS facility is located in eastern United States and ships either intact fuel assemblies or consolidated fuel rods and compacted assembly hardware in canisters. In Scenarios 3 and 4, an MRS facility is located in the western United States and ship either intact fuel assemblies or consolidated fuel rods and compacted assembly hardware in canisters

Mobile radiation monitoring of Mumbai and it's suburb through various road routes by using state-of-the-art radiation monitoring systems

International Nuclear Information System (INIS)

Divkar, J.K.; Chatterjee, M.K.; Patil, S.S.; Sharma, Ranjit; Singh, Rajvir; Pradeepkumar, K.S.

2007-01-01

The monitoring of environmental radiation in different parts of the country is being periodically carried out with an objective to establish the countrywide baseline dose rate data. The task of quick assessment of impact due to any large-scale radiological emergencies in public domain involves reliable and quick monitoring of dose rate levels using mobile monitoring techniques. In order to achieve higher accuracy and more confidence in measured values, various state-of-the-art monitoring systems are used for mapping a large area. It enables collection and processing of data for rapid and correct evaluation of the situation. The evaluation of measured data from the different systems provides comparable results. This paper describes the radiation mapping of Mumbai and its suburbs carried out through different road routes by installing state-of-the art monitoring systems like CARMS, PMGSS, gamma tracers and micro-R survey meters in a light motor vehicle with the objective of assessing the background radiation level of Mumbai city including Mumbai Suburb, Navi Mumbai and Thane, tagging each data with the positional coordinates and also to detect and locate the presence of orphan sources, if any. The average of measured dose rate levels of Mumbai and Mumbai Suburbs, Navi Mumbai and Thane are 53.3±9.1 nGy.h -1 , 50.9±10.0 nGy.h -1 and 52.1±10.8 nGy.h -1 respectively with maximum ∼ 160 nGy.h -l due to presence of high concentration of 40 K at some locations. (author)

Control of occupational exposure using remote monitoring systems

Energy Technology Data Exchange (ETDEWEB)

Lunn, M. P. [British Energy Generation Ltd. Sizewell B Power Station, Leiston, Suffolk (United Kingdom)

2004-07-01

Advances in electronic dosimetry, portable radio technology and digital video have enabled the development of Remote Monitoring Systems (RMS) that provide a powerful dose control tool for the Operational Health Physicist. North American utilities have led the implementation of these systems, often with coverage of the entire plant, feeding back to a centralized control room. These large-scale systems typically cost around EURO 500,000. In Europe, and especially the UK, implementation of RMS technology has been slower and on a smaller scale. US utilities have justified the high capital cost of their systems by significantly reducing the number of contract RP technicians required during refuelling outages, saving up to EURO 1,000,000. In the UK, the number of contract RP technicians employed during outages is already minimal, and with the generally low dose rates found on Gas-Cooled Reactors, RP engineers have traditionally considered RMS to be an extravagance. However, the commissioning of the UK's first PWR and a significant increase in the number of AGR Vessel entries, have increased the radiological protection challenges facing the British Health Physicist, thus prompting a re-evaluation of this view. The benefit derived from a system that combines telemetry, video and voice communications is synergistic. We found that the system can be used in a variety of ways to significantly enhance radiological protection control in high radiation areas and to significantly reduce the dose received by RP staff covering such jobs. Indeed, it is estimated that the use of RMS saved at least 10 man.mSv of Radiological Protection dose during RF06 However, it is important to note that RMS is a monitoring tool to support existing monitoring techniques and arrangements. Suitably qualified and experienced staff are required to interpret the data and provide suitable advice to the work party. In addition, detailed training on the limitations of RMS, explicit procedures for

Emissions and doses from sources of ionising radiation in the Netherlands: radiation policy monitoring

International Nuclear Information System (INIS)

Eleveld, H.; Pruppers, M.

2002-01-01

In 1997 the Ministry of Housing, Spatial Planning and the Environment requested RIVM to develop an information system for policy monitoring. One of the motives was that the European Union requires that the competent authorities of each member state ensure that dose estimates due to practices involving exposure to ionising radiation are made as realistic as possible for the population as a whole and for reference groups in all places where such groups may occur. Emissions of radionuclides and radiation to the environment can be classified as follows: (1) emissions to the atmosphere, (2) emissions to the aquatic system and (3) emission of external radiation from radioactive materials and equipment that produces ionising radiation. Released radioactivity is dispersed via exposure pathways, such as the atmosphere, deposition on the ground and farmland products, drinking water, fish products, etc. This leads to radiation doses due to inhalation, ingestion and exposure to external radiation. To assess the possible radiation doses different kinds of models are applied, varying from simple multiplications with dispersion coefficients, transfer coefficients and dose conversion coefficients to complex dispersion models. In this paper an overview is given of the human-induced radiation doses in the Netherlands. Also, trends in and the effect of policy on the radiation dose of members of the public are investigated. This paper is based on an RIVM report published recently. A geographical distribution of radiation risks due to routine releases for a typical year in the Netherlands was published earlier

Measurement of the external doses at low and high exposures by Agfa personal monitoring film, FD-III-B badge

International Nuclear Information System (INIS)

Mihai, F.; Stochioiu, A.; Bercea, S.; Udup, E.; Tudor, I.

2008-01-01

Full text: A growing number of papers report occupational exposure monitoring by different dosemeter devices. Researches into improvement of the personal dosemeter systems are encouraged. Dose measurement and especially skin dose measurement, are therefore increasingly important. Methods and acceptable dosemeter are not clearly defined and differ from a dosimetry laboratory to other depending on their specifically work procedure and type of dosemeter utilized. Taking into account the characteristic of the work place (industry, research, medical application) dosemeter have to cover a large dose range. The dose assessment problems are manly in low doses range (under 0.2 mSv) and higher doses range. For example, typical for radiation oncology and nuclear accident dosimetry the dose ranges are on the order of 2-70 Gy and 0.1-5 Gy. This work presents the performance of the Agfa personal monitoring film, badge FD-III-B type used in the most of the occupational exposure monitoring from Romania. The FD-III-B dosimeter, manufactured in Romania, is used for monitoring personnel working in radioactive environment - the photodosimetric method is the one of the most reliable method presenting the advantage that the film may be considered as master probe over 30 year and may be utilized during litigation. The dosimeter contains metallic filters of Al, Cu, Pb with different thicknesses, a plastic filter and a open window. The badge FD-III-B is a class B dosimeter according to the dose range and an indices 3 dosimeter from energy range of the radiations in conformity with Romanian Standard in force. Film Agfa 'personal monitoring', tacked in this experiment, consists of a low speed film (D2) and a very sensitive film (D10) designed for recording X-ray, gamma and beta radiation over the doses range 0.1 mSv to 1 Sv. The experiments have been effectuated at different background optical density (base fog) of the films and at different sources of radiation: 13 :7Cs, 60 Co and 24 : 1 Am

An approach to routine individual internal dose monitoring at the object 'Shelter' personnel considering uncertainties

International Nuclear Information System (INIS)

Mel'nichuk, D.V.; Bondarenko, O.O.; Medvedjev, S.Yu.

2002-01-01

An approach to organisation of routine individual internal dose monitoring of the personnel of the Object 'Shelter' is presented in the work, that considers individualised uncertainties. In this aspect two methods of effective dose assessment based on bioassay are considered in the work: (1) traditional indirect method at which application results of workplace monitoring are not taken into account, and (2) a combined method in which both results of bioassay measurements and workplace monitoring are considered

SU-D-201-03: During-Treatment Delivery Monitoring System for TomoTherapy

Energy Technology Data Exchange (ETDEWEB)

Chen, Q; Read, P [University of Virginia, Charlottesville, VA (United States)

2016-06-15

Purpose: Multiple error pathways can lead to delivery errors during the treatment course that cannot be caught with pre-treatment QA. While in vivo solutions are being developed for linacs, no such solution exists for tomotherapy. The purpose of this study is to develop a near real-time system for tomotherapy that can monitor the delivery and dose accumulation process during the treatment-delivery, which enable the user to assess the impact of delivery variations and/or errors and to interrupt the treatment if necessary. Methods: A program running on a tomotherapy planning station fetches the raw DAS data during treatment. Exit detector data is extracted as well as output, gantry angle, and other machine parameters. For each sample, the MLC open-close state is determined. The delivered plan is compared with the original plan via a Monte Carlo dose engine which transports fluence deviations from a pre-treatment Monte Carlo run. A report containing the difference in fluence, dose and DVH statistics is created in html format. This process is repeated until the treatment is completed. Results: Since we only need to compute the dose for the difference in fluence for a few projections each time, dose with 2% statistical uncertainty can be computed in less than 1 second on a 4-core cpu. However, the current bottleneck in this near real-time system is the repeated fetching and processing the growing DAS data file throughout the delivery. The frame rate drops from 10Hz at the beginning of treatment to 5Hz after 3 minutes and to 2Hz after 10 minutes. Conclusion: A during-treatment delivery monitor system has been built to monitor tomotherapy treatments. The system improves patient safety by allowing operators to assess the delivery variations and errors during treatment delivery and adopt appropriate actions.

SU-D-201-03: During-Treatment Delivery Monitoring System for TomoTherapy

International Nuclear Information System (INIS)

Chen, Q; Read, P

2016-01-01

Purpose: Multiple error pathways can lead to delivery errors during the treatment course that cannot be caught with pre-treatment QA. While in vivo solutions are being developed for linacs, no such solution exists for tomotherapy. The purpose of this study is to develop a near real-time system for tomotherapy that can monitor the delivery and dose accumulation process during the treatment-delivery, which enable the user to assess the impact of delivery variations and/or errors and to interrupt the treatment if necessary. Methods: A program running on a tomotherapy planning station fetches the raw DAS data during treatment. Exit detector data is extracted as well as output, gantry angle, and other machine parameters. For each sample, the MLC open-close state is determined. The delivered plan is compared with the original plan via a Monte Carlo dose engine which transports fluence deviations from a pre-treatment Monte Carlo run. A report containing the difference in fluence, dose and DVH statistics is created in html format. This process is repeated until the treatment is completed. Results: Since we only need to compute the dose for the difference in fluence for a few projections each time, dose with 2% statistical uncertainty can be computed in less than 1 second on a 4-core cpu. However, the current bottleneck in this near real-time system is the repeated fetching and processing the growing DAS data file throughout the delivery. The frame rate drops from 10Hz at the beginning of treatment to 5Hz after 3 minutes and to 2Hz after 10 minutes. Conclusion: A during-treatment delivery monitor system has been built to monitor tomotherapy treatments. The system improves patient safety by allowing operators to assess the delivery variations and errors during treatment delivery and adopt appropriate actions.

Eye lens dosimetry for fluoroscopically guided clinical procedures: practical approaches to protection and dose monitoring

International Nuclear Information System (INIS)

Martin, Colin J.

2016-01-01

Doses to the eye lenses of clinicians undertaking fluoroscopically guided procedures can exceed the dose annual limit of 20 mSv, so optimisation of radiation protection is essential. Ceiling-suspended shields and disposable radiation absorbing pads can reduce eye dose by factors of 2-7. Lead glasses that shield against exposures from the side can lower doses by 2.5-4.5 times. Training in effective use of protective devices is an essential element in achieving good protection and acceptable eye doses. Effective methods for dose monitoring are required to identify protection issues. Dosemeters worn adjacent to the eye provide the better option for interventional clinicians, but an unprotected dosemeter worn at the neck will give an indication of eye dose that is adequate for most interventional staff. Potential requirements for protective devices and dose monitoring can be determined from risk assessments using generic values for dose linked to examination workload. (author)

Thermoluminescence and phosphate glass dosimeter systems in the low dose range

International Nuclear Information System (INIS)

Piesch, E.; Burgkhardt, B.

1978-06-01

This report describes a standard test program for TLD and RPL systems worked out by the Working Party on 'Dose Measurement of External Radiation' by the Fachverband fuer Strahlenschutz e.V. to demonstrate the performance of dosimeter systems to be employed in environmental monitoring and in personnel dosimetry. The results of an intercomparison study are outlined in which 17 laboratories from the German speaking countries participated with 43 dosimeter systems. (orig.) [de

Environmental monitoring systems: a new type of mobile laboratory

International Nuclear Information System (INIS)

Bruecher, L.; Langmueller, G.; Tuerschmann, G.

1999-01-01

Nuclear facilities are obligated to monitor the environmental radiation in their vicinity, which is often fulfilled by monitoring cars, combined with fixed monitoring stations. The MOLAR Mobile Laboratory for Environmental Radiation Monitoring as described here is being used under normal and accident conditions as a spot check monitoring system or to perform continuous measurements along a driving track. The mobile laboratories are continuously connected with the control centre's CRCS Central Radiological Computer System, where the RIS Radiological Information System provides corresponding evaluation functions. The mobile labs contain measuring and controlling units like γ-dose rate monitors, γ-spectrometer with a HpGe High Purity Germanium detector, a lead shielded measuring cell and MCA Multi-Channel Analyser, portable β-contamination monitor, α/β/γ multipurpose quick measuring unit, aerosol and iodine sampling units. The collected samples are safely stored for the transport to the environmental laboratory for being analysed later. The geographical location of the moving car is continuously determined by the satellite based GPS Global Positioning System and transferred in the on-board rack mounted computer system for being stored and locally displayed. Real-time data transmission via radio and mobile phone is continuously performed to supply the RIS Radiological Information System in the control centre via radio and mobile phone. The latter also serves for voice communication. Currently three MOLAR systems can be operated parallel and independent from the control centre. The system is ready to be extended to more mobile labs. This combination of mobile monitoring, sample analysis and radiological assessment of environmental data in combination with process occurrences has turned out to be a powerful instrument for emergency preparedness and environmental supervising. (orig.) [de

Analysis of records of external occupational dose records in Brazil; Analise dos registros de dose ocupacional externa no Brasil

Energy Technology Data Exchange (ETDEWEB)

Mauricio, Claudia L.P.; Silva, Herica L.R. da, E-mail: claudia@ird.gov.br, E-mail: herica@ird.gov.br [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ),Rio de Janeiro, RJ (Brazil); Silva, Claudio Ribeiro da, E-mail: claudio@cnen.gov.br [Comissao Nacional de Energia Nuclear (CNEN), Rio de Janeiro, RJ (Brazil)

2014-07-01

Brazil, a continental country, with actually more than 150,000 workers under individual monitoring for ionizing radiation, has implemented in 1987 a centralized system for storage of external occupational dose. This database has been improved over the years and is now a web-based information system called Brazilian External Occupational Dose Management Database System - GDOSE. This paper presents an overview of the Brazilian external occupational dose over the years. The estimated annual average effective dose shows a decrease from 2.4 mSv in 1987 to about 0.6 mSv, having been a marked reduction from 1987 to 1990. Analyzing by type of controlled practice, one sees that the medical and dental radiology is the area with the largest number of users of individual monitors (70%); followed by education practices (8%) and the industrial radiography (7%). Additionally to photon whole body monitoring; neutron monitors are used in maintenance (36%), reactor (30%) and education (27%); and extremity monitors, in education (27%), nuclear medicine (22%) and radiology (19%). In terms of collective dose, the highest values are also found in conventional radiology, but the highest average dose values are those of interventional radiology. Nuclear medicine, R and D and radiotherapy also have average annual effective dose higher than 1 mSv. However, there is some very high dose values registered in GDOSE that give false information. This should be better analyzed in the future. Annual doses above 500 are certainly not realistic. (author)

Operation of radiation monitoring system in radwaste form test facility

International Nuclear Information System (INIS)

Ryu, Young Gerl; Kim, Ki Hong; Lee, Jae Won; Kwac, Koung Kil

1998-08-01

RWFTF (RadWaste Form Test Facility) must have a secure radiation monitoring system (RMS) because of having a hot-cell capable of handling high radioactive materials. And then in controlled radiation zone, which is hot-cell and its maintenance and operation / control room, area dose rate, radioactivities in air-bone particulates and stack, and surface contamination are monitored continuously. For the effective management such as higher utilization, maintenance and repair, the status of this radiation monitoring system, the operation and characteristics of all kinds of detectors and other parts of composing this system, and signal treatment and its evaluation were described in this technical report. And to obtain the accuracy detection results and its higher confidence level, the procedure such as maintenance, functional check and system calibration were established and appended to help the operation of RMS. (author). 6 tabs., 30 figs

Occupational dose estimates for a monitored retrievable storage facility

International Nuclear Information System (INIS)

Harty, R.; Stoetzel, G.A.

1986-06-01

Occupational doses were estimated for radiation workers at the monitored retrievable storage (MRS) facility. This study provides an estimate of the occupational dose based on the current MRS facility design, examines the extent that various design parameters and assumptions affect the dose estimates, and identifies the areas and activities where exposures can be reduced most effectively. Occupational doses were estimated for both the primary storage concept and the alternate storage concept. The dose estimates indicate the annual dose to all radiation workers will be below the 5 rem/yr federal dose equivalent limit. However, the estimated dose to most of the receiving and storage crew (the workers responsible for the receipt, storage, and surveillance of the spent fuel and its subsequent retrieval), to the crane maintenance technicians, and to the cold and remote maintenance technicians is above the design objective of 1 rem/yr. The highest annual dose is received by the riggers (4.7 rem) in the receiving and storage crew. An indication of the extent to which various design parameters and assumptions affect the dose estimates was obtained by changing various design-based assumptions such as work procedures, background dose rates in radiation zones, and the amount of fuel received and stored annually. The study indicated that a combination of remote operations, increased shielding, and additional personnel (for specific jobs) or changes in operating procedures will be necessary to reduce worker doses below 1.0 rem/yr. Operations that could be made at least partially remote include the removal and replacement of the tiedowns, impact limiters, and personnel barriers from the shipping casks and the removal or installation of the inner closure bolts. Reductions of the background dose rates in the receiving/shipping and the transfer/discharge areas may be accomplished with additional shielding

Electrical behavior research of silicon photo-cell used in online monitoring absorbed dose rate of γ-ray

International Nuclear Information System (INIS)

Yang Guixia; Li Xiaoyan; Fu Lan; Wu Wenhao; An You; Zeng Fansong

2015-01-01

The real-time online monitoring system for γ-ray absorbed dose rate was established to study the relationship between the photocurrent of semi-conductive silicon photo-cell BBZSGD-4 and γ-ray absorbed dose rate under the open circuit. The radioactive experiments in "6"0Co γ radiation field show that photo-cell BBZSGD-4 has good response to "6"0Co γ-ray, and their relationship accords with the linear law. The photocurrent of photo-cell can be up to 1.26 μA when the absorbed dose rate is 94.54 Gy/min. The relationship between photocurrent and the absorbed dose accords with exponential law when absorbed dose rate is 50 Gy/min, and the attenuation of photocurrent is 1% when the absorbed dose is 5445.8 Gy. Thus photo-cell BBZSGD-4 has the potential to be a real-time detector to detect low absorbed dose rate in "6"0Co γ radiation field. (authors)

An automated DICOM database capable of arbitrary data mining (including radiation dose indicators) for quality monitoring.

Science.gov (United States)

Wang, Shanshan; Pavlicek, William; Roberts, Catherine C; Langer, Steve G; Zhang, Muhong; Hu, Mengqi; Morin, Richard L; Schueler, Beth A; Wellnitz, Clinton V; Wu, Teresa

2011-04-01

The U.S. National Press has brought to full public discussion concerns regarding the use of medical radiation, specifically x-ray computed tomography (CT), in diagnosis. A need exists for developing methods whereby assurance is given that all diagnostic medical radiation use is properly prescribed, and all patients' radiation exposure is monitored. The "DICOM Index Tracker©" (DIT) transparently captures desired digital imaging and communications in medicine (DICOM) tags from CT, nuclear imaging equipment, and other DICOM devices across an enterprise. Its initial use is recording, monitoring, and providing automatic alerts to medical professionals of excursions beyond internally determined trigger action levels of radiation. A flexible knowledge base, aware of equipment in use, enables automatic alerts to system administrators of newly identified equipment models or software versions so that DIT can be adapted to the new equipment or software. A dosimetry module accepts mammography breast organ dose, skin air kerma values from XA modalities, exposure indices from computed radiography, etc. upon receipt. The American Association of Physicists in Medicine recommended a methodology for effective dose calculations which are performed with CT units having DICOM structured dose reports. Web interface reporting is provided for accessing the database in real-time. DIT is DICOM-compliant and, thus, is standardized for international comparisons. Automatic alerts currently in use include: email, cell phone text message, and internal pager text messaging. This system extends the utility of DICOM for standardizing the capturing and computing of radiation dose as well as other quality measures.

Monitoring System for the Inspection of Vehicle Loads for Radioactivity

International Nuclear Information System (INIS)

Krishnamarchri, G.; Chaudhury, P.; Jain, A.; Kale, M. S.; Pradeepkumar, K. S.; Sharma, D. N.; Venkat Raj, V.

2004-01-01

From the nuclear facilities, inactive scrap may have to be sent periodically for disposal. The scrap is to be monitored to ensure that it is free from inadvertent mix up of contaminated material, which has got the potential of unwanted exposure to people as well as costly and time consuming clean up operations. Earlier the scrap carrying vehicles were monitored manually using portable radiation survey monitors by health physicists. A PC based monitoring system for the inspection of vehicle loads for radioactivity is developed and is in use which requires minimum manual interaction. The advantage of the system is that it can automatically screen all outgoing vehicles from the establishment. The PC based system consists of two detector boxes, each having three Plastic Scintillation detectors of 50 mm dia x 500 mm long. The processing unit is built around a PC addon card. Using the calibration factor (i.e., nGy/h per cps), the dose rate is computed and 'allow' / 'disallow' visual signal is generated in the PC located in a control room. The graphical user interface provides ON / OFF button for controlling the counting process and counting time interval can be set by the user as desired. All the six counters are synchronized for the process of counting. The acquired counts are displayed on the PC screen in the form of a count rate vs. time graph. At the completion of scanning of a vehicle, the counting is continued to acquire background radiation level till the next vehicle arrives. The processing unit estimates the radiation dose rate from these recorded counts by using already established calibration factor and displays the data on the monitor screen of the computer. If the determined dose rate exceeds the pre determined limit, an audio alarm is initiated and the alarm information is displayed on the monitor of the computer. The system has provision to enter information like vehicle registration number, type of the vehicle, origin of the load, destination etc. These

Monitoring of dose rates and radiation flux density in working rooms

International Nuclear Information System (INIS)

Krajtor, S.N.

1980-01-01

The problems of determining the neutron field characteristics (dose equivalent rate and flux density) in relation to the environmental monitoring by radiation protection services. The measurement devices used for measuring dose equivalent rate and neutron flux density RUS-U8 multi-purpose scintillation radiometer and RUP-1 multi-purpose transportable radiometer as well as measurement technique are described. Recommendations are given for checking measuring devices calibration, registering measurement results [ru

Independent dose per monitor unit review of eight U.S.A. proton treatment facilities

International Nuclear Information System (INIS)

Moyers, M. F.; Ibbott, G. S.; Grant, R. L.; Summers, P. A.; Followill, D. S.

2014-01-01

Purpose: Compare the dose per monitor unit at different proton treatment facilities using three different dosimetry methods. Methods: Measurements of dose per monitor unit were performed by a single group at eight facilities using 11 test beams and up to six different clinical portal treatment sites. These measurements were compared to the facility reported dose per monitor unit values. Results: Agreement between the measured and reported doses was similar using any of the three dosimetry methods. Use of the ICRU 59 N D,w based method gave results approximately 3% higher than both the ICRU 59 N X and ICRU 78 (TRS-398) N D,w based methods. Conclusions: Any single dosimetry method could be used for multi-institution trials with similar conformity between facilities. A multi-institutional trial could support facilities using both the ICRU 59 N X based and ICRU 78 (TRS-398) N D,w based methods but use of the ICRU 59 N D,w based method should not be allowed simultaneously with the other two until the difference is resolved

Review of personal monitoring techniques for the measurement of absorbed dose from external beta and low energy photon radiation

DEFF Research Database (Denmark)

Christensen, Poul

1986-01-01

The techniques available at present for personal monitoring of doses from external beta and low energy photon radiation are reviewed. The performance of currently used dosimetry systems is compared with that recommended internationally, and developments for improving the actual performance...

REMIT5.1, Radiation exposure monitoring and information transmittal system

International Nuclear Information System (INIS)

2007-01-01

1 - Description of program or function - The Radiation Exposure Monitoring and Information Transmittal (REMIT) is a PC-based menu driven system that facilitates the manipulation of data base files to record and report radiation exposure information. REMIT is designed to be user-friendly and contains the full text of Regulatory Guide 8.7, Rev.1, on-line as well as context-sensitive help throughout the program. The user can enter data directly from NRC Forms 4 or 5. REMIT allows the user to view the individual's exposure in relation to regulatory or administrative limits and will alert the user to exposures in excess of these limits. The system also provides for the calculation and summation of dose from intakes and the determination of the dose to the maximally exposed extremity for the monitoring year. REMIT can produce NRC Forms 4 and 5 in paper and electronic format and can import/export data from ASCII and data base files. Additional information is available from the web page www.reirs.com. REMIT system is designed to assist U.S. Nuclear Regulatory Commission (NRC) licensees in meeting the reporting requirements of the Revised 10 CFR Parts 20.1001 through 20.2401 as outlined in Regulatory Guide 8.7, Rev.1, Instructions for Recording and Reporting Occupational Exposure Data. 2 - Methods - REMIT makes use of the dose conversion factors from EPA Report 11 Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submission, and Ingestion, to calculate the Committed Dose Equivalent to the maximally exposed organ and the Committed Effective Dose Equivalent from intakes measured in microcuries. REMIT also estimates the amount (in micrograms) of uranium intake from the activity entered in microcuries. This calculation is based on the specific activities of the uranium isotopes. 3 - Restrictions on the complexity of the problem - None noted

SU-E-I-10: Automatic Monitoring of Accumulated Dose Indices From DICOM RDSR to Improve Radiation Safety in X-Ray Angiography

International Nuclear Information System (INIS)

Omar, A; Bujila, R; Nowik, P; Karambatsakidou, A

2014-01-01

Purpose: To investigate the potential benefits of automatic monitoring of accumulated patient and staff dose indicators, i.e., CAK and KAP, from DICOM Radiation Dose Structured Reports (RDSR) in x-ray angiography (XA). Methods: Recently RDSR has enabled the convenient aggregation of dose indices and technique parameters for XA procedures. The information contained in RDSR objects for three XA systems, dedicated to different types of clinical procedures, has been collected and aggregated in a database for over one year using a system developed with open-source software at the Karolinska University Hospital. Patient weight was complemented to the RDSR data via an interface with the Hospital Information System (HIS). Results: The linearly approximated trend in KAP over a time period of a year for cerebrovascular, pelvic/peripheral vascular, and cardiovascular procedures showed a decrease of 12%, 20%, and 14%, respectively. The decrease was mainly due to hardware/software upgrades and new low-dose imaging protocols, and partially due to ongoing systematic radiation safety education of the clinical staff. The CAK was in excess of 3 Gy for 15 procedures, and exceeded 5 Gy for 3 procedures. The dose indices have also shown a significant dependence on patient weight for cardiovascular and pelvic/peripheral vascular procedures; a 10 kg shift in mean patient weight can result in a dose index increase of 25%. Conclusion: Automatic monitoring of accumulated dose indices can be utilized to notify the clinical staff and medical physicists when the dose index has exceeded a predetermined action level. This allows for convenient and systematic follow-up of patients in risk of developing deterministic skin injuries. Furthermore, trend analyses of dose indices over time is a valuable resource for the identification of potential positive or negative effects (dose increase/decrease) from changes in hardware, software, and clinical work habits

SU-E-I-10: Automatic Monitoring of Accumulated Dose Indices From DICOM RDSR to Improve Radiation Safety in X-Ray Angiography

Energy Technology Data Exchange (ETDEWEB)

Omar, A; Bujila, R; Nowik, P; Karambatsakidou, A [Karolinska University Hospital, Stockholm (Sweden)

2014-06-01

Purpose: To investigate the potential benefits of automatic monitoring of accumulated patient and staff dose indicators, i.e., CAK and KAP, from DICOM Radiation Dose Structured Reports (RDSR) in x-ray angiography (XA). Methods: Recently RDSR has enabled the convenient aggregation of dose indices and technique parameters for XA procedures. The information contained in RDSR objects for three XA systems, dedicated to different types of clinical procedures, has been collected and aggregated in a database for over one year using a system developed with open-source software at the Karolinska University Hospital. Patient weight was complemented to the RDSR data via an interface with the Hospital Information System (HIS). Results: The linearly approximated trend in KAP over a time period of a year for cerebrovascular, pelvic/peripheral vascular, and cardiovascular procedures showed a decrease of 12%, 20%, and 14%, respectively. The decrease was mainly due to hardware/software upgrades and new low-dose imaging protocols, and partially due to ongoing systematic radiation safety education of the clinical staff. The CAK was in excess of 3 Gy for 15 procedures, and exceeded 5 Gy for 3 procedures. The dose indices have also shown a significant dependence on patient weight for cardiovascular and pelvic/peripheral vascular procedures; a 10 kg shift in mean patient weight can result in a dose index increase of 25%. Conclusion: Automatic monitoring of accumulated dose indices can be utilized to notify the clinical staff and medical physicists when the dose index has exceeded a predetermined action level. This allows for convenient and systematic follow-up of patients in risk of developing deterministic skin injuries. Furthermore, trend analyses of dose indices over time is a valuable resource for the identification of potential positive or negative effects (dose increase/decrease) from changes in hardware, software, and clinical work habits.

Online remote radiological monitoring during operation of Advance Vitrification System (AVS), Tarapur

International Nuclear Information System (INIS)

Deokar, U.V.; Kulkarni, V.V.; Mathew, P.; Khot, A.R.; Singh, K.K.; Kamlesh; Deshpande, M.D.; Kulkarni, Y.

2010-01-01

Advanced Vitrification System (AVS) is commissioned for vitrification of high level waste (HLW) by using Joule heated ceramic melter first time in India. The HLW is generated in fuel reprocessing plant. For radiological surveillance of plant, Health Physics Unit (HPU) had installed 37 Area Gamma Monitors (AGM), 7 Continuous Air Monitors (CAM) and all types of personal contamination monitors. Exposure control is a major concern in operating plant. Therefore in addition to installed monitors, we have developed online remote radiation monitoring system to minimize exposures to the surveyor and operator. This also helped in volume reduction of secondary waste. The reliability and accuracy of the online monitoring system is confirmed by calibrating the system by comparing TLD and DRD readings and by theoretical analysis. In addition some modifications were carried in HP instruments to make them user friendly. This paper summarizes different kinds of remote radiological monitoring systems installed for online monitoring of Melter off Gas (MOG) filter, Hood filter, three exhaust filter banks, annulus air sampling and over pack monitoring in AVS. Our online remote monitoring system has helped the plant management to plan in advance for replacement of these filters, which resulted in considerable saving of collective dose. (author)

Biological monitoring to determine worker dose in a butadiene processing plant

Energy Technology Data Exchange (ETDEWEB)

Bechtold, W.E.; Hayes, R.B. [National Cancer Inst., Bethesda, MD (United States)

1995-12-01

Butadiene (BD) is a reactive gas used extensively in the rubber industry and is also found in combustion products. Although BD is genotoxic and acts as an animal carcinogen, the evidence for carcinogenicity in humans is limited. Extrapolation from animal studies on BD carcinogenicity to risk in humans has been controversial because of uncertainties regarding relative biologic exposure and related effects in humans vs. experimental animals. To reduce this uncertainty, a study was designed to characterize exposure to BD at a polymer production facility and to relate this exposure to mutational and cytogenetic effects. Biological monitoring was used to better assess the internal dose of BD received by the workers. Measurement of 1,2-dihydroxy-4-(N-acetylcysteinyl) butane (M1) in urine served as the biomarker in this study. M1 has been shown to correlate with area monitoring in previous studies. Most studies that relate exposure to a toxic chemical with its biological effects rely on exposure concentration as the dose metric; however, exposure concentration may or may not reflect the actual internal dose of the chemical.

Occupational dose assessment and national dose registry system in Iran

International Nuclear Information System (INIS)

Jafari-Zadeh, M.; Nazeri, F.; Hosseini-Pooya, S. M.; Taheri, M.; Gheshlaghi, F.; Kardan, M. R.; Babakhani, A.; Rastkhah, N.; Yousefi-Nejad, F.; Darabi, M.; Oruji, T.; Gholamali-Zadeh, Z.; Karimi-Diba, J.; Kazemi-Movahed, A. A.; Dashti-Pour, M. R.; Enferadi, A.; Jahanbakhshian, M. H.; Sadegh-Khani, M. R.

2011-01-01

This report presents status of external and internal dose assessment of workers and introducing the structure of National Dose Registry System of Iran (NDRSI). As well as types of individual dosemeters in use, techniques for internal dose assessment are presented. Results obtained from the International Atomic Energy Agency intercomparison programme on measurement of personal dose equivalent H p (10) and consistency of the measured doses with the delivered doses are shown. Also, implementation of dosimetry standards, establishment of quality management system, authorisation and approval procedure of dosimetry service providers are discussed. (authors)

Vehicle Radiation Monitoring Systems for Medical Waste Disposal - 12102

Energy Technology Data Exchange (ETDEWEB)

Kondrashov, Vladislav S.; Steranka, Steve A. [RadComm Systems Corp., 2931 Portland Dr., Oakville, ON L6H 5S4 (Canada)

2012-07-01

Hospitals often declare their waste as being 'non-radioactive'; however this material often has excessive levels of radiation caused either by an accident or lack of control. To ensure the best possible protection against the accidental receipt of radioactive materials and as a safety precaution for their employees, waste-handling companies have installed large-scale radiation portal monitors at their weigh scales or entry gates of the incinerator plant, waste transfer station, and/or landfill. Large-volume plastic scintillator-based systems can be used to monitor radiation levels at entry points to companies handling medical waste. The recent and intensive field tests together with the thousands of accumulated hours of actual real-life vehicle scanning have proven that the plastic scintillation based system is an appropriate radiation control instrument for waste management companies. The Real-Time background compensation algorithm is flexible with automatic adjustable coefficients that will response to rapidly changing environmental and weather conditions maintaining the preset alarm threshold levels. The Dose Rate correction algorithms further enhance the system's ability to meet the stringent requirements of the waste industries need for Dose Rate measurements. (authors)

Absorbed dose measurement by the MIRD system in the 131-I treated Thyroid Cancer patients

Energy Technology Data Exchange (ETDEWEB)

Hong, Seong Woon; Lim, Sang Mu; Kim, Chang Hui; Kim, Ki Sub; Cho, Jong Sio; Jeong, Jin Sung; Park, Heung Kyu; Kwon, Oh Jin [Korea Cancer Center Hospital, Seoul (Korea, Republic of)

1995-12-01

Medical Internal Radiation Dose(MIRD) schema was developed for calculating the absorbed dose from the administrated radiopharmaceuticals. With the biological distribution data and physical properties of the radionuclide, we can estimated the absorbed dose by the MIRD schema. For the thyroid cancer patients received high dose 131-I therapy, the absorbed dose to the bone marrow is limiting factor to the administered dose and the duration of admission is determined by the retained activity in the whole body. To the monitoring of whole body radioactivity, we used Eberline Smart 200 system using ionization chamber as a detector. With the time activity (Author).

Monitoring and assessment of individual doses of occupationally exposed workers due to intake of radionuclides

International Nuclear Information System (INIS)

Alexander, O. A.

2014-04-01

Monitoring and estimation of individual intakes of radionuclides can be complex. Doses of intakes cannot be measured directly, however must be assessed from the monitoring data of the individual. The individual monitoring data includes whole body counting, excretion analysis (urine or faecal). In the estimation of these data requires that the assessor makes assumptions about the exposure scenario, including the pattern and mode of radionuclide intake. Also physicochemical characteristics of the material involved and the period of time between exposure and measurement. This project report seeks to provide some underlying guidance on monitoring programmes and data interpretation using case study. In this present study the committed effective dose (CED) 1.20mSv exceeded the recording level (i.e. 1mSv) however it was below the investigation level (i.e. 2mSv). The present study recommends that as an essential part in internal dosimetry, specialists be capable of recognizing conditions warranting follow-up bioassay and dose evaluation. Personnel should be familiar with the relevant internal dosimetry literature and the recommendations of national and international scientific organizations with regard to internal dose. (au)

Radiation exposure control by estimation of multiplication factors for online remote radiation monitoring systems at Vitrification Plant

International Nuclear Information System (INIS)

Deokar, Umesh V.; Kukarni, V.V.; Khot, A.R.; Mathew, P.; Kamlesh; Purohit, R.G.; Sarkar, P.K.

2011-01-01

Vitrification Plant is commissioned for vitrification of high-level liquid waste generated in Nuclear Fuel Cycle operations by using Joule Heated Ceramic Melter first time in India. Exposure control is a major concern in operating plant. Therefore, in addition to installed monitors, we have developed online remote radiation monitoring system to minimize number of entries in amber areas and to reduce the exposure to the surveyor and operator. This also helped in volume reduction of secondary waste. The reliability and accuracy of the online monitoring system is confirmed with actual measurements and by theoretical shielding calculations. The multiplication factors were estimated for remote online monitoring of Melter off Gas (MOG) filter, Hood filter, three exhaust filter banks, and overpack monitoring. This paper summarizes how the online remote monitoring system had helped in saving of 128.52 Person-mSv collective dose (14.28% of budgeted dose) and also there was 2.6 m 3 reduction in generation of Cat-I waste. (author)

Doses of the staff during the spent fuel assemblies transportation and storage in Nuhmos 56V concrete system

International Nuclear Information System (INIS)

Atoyan, V.; Muradyan, A.

2003-01-01

The NUHMOS 56V concrete system provides long-term interim storage (50 years) for spent fuel assemblies, which have been out of the reactor for a sufficient period of time. It consists from horizontal storage modules. The fuel assemblies are confined in a helium atmosphere by a canister containment pressure vessel. The canister is protected and shielded by a massive reinforced concrete module. Decay heat is removed from the canister and concrete module by a passive natural draft convection ventilation system. The project of storage does not foresee the radiation monitoring inside of building and around it. But we provided and realize the radiation monitoring program around storage, it includes tree phases: - determination the zero background around the building before storage put in exploiting; - monitoring of the radioactive particles in air (additional aspiration plant); dose rate monitoring by portable dosimeters and soil monitoring during the process of the fuel storage; - constantly after the completion the fuel storage process - monitoring of the radioactive particles in air (additional aspiration plant); dose rate monitoring by portable dosimeters, and soil monitoring. Also designed the dose rate monitoring by the dosimeter RME 3 with the transfer of data by radio channel to central monitor. The canistered spent fuel assemblies are transferred from the plant's spent fuel pool to the concrete storage modules in a transfer cask. The cask is aligned with the storage module and the canister and inserted into the module by means of a hydraulic ram. The system is a totally passive installation that is designed to provide shielding and safe confinement of spent fuel for a range of postulated accident conditions and natural phenomena. (authors)

Occlusion dose monitoring in amblyopia therapy: status, insights, and future directions.

Science.gov (United States)

Stewart, Catherine E; Moseley, Merrick J; Georgiou, Pantelis; Fielder, Alistair R

2017-10-01

Occlusion therapy remains the mainstay treatment of amblyopia, but its outcome is not assured or universally excellent. Many factors are known to influence treatment outcome, among which compliance is foremost. The occlusion dose monitor (ODM) removes one variable from the treatment equation, because it records the occlusion actually received by-rather than prescribed for-the child. Improvement observed can thus be quantitatively related to the patching received. This review summarizes the insights the ODM has provided to date particularly in elucidating the dose-response relationship. We are entering the era of personalized ophthalmology in which treatments will be tailored to the needs of the individual child and facilitated by the use of wearable monitors. Copyright © 2017 American Association for Pediatric Ophthalmology and Strabismus. Published by Elsevier Inc. All rights reserved.

Meteorological monitoring for environmental/dose assessment and emergency response modeling: How much is enough?

International Nuclear Information System (INIS)

Glantz, C.S.

1989-01-01

In evaluation the effectiveness and appropriateness of meteorological monitoring programs, managers responsible for planning and operating emergency response or environmental/dose assessment systems must routinely question whether enough meteorological data are being obtained to adequately support system applications. There is no simple answer or cookbook procedure that can be followed in generating an appropriate answer to this question. The answer must be developed through detailed consideration of the intended applications for the data, the capabilities of the models that would use the data, pollutant release characteristics, terrain in the modeling region, the size of the modeling domain, and the distribution of human population in the modeling domain. It is recommended that manager consult meteorologists when assessing these factors; the meteorologist's detailed knowledge of, and experience in, studying atmospheric transport and diffusion should assist the manager in determining the appropriate level of meteorological monitoring. 1 ref

Professional exposure of medical workers: radiation levels, radiation risk and personal dose monitoring

International Nuclear Information System (INIS)

Bai Guang

2005-01-01

The application of radiation in the field of medicine is the most active area. Due to the rapid and strong development of intervention radiology at present near 20 years, particularly, the medical workers become a popularize group which most rapid increasing and also receiving the must high of professional exposure dose. Because, inter alias, radiation protection management nag training have not fully follow up, the aware of radioactive protection and appropriate approach have tot fully meet the development and need, the professional exposure dose received by medical workers, especially those being engaged in intervention radiology, are more higher, as well as have not yet fully receiving the complete personal dose monitoring, the medical workers become the population group which should be paid the most attention to. The writer would advice in this paper that all medical workers who being received a professional radiation exposure should pay more attention to the safety and healthy they by is strengthening radiation protection and receiving complete personal dose monitoring. (authors)

Study and project of a radiation monitoring system in ships

International Nuclear Information System (INIS)

Morgado, Mario Monteiro

1998-01-01

In this work we present the project and the development of a radiation detection system for use in ships, called RADINAC. This system was developed to measure the radiation in several points of the ship and to give the dose rates and total dose. The radioactive activity of the sea water is also measured. The project was based on a system developed in the middle of the seventies which is not working due to the lack of some mechanical and electronic components. The RADINAC system was developed in order to nationalize and modernize the old project. The detectors used are plastic scintillator to measure the sea water radioactive activity and ionization chambers to measure the dose rates. The nuclear instrumentation has only three imported items: acquisition data board, picoamperimeter and photomultiplier tube. All the other items are made in Brazil. With regard to the data acquisition, we used the Labwindows software to create the 'virtual instruments' in order to display the data on the computer monitor. (author)

Radiation monitoring and dose distribution of medical workers in A.P. state 1999-2000

International Nuclear Information System (INIS)

Singh, D.R.; Reddy, K.S.; Kamble, M.K.; Roy, Madhumita

2001-01-01

Individual monitoring for external ionizing radiation is being conducted for all radiation workers in Andhra Pradesh State by TLD Unit located in Nuclear Fuel Complex, Hyderabad.The Unit comes under Personnel Monitoring Section of Bhabha Atomic Research Center, Mumbai. The aim of monitoring is to confirm that the radiation safety standards are strictly adhered in the institutions and also to investigate excessive exposures, if any. Personnel monitoring also provides data for epidemiological studies. In view of ICRP/AERB recommendations of 100 mSv dose limit for the five years block of 1994-98, the dose distribution among radiation workers in Andhra Pradesh State is analyzed for the period 1994-98. In continuation of above work, we have analyzed the data for the year 1999-2000 for various medical diagnostic procedures and these are presented

Environmental gamma radiation monitoring system with a large volume air ionization chamber

International Nuclear Information System (INIS)

Duftschmid, K.E.; Strachotinsky, C.; Witzani, J.

1986-01-01

An improved environmental monitoring system has been designed and tested consisting of an ionization chamber with 120 l sensitive volume, operated at atmospheric pressure, and a commercial electrometer amplifier with digital voltmeter. The system is controlled by a desk calculator with printer for automated operation and calculation of dose and doserate. The ionization chamber provides superior dosimetric performance as compared to usual GM-counters and high pressure chambers. The system has been field-tested during the 'European Intercomparison Programme for Environmental Monitoring Instruments' organized by the Commission of the European Communities. (Author)

Analysis of data on radon monitoring and dose estimates for uranium mines

International Nuclear Information System (INIS)

Khan, A.H.; Srivastava, G.K.; Jha, Shankar; Sagar, D.V.

1994-01-01

Radon progeny are the major contributors to the radiation dose to uranium miners. Monitoring for radon and gamma radiation is an integral part of radiation protection in such mines. Data for equilibrium equivalent radon and the estimated mean annual doses are presented in this paper for Jaduguda uranium mine from 1986 to 1992. The 1992 data for Jaduguda and Bhatin mines are compared. The average annual effective dose for uranium miners is estimated at around 15.5 mSv. (author). 1 ref., 2 figs

A yeast screening system for simultaneously monitoring multiple genetic endpoints

International Nuclear Information System (INIS)

Dixon, M.L.; Mortimer, R.K.

1986-01-01

Mutation, recombination, and mitochondrial deficiencies have been proposed to have roles in the carcinogenic process. The authors describe a diploid strain of the yeast Saccharomyces cerevisiae capable of detecting this wide spectrum of genetic changes. The markers used for monitoring these events have been especially well characterized genetically. Ultraviolet light was chosen as a model carcinogenic agent to test this system. In addition to highly significant increases in the frequencies of each genetic change, increases in the absolute numbers of each change indicated induction and not selective survival. The relative amounts of each type of genetic change varied with dose. The wide spectrum of endpoints monitored in the XD83 yeast system may allow the detection of certain carcinogens and other genetically toxic agents which have escaped detection in more limited systems. Since only one strain is required to simultaneously monitor these genetic changes, this assay system should facilitate comparisons of the induced changes and be more efficient than using multiple strains to monitor the same endpoints. (Auth.)

Personalized Feedback on Staff Dose in Fluoroscopy-Guided Interventions: A New Era in Radiation Dose Monitoring.

Science.gov (United States)

Sailer, Anna M; Vergoossen, Laura; Paulis, Leonie; van Zwam, Willem H; Das, Marco; Wildberger, Joachim E; Jeukens, Cécile R L P N

2017-11-01

Radiation safety and protection are a key component of fluoroscopy-guided interventions. We hypothesize that providing weekly personal dose feedback will increase radiation awareness and ultimately will lead to optimized behavior. Therefore, we designed and implemented a personalized feedback of procedure and personal doses for medical staff involved in fluoroscopy-guided interventions. Medical staff (physicians and technicians, n = 27) involved in fluoroscopy-guided interventions were equipped with electronic personal dose meters (PDMs). Procedure dose data including the dose area product and effective doses from PDMs were prospectively monitored for each consecutive procedure over an 8-month period (n = 1082). A personalized feedback form was designed displaying for each staff individually the personal dose per procedure, as well as relative and cumulative doses. This study consisted of two phases: (1) 1-5th months: Staff did not receive feedback (n = 701) and (2) 6-8th months: Staff received weekly individual dose feedback (n = 381). An anonymous evaluation was performed on the feedback and occupational dose. Personalized feedback was scored valuable by 76% of the staff and increased radiation dose awareness for 71%. 57 and 52% reported an increased feeling of occupational safety and changing their behavior because of personalized feedback, respectively. For technicians, the normalized dose was significantly lower in the feedback phase compared to the prefeedback phase: [median (IQR) normalized dose (phase 1) 0.12 (0.04-0.50) µSv/Gy cm 2 versus (phase 2) 0.08 (0.02-0.24) µSv/Gy cm 2 , p = 0.002]. Personalized dose feedback increases radiation awareness and safety and can be provided to staff involved in fluoroscopy-guided interventions.

Radiation area monitoring by wireless-communicating area monitor with surveillance camera

International Nuclear Information System (INIS)

Shimura, Mitsuo; Kobayashi, Hiromitsu; Kitahara, Hideki; Kobayashi, Hironobu; Okamoto, Shinji

2004-01-01

Aiming at a dose reduction and a work efficiency improvement for nuclear power plants that have high dose regions, we have developed our system of wireless-communicating Area Monitor with Surveillance Camera, and have performed an on-site test. Now we are implementing this Area Monitor with Surveillance Camera for a use as a TV camera in the controlled-area, which enables a personal computer to simultaneously display two or more dose values and site live images on the screen. For the radiation detector of this Area Monitor System, our wireless-communicating dosimeter is utilized. Image data are transmitted via a wireless Local Area Network (LAN). As a test result, image transmission of a maximum of 20 frames per second has been realized, which shows that this concept is a practical application. Remote-site monitoring also has been realized from an office desk located within the non-controlled area, adopting a Japan's wireless phone system, PHS (Personal Handy Phone) for the transmission interface. (author)

Study of response of radiation monitors for environmental dose equivalent measurements

International Nuclear Information System (INIS)

Souza, Macilene N.; Khoury, H.J.

2005-01-01

The environmental dose equivalent H * (10), is the magnitude recommended by ICRU 39 for environmental monitoring in fields of radiation of photons. Most of the equipment used for area monitoring, only quantifies the magnitudes exposure or dose not being designed to this new magnitude. In Brazil, particularly, is not yet regulated the use of H * (10). However, with the revision of the standard 3.01 it will necessary the use of monitors that allow the achievement of measures according to H * (10). The transition for using new magnitudes will be a slow process and the contribution that the laboratories of metrology of ionizing radiation in the country can give is, at first, promote and create the habit of using the unit Sievert (Sv) in the calibration of the instruments, and that is the unit recommended for H * (10). In a second step, the tests for determining the response of the instruments for H * (10) should be made and this is the harder step, taking into account the large number of area monitors around the country. These tests will provide information about the limitations of the instrument to the new magnitude, that is, the range where the instrument will have the best performance in quantification of new magnitude. This paper evaluates the performance for H * (10), with the variation of energy and angle of incidence of radiation, of three of the most used monitors in the country

The Impact of AUC-Based Monitoring on Pharmacist-Directed Vancomycin Dose Adjustments in Complicated Methicillin-Resistant Staphylococcus aureus Infection.

Science.gov (United States)

Stoessel, Andrew M; Hale, Cory M; Seabury, Robert W; Miller, Christopher D; Steele, Jeffrey M

2018-01-01

This study aimed to assess the impact of area under the curve (AUC)-based vancomycin monitoring on pharmacist-initiated dose adjustments after transitioning from a trough-only to an AUC-based monitoring method at our institution. A retrospective cohort study of patients treated with vancomycin for complicated methicillin-resistant Staphylococcus aureus (MRSA) infection between November 2013 and December 2016 was conducted. The frequency of pharmacist-initiated dose adjustments was assessed for patients monitored via trough-only and AUC-based approaches for trough ranges: 10 to 14.9 mg/L and 15 to 20 mg/L. Fifty patients were included: 36 in the trough-based monitoring and 14 in the AUC-based-monitoring group. The vancomycin dose was increased in 71.4% of patients when troughs were 10 to 14.9 mg/L when a trough-only approach was used and in only 25% of patients when using AUC estimation ( P = .048). In the AUC group, the dose was increased only when AUC/minimum inhibitory concentration (MIC) AUC/MIC ≥400. The AUC-based monitoring did not significantly increase the frequency of dose reductions when trough concentrations were 15 to 20 mg/L (AUC: 33.3% vs trough: 4.6%; P = .107). The AUC-based monitoring resulted in fewer patients with dose adjustments when trough levels were 10 to 14.9 mg/L. The AUC-based monitoring has the potential to reduce unnecessary vancomycin exposure and warrants further investigation.

Monitoring dose-length product in computed tomography of the chest considering sex and body weight

International Nuclear Information System (INIS)

Inoue, Yusuke; Nagahara, Kazunori; Hayakawa, Naomichi; Hanawa, Hironori; Hata, Hirofumi

2016-01-01

Dose-length product (DLP) is widely used as an indicator of the radiation dose in computed tomography. The aim of this study was to investigate the significance of sex and body weight in DLP-based monitoring of the radiation dose. Eight hundred computed tomographies of the chest performed using four different scanners were analysed. The DLP was compared with body weight by linear regression in men and women separately. The DLP was positively correlated with body weight, and dependence on sex and weight differed among scanners. Standard DLP values adjusted for sex and weight facilitated inter-scanner comparison of the radiation dose and its dependence on sex and weight. Adjusting the DLP for sex and weight allowed one to identify examinations with possibly excessive doses independently of weight. Monitoring the DLP in relation to sex and body weight appears to aid detailed comparison of the radiation dose among imaging protocols and scanners and daily observations to find unexpected variance. (authors)

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

The Brazilian external individual monitoring scenario

International Nuclear Information System (INIS)

Mauricio, Claudia L.P.; Silva, Claudio R. da; Cunha, Paulo G. da

2015-01-01

In order to improve radiation protection it is necessary to have knowledge of the occupational radiation dose levels in all radiation facilities. This information comes from individual monitoring services, which are responsible for measuring and providing information about workers' radiation exposure. In 1981, the Comissao Nacional de Energia Nuclear (CNEN) of Brazil starts to develop a comprehensive system for regulation and storage of occupational radiation dose. This paper starts with an overview of the evolution of the Brazilian authorization and data storage system for external individual monitoring. It starts with a rule for authorization of all Brazilian photon individual monitoring services and the obligation for them to send the measured dose to CNEN. Up to now there is no regulation for neutron individual monitoring. The aim of this paper is to present the current scenario of the Brazilian external monitoring system, reinforcing its importance and remaining problems. The number of monitored workers greatly increases every year, having surpassed 150,000 people monitored. The stored data show that the mean annual occupational external dose is decreasing from 2.4 mSv in 1987 to about 0.6 mSv, in 2012, but there is still some not realistic very high dose measured (higher than 100 mSv), without investigation. About 80% of the annual dose values are lower than the monthly register level. As expected, the higher real photon doses are found in Nuclear Medicine, Industrial Radiology and Interventional Radiology. All recorded annual neutron dose values are lower than 20 mSv. (author)

Diffraction measurements using the LHC Beam Loss Monitoring System

Science.gov (United States)

Kalliokoski, Matti

2017-03-01

The Beam Loss Monitoring (BLM) system of the Large Hadron Collider protects the machine from beam induced damage by measuring the absorbed dose rates of beam losses, and by triggering beam dump if the rates increase above the allowed threshold limits. Although the detection time scales are optimized for multi-turn losses, information on fast losses can be recovered from the loss data. In this paper, methods in using the BLM system in diffraction studies are discussed.

Development of γ dose rate monitor based on FPGA and single-chip microcomputer

International Nuclear Information System (INIS)

He Zhiguo; Ling Qiu; Guo Lanying; Yang Binhua

2009-01-01

A novelγdose rate monitor with multiple channels signal collection in which takes the FPGA as the core process chip and single-chip microcomputer as the data processor had been developed. This paper introduced the communication interface design between FPGA and MCU, and gave the data acquisition module and the function simulation chart designed by FPGA. In addition, the software and hardware design diagrams of MCU had been given in this paper. The maximum digitallization was carried on in the designing process. The experiments showed that the scheme for the system matched to the requests completely. (authors)

Development of a portable system to test area monitors for neutrons

International Nuclear Information System (INIS)

Souza, Luciane de Rezende

2011-02-01

The objective is to develop a portable system to test the reliability in terms of calibration of area monitors for neutrons. For the production of this system, thickness and location of the source within the system were simulated using the code of radiation transport MCNP5. The thicknesses were set for a 241 Am-Be source with an activity of 395 mCi, which will be in a polyethylene cylinder which will provide a ambient dose equivalent rate chosen through the points of calibration settings' used by the Laboratory of Neutrons (IRD / CNEN). The results obtained in this study show the feasibility of mounting the portable system as a tool to test the area monitors for neutrons, which will provide the user of neutron area monitors to check the instrument's response in the same field of operation, thus avoiding the use of an inadequate equipment. (author)

Visualization of radiation dose big data acquired by monitoring posts

International Nuclear Information System (INIS)

Hashimoto, Takeyuki; Jumonji, Hiromichi

2014-01-01

Currently, in Fukushima Prefecture, 3625 radiation dose monitoring posts is available, and the radiation data is acquired every 10 minutes. However, an effective visualization of such an enormous amount of data has not been sufficiently performed. In this study, pull out the meaningful information from the big data, to achieve an effective visualization. By comparing the physical attenuation with the radiation dose changes, we can predict the trend of environment attenuation. We visualize the influence of the environment by plotting the results to the map. As a result, the difference in the increase or decrease depending on the location appeared. Under the influence of snow cover, a phenomenon that radiation dose is reduced in winter were also seen. We considered that these results will be effective for the policies of decontamination and the estimation of the amount of snow as water resources. (author)

An automated dose tracking system for adaptive radiation therapy.

Science.gov (United States)

Liu, Chang; Kim, Jinkoo; Kumarasiri, Akila; Mayyas, Essa; Brown, Stephen L; Wen, Ning; Siddiqui, Farzan; Chetty, Indrin J

2018-02-01

The implementation of adaptive radiation therapy (ART) into routine clinical practice is technically challenging and requires significant resources to perform and validate each process step. The objective of this report is to identify the key components of ART, to illustrate how a specific automated procedure improves efficiency, and to facilitate the routine clinical application of ART. Data was used from patient images, exported from a clinical database and converted to an intermediate format for point-wise dose tracking and accumulation. The process was automated using in-house developed software containing three modularized components: an ART engine, user interactive tools, and integration tools. The ART engine conducts computing tasks using the following modules: data importing, image pre-processing, dose mapping, dose accumulation, and reporting. In addition, custom graphical user interfaces (GUIs) were developed to allow user interaction with select processes such as deformable image registration (DIR). A commercial scripting application programming interface was used to incorporate automated dose calculation for application in routine treatment planning. Each module was considered an independent program, written in C++or C#, running in a distributed Windows environment, scheduled and monitored by integration tools. The automated tracking system was retrospectively evaluated for 20 patients with prostate cancer and 96 patients with head and neck cancer, under institutional review board (IRB) approval. In addition, the system was evaluated prospectively using 4 patients with head and neck cancer. Altogether 780 prostate dose fractions and 2586 head and neck cancer dose fractions went processed, including DIR and dose mapping. On average, daily cumulative dose was computed in 3 h and the manual work was limited to 13 min per case with approximately 10% of cases requiring an additional 10 min for image registration refinement. An efficient and convenient

Monitoring device for radioactive leakage from steam system in nuclear power plant

International Nuclear Information System (INIS)

Ogawa, Tateo; Sato, Kohei

1988-01-01

Purpose: To improve the reliability for the monitor of radio-active leakage by accumulating small quantity of radioactivities each lower than the detectable level and increasing their dose rate. Constitution: Even if the steam system radiation monitor in the nuclear power plant is disposed for the detection of in-leak radioactivity, radioactive leakage can be monitored at high reliability by increasing the small quantity of radioactivities in the drains to a detectable sensitivity range of the monitor upon detection. In view of the above, in the present invention, radioactive material catching medium is incorporated to a radio-activity monitor spool piece for accumulating small quantity of radioactivities. Specifically as the catching medium, an ion exchange resin is used for the leakage of ionic radioactive material, while an ion exchange resin increased with the mixing ratio of a cationic resin or hollow thread membrane filter is used for crud-like radioactive material leakage. These catching media are incorporated into the spool piece, thereby enabling to catch even small quantity of radioactive leakage lower than the detectable sensitivity of the radiation monitor, if should occur, in the spool piece and enabling radioactive detection for the accumulated dose rate. (Horiuchi, T.)

Nuclear plant's virtual simulation for on-line radioactive environment monitoring and dose assessment for personnel

International Nuclear Information System (INIS)

Mol, Antonio Carlos A.; Jorge, Carlos Alexandre F.; Lapa, Celso Marcelo F.

2009-01-01

This paper reports the use of nuclear plant's simulation for online dose rate monitoring and dose assessment for personnel, using virtual reality technology. The platform used for virtual simulation was adapted from a low cost game engine, taking advantage of all its image rendering capabilities, as well as the physics for movement and collision, and networking capabilities for multi-user interactive navigation. A real nuclear plant was virtually modeled and simulated, so that a number of users can navigate simultaneously in this virtual environment in first or third person view, each one receiving visual information about both the radiation dose rate in each actual position, and the radiation dose received. Currently, this research and development activity has been extended to consider also on-line measurements collected from radiation monitors installed in the real plant that feed the simulation platform with dose rate data, through a TCP/IP network. Results are shown and commented, and other improvements are discussed, as the execution of a more detailed dose rate mapping campaign.

Development of Nuclide Recognizing Prompt Radiation Distribution Monitoring System

Energy Technology Data Exchange (ETDEWEB)

Lee, Uk Jae; Yoo, Dong Han; Kim, Hee Reyoung [Ulsan National Institute of Science and Technology, Ulsan (Korea, Republic of)

2014-05-15

The geographic data such as latitude, longitude and map image can be obtained by using GPS and digital map. Radiation data can be acquired by detector. Finally simultaneous visibility system can be operated by using CDMA. Existing radiation distribution monitoring system is based on random generated data. However the radiation distribution monitoring system is developed. It is based on real detected data. Connection between the detector and laptop which are located at a site place is operated by using Bluetooth. CDMA is used to simulate visibility system between laptop in a site place and server PC in the control office. Real map image is taken from digital map. Finally radiation distribution contour map on the real map image can be shown by using MATLAB. 5 figures appear which shows natural, {sup 137}Cs, {sup 131}I, artificial and total radiation dose rate. So this system can be used in everywhere to check the distribution of radiation with geographic information.

The LCLS Undulator Beam Loss Monitor Readout System

Energy Technology Data Exchange (ETDEWEB)

Dusatko, John; Browne, M.; Fisher, A.S.; Kotturi, D.; Norum, S.; Olsen, J.; /SLAC

2012-07-23

The LCLS Undulator Beam Loss Monitor System is required to detect any loss radiation seen by the FEL undulators. The undulator segments consist of permanent magnets which are very sensitive to radiation damage. The operational goal is to keep demagnetization below 0.01% over the life of the LCLS. The BLM system is designed to help achieve this goal by detecting any loss radiation and indicating a fault condition if the radiation level exceeds a certain threshold. Upon reception of this fault signal, the LCLS Machine Protection System takes appropriate action by either halting or rate limiting the beam. The BLM detector consists of a PMT coupled to a Cherenkov radiator located near the upstream end of each undulator segment. There are 33 BLMs in the system, one per segment. The detectors are read out by a dedicated system that is integrated directly into the LCLS MPS. The BLM readout system provides monitoring of radiation levels, computation of integrated doses, detection of radiation excursions beyond set thresholds, fault reporting and control of BLM system functions. This paper describes the design, construction and operational performance of the BLM readout system.

KERMA-based radiation dose management system for real-time patient dose measurement

Science.gov (United States)

Kim, Kyo-Tae; Heo, Ye-Ji; Oh, Kyung-Min; Nam, Sang-Hee; Kang, Sang-Sik; Park, Ji-Koon; Song, Yong-Keun; Park, Sung-Kwang

2016-07-01

Because systems that reduce radiation exposure during diagnostic procedures must be developed, significant time and financial resources have been invested in constructing radiation dose management systems. In the present study, the characteristics of an existing ionization-based system were compared to those of a system based on the kinetic energy released per unit mass (KERMA). Furthermore, the feasibility of using the KERMA-based system for patient radiation dose management was verified. The ionization-based system corrected the effects resulting from radiation parameter perturbations in general radiography whereas the KERMA-based system did not. Because of this difference, the KERMA-based radiation dose management system might overestimate the patient's radiation dose due to changes in the radiation conditions. Therefore, if a correction factor describing the correlation between the systems is applied to resolve this issue, then a radiation dose management system can be developed that will enable real-time measurement of the patient's radiation exposure and acquisition of diagnostic images.

Assessment of population external irradiation doses with consideration of Rospotrebnadzor bodies equipment for monitoring of photon radiation dose

Directory of Open Access Journals (Sweden)

I. P. Stamat

2016-01-01

Full Text Available This paper provides review of equipment and methodology for measurement of photon radiation dose; analysis of possible reasons for considerable deviation between the Russian Federation population annual effective external irradiation doses and the relevant average global value. Data on Rospotrebnadzor bodies dosimetry equipment used for measurement of gamma radiation dose are collected and systematized. Over 60 kinds of dosimeters are used for monitoring of population external irradiation doses. Most of dosimeters used in the country have gas-discharge detectors (Geiger-Mueller counters, minor biochemical annunciators, etc. which have higher total values of own background level and of space radiation response than the modern dosimeters with scintillation detectors. This feature of dosimeters is apparently one of most plausible reasons of a bit overstating assessment of population external irradiation doses. The options for specification of population external irradiation doses assessment are: correction of gamma radiation dose measurement results with consideration of dosimeters own background level and space radiation response, introduction of more up-to-date dosimeters with scintillation detectors, etc. The most promising direction of research in verification of population external irradiation doses assessment is account of dosimetry equipment.

Application of the personnel photographic monitoring method to determine equivalent radiation dose beyond proton accelerator shielding

International Nuclear Information System (INIS)

Gel'fand, E.K.; Komochkov, M.M.; Man'ko, B.V.; Salatskaya, M.I.; Sychev, B.S.

1980-01-01

Calculations of regularities to form radiation dose beyond proton accelerator shielding are carried out. Numerical data on photographic monitoring dosemeter in radiation fields investigated are obtained. It was shown how to determine the total equivalent dose of radiation fields beyond proton accelerator shielding by means of the photographic monitoring method by introduction into the procedure of considering nuclear emulsions of division of particle tracks into the black and grey ones. A comparison of experimental and calculational data has shown the applicability of the used calculation method for modelling dose radiation characteristics beyond proton accelerator shielding [ru

The Assessment of I-131 Internal Doses of Nuclear Medicine Workers in Korea Using Thyroid uptake system

International Nuclear Information System (INIS)

Bahn, Young Kag; Oh, Gi Back; Lee, Chang Ho; Lee, Jong Doo; Yeom, Yu Sun; Hwang, Young Muk

2012-01-01

There are possibilities the radiation workers could intake the radiation when workers deal with radiation-materials. Therefore, internal radiation doses of radiation workers need to be assessed. Although an application of the nuclear medicine is continuously increased in Korea, there is not a proper tool and form to monitor the internal doses of nuclear medicine workers. However, it is possible to attain the internal doses of I-131 to evaluate using thyroid uptake and well count system. In this study, we measured and evaluated the I-131 internal doses of nuclear medicine workers in Korea using thyroid uptake and well count system and performed an air sampling

User Performance Evaluation of Four Blood Glucose Monitoring Systems Applying ISO 15197:2013 Accuracy Criteria and Calculation of Insulin Dosing Errors.

Science.gov (United States)

Freckmann, Guido; Jendrike, Nina; Baumstark, Annette; Pleus, Stefan; Liebing, Christina; Haug, Cornelia

2018-04-01

The international standard ISO 15197:2013 requires a user performance evaluation to assess if intended users are able to obtain accurate blood glucose measurement results with a self-monitoring of blood glucose (SMBG) system. In this study, user performance was evaluated for four SMBG systems on the basis of ISO 15197:2013, and possibly related insulin dosing errors were calculated. Additionally, accuracy was assessed in the hands of study personnel. Accu-Chek ® Performa Connect (A), Contour ® plus ONE (B), FreeStyle Optium Neo (C), and OneTouch Select ® Plus (D) were evaluated with one test strip lot. After familiarization with the systems, subjects collected a capillary blood sample and performed an SMBG measurement. Study personnel observed the subjects' measurement technique. Then, study personnel performed SMBG measurements and comparison measurements. Number and percentage of SMBG measurements within ± 15 mg/dl and ± 15% of the comparison measurements at glucose concentrations performed by lay-users. The study was registered at ClinicalTrials.gov (NCT02916576). Ascensia Diabetes Care Deutschland GmbH.

Dose rate mapping and quantitative analysis of radioactive deposition with simple monitoring instruments in Finland after the Chernobyl accident.

Energy Technology Data Exchange (ETDEWEB)

Koivukoski, J. [Ministry of the Interior, Rescue Dept., Helsinki (Finland); Paatero, J. [Finnish Meteorological Inst., Helsinki (Finland)], E-mail: janne.koivukoski@intermin.fi

2013-03-01

This article reviews the Finnish dose-rate mapping equipment and the system to process the obtained results, which were used immediately after the 1986 Chernobyl accident. We present the results of the external gamma-radiation monitoring carried out with simple civil-defence gamma monitoring instruments and compare them with the subsequent deposition mapping performed with research-grade instruments. The analysis shows that the quality of radiation mapping is good enough for decision makers to direct protective measures to the right areas. This review also demonstrates that a simple stationary external gamma radiation monitoring network can be effectively used for early warning in radiation emergency situations. (orig.)

Radiation monitoring system

Energy Technology Data Exchange (ETDEWEB)

Aghina, Mauricio A.C.; Farias, Marcos S. de; Lacerda, Fabio de; Heimlich, Adino [Instituto de Engenharia Nuclear (IEN/CNEN-RJ), Rio de Janeiro, RJ (Brazil)

2015-07-01

Design of a portable low-power multichannel analyzer with wireless connectivity for remote radiation monitoring, powered from a solar panel with a internal battery to be operated in field. The multichannel analyzer is based on a single microcontroller which performs the digital functions and an analog signal processing board for implementing a Gaussian shaper preamplifier, a Gaussian stretcher, sample and hold, pile-up rejector and a 10 bit ADC. Now this design is to be used with a NaI(Ti) scintillator detector. This multichannel analyzer is designed to be a part of radiation monitoring network. All of them are connected, by radio in a radius of 10 kilometers, to a supervisor computer that collects data from the network of multichannel analyzers and numerically display the latest radiation measurements or graphically display measurements over time for all multichannel analyzers. Like: dose rate, spectra and operational status. Software also supports remotely configuring operating parameters (such as radiation alarm level) for each monitor independently. (author)

Radiation monitoring system

International Nuclear Information System (INIS)

Aghina, Mauricio A.C.; Farias, Marcos S. de; Lacerda, Fabio de; Heimlich, Adino

2015-01-01

Design of a portable low-power multichannel analyzer with wireless connectivity for remote radiation monitoring, powered from a solar panel with a internal battery to be operated in field. The multichannel analyzer is based on a single microcontroller which performs the digital functions and an analog signal processing board for implementing a Gaussian shaper preamplifier, a Gaussian stretcher, sample and hold, pile-up rejector and a 10 bit ADC. Now this design is to be used with a NaI(Ti) scintillator detector. This multichannel analyzer is designed to be a part of radiation monitoring network. All of them are connected, by radio in a radius of 10 kilometers, to a supervisor computer that collects data from the network of multichannel analyzers and numerically display the latest radiation measurements or graphically display measurements over time for all multichannel analyzers. Like: dose rate, spectra and operational status. Software also supports remotely configuring operating parameters (such as radiation alarm level) for each monitor independently. (author)

The automatic radiation monitor distributed System SRM-256C

International Nuclear Information System (INIS)

Stetsenko, G.N.; Rastsvetalov, Y.N.; Yanovich, A.A.

1996-01-01

The Controlled and Supervised Areas (CSA) of UNK proton accelerator built in Protvino (IHEP, Russia), borrows the significant area (more than 15 sq.km). Submitted in work results of accounts show, that by major factors, influencing to a radioecological conditions in region at the expense of work UNK are: 1) the output of pulsing radiation on day-time surface; 2) the radionuclides receipts with drinking water; 3) the pollution of radioactive air from system of ventilation. At normal mode of UNK operation the equivalent dose rates on daytime surface of pulsing radiation will changes in limits from 0.5 mcSv/hours near overmines buildings up to 0.1 mcSv / hour on the CSA border. The average equivalent dose rates per year due to internal irradiation at use (intakes) of drinking water will not exceed 5 - 50 mcSv/years. The Maximum equivalent dose rates on day-time surface, caused by pollution of radioactive air does not exceed 0.01... 0.03 mcSv/hour in limits of CSA, and the average equivalent dose per year caused by internal irradiation does not exceed 0.05 mcSv/years. At emergency-free operation the maximum degree of the UNK influence in limits of CSA is estimated in terms of average equivalent dose per year at levels, not exceeding 0.05... 0.10 mSv/year. For maintenance of integral environmental monitoring of total external radiation levels in limits of CSA network of passive monitor stations will be developed

Safety system status monitoring

International Nuclear Information System (INIS)

Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

1984-03-01

The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide

Safety system status monitoring

Energy Technology Data Exchange (ETDEWEB)

Lewis, J.R.; Morgenstern, M.H.; Rideout, T.H.; Cowley, P.J.

1984-03-01

The Pacific Northwest Laboratory has studied the safety aspects of monitoring the preoperational status of safety systems in nuclear power plants. The goals of the study were to assess for the NRC the effectiveness of current monitoring systems and procedures, to develop near-term guidelines for reducing human errors associated with monitoring safety system status, and to recommend a regulatory position on this issue. A review of safety system status monitoring practices indicated that current systems and procedures do not adequately aid control room operators in monitoring safety system status. This is true even of some systems and procedures installed to meet existing regulatory guidelines (Regulatory Guide 1.47). In consequence, this report suggests acceptance criteria for meeting the functional requirements of an adequate system for monitoring safety system status. Also suggested are near-term guidelines that could reduce the likelihood of human errors in specific, high-priority status monitoring tasks. It is recommended that (1) Regulatory Guide 1.47 be revised to address these acceptance criteria, and (2) the revised Regulatory Guide 1.47 be applied to all plants, including those built since the issuance of the original Regulatory Guide.

Analysis of records of external occupational dose records in Brazil

International Nuclear Information System (INIS)

Mauricio, Claudia L.P.; Silva, Herica L.R. da; Silva, Claudio Ribeiro da

2014-01-01

Brazil, a continental country, with actually more than 150,000 workers under individual monitoring for ionizing radiation, has implemented in 1987 a centralized system for storage of external occupational dose. This database has been improved over the years and is now a web-based information system called Brazilian External Occupational Dose Management Database System - GDOSE. This paper presents an overview of the Brazilian external occupational dose over the years. The estimated annual average effective dose shows a decrease from 2.4 mSv in 1987 to about 0.6 mSv, having been a marked reduction from 1987 to 1990. Analyzing by type of controlled practice, one sees that the medical and dental radiology is the area with the largest number of users of individual monitors (70%); followed by education practices (8%) and the industrial radiography (7%). Additionally to photon whole body monitoring; neutron monitors are used in maintenance (36%), reactor (30%) and education (27%); and extremity monitors, in education (27%), nuclear medicine (22%) and radiology (19%). In terms of collective dose, the highest values are also found in conventional radiology, but the highest average dose values are those of interventional radiology. Nuclear medicine, R and D and radiotherapy also have average annual effective dose higher than 1 mSv. However, there is some very high dose values registered in GDOSE that give false information. This should be better analyzed in the future. Annual doses above 500 are certainly not realistic. (author)

The Mayak Worker Dosimetry System (MWDS-2013): implementation of the dose calculations

International Nuclear Information System (INIS)

Zhdanov, A.; Vostrotin, V.; Efimov, A.; Birchall, A.; Puncher, M.

2017-01-01

The calculation of internal doses for the Mayak Worker Dosimetry System (MWDS-2013) involved extensive computational resources due to the complexity and sheer number of calculations required. The required output consisted of a set of 1000 hyper-realizations: each hyper-realization consists of a set (1 for each worker) of probability distributions of organ doses. This report describes the hardware components and computational approaches required to make the calculation tractable. Together with the software, this system is referred to here as the 'PANDORA system'. It is based on a commercial SQL server database in a series of six work stations. A complete run of the entire Mayak worker cohort entailed a huge amount of calculations in PANDORA and due to the relatively slow speed of writing the data into the SQL server, each run took about 47 days. Quality control was monitored by comparing doses calculated in PANDORA with those in a specially modified version of the commercial software 'IMBA Professional Plus'. Suggestions are also made for increasing calculation and storage efficiency for future dosimetry calculations using PANDORA. (authors)

AIP Diffraction measurements using the LHC Beam Loss Monitoring System

CERN Document Server

Kalliokoski, Matti

2017-01-01

The Beam Loss Monitoring (BLM) system of the Large Hadron Collider protects the machine from beam induced damage by measuring the absorbed dose rates of beam losses, and by triggering beam dump if the rates increase above the allowed threshold limits. Although the detection time scales are optimized for multi-turn losses, information on fast losses can be recovered from the loss data. In this paper, methods in using the BLM system in di ff raction studies are discussed.

Sampling optimization trade-offs for long-term monitoring of gamma dose rates

NARCIS (Netherlands)

Melles, S.J.; Heuvelink, G.B.M.; Twenhöfel, C.J.W.; Stöhlker, U.

2008-01-01

This paper applies a recently developed optimization method to examine the design of networks that monitor radiation under routine conditions. Annual gamma dose rates were modelled by combining regression with interpolation of the regression residuals using spatially exhaustive predictors and an

Successful withdrawal from high-dose benzodiazepine in a young patient through electronic monitoring of polypharmacy: a case report in an ambulatory setting.

Science.gov (United States)

Loscertales, Hèctor R; Wentzky, Valerie; Dürsteler, Kenneth; Strasser, Johannes; Hersberger, Kurt E; Arnet, Isabelle

2017-05-01

Dependence on high-dose benzodiazepines (BZDs) is well known and discontinuation attempts are generally unsuccessful. A well established protocol for high-dose BZD withdrawal management is lacking. We present the case of withdrawal from high-dose lorazepam (>20 mg daily) in an unemployed 35-year-old male outpatient through agonist substitution with long-acting clonazepam and electronic monitoring over 28 weeks. All medicines were repacked into weekly 7 × 4 cavity multidose punch cards with an electronic monitoring system. The prescribed daily dosages of BZDs were translated into an optimal number of daily tablets, divided into up to four units of use. Withdrawal was achieved by individual leftover of a small quantity of BZDs that was placed in a separate compartment. Feedback with visualization of intake over the past week was given during weekly psychosocial sessions. Stepwise reduction was obtained by reducing the mg content of the cavities proportionally to the leftovers, keeping the number of cavities in order to maintain regular intake behavior, and to determine the dosage decrease. At week 28, the primary objectives were achieved, that is, lorazepam reduction to 5 mg daily and cannabis abstinence. Therapy was continued using multidrug punch cards without electronic monitoring to maintain the management system. At week 48, a smaller size weekly pill organizer with detachable daily containers was dispensed. At week 68, the patient's therapy was constant with 1.5 mg clonazepam + 5 mg lorazepam daily for anxiety symptoms and the last steps of withdrawal were started. Several key factors led to successful withdrawal from high-dose BZD in this outpatient, such as the use of weekly punch cards coupled with electronic monitoring, the patient's empowerment over the withdrawal process, and the collaboration of several healthcare professionals. The major implication for clinical care is reduction by following the leftovers, and not a diktat from the healthcare

Development of a Real-time Hand Dose Monitor for Personnel in Interventional Radiology

Energy Technology Data Exchange (ETDEWEB)

Ban, N.; Nakaoka, H.; Haruta, R.; Murakami, Y.; Kubo, T.; Maeda, T.; Kusama, T

2001-07-01

Medical procedures denoted as interventional radiology require operation near an X ray beam, which brings high dose exposures to the operators' hands. For the effectual control of their extremity doses, a prototype of a real-time wrist dosemeter has been developed, hand dose monitor (HDM), based on a single silicon detector. Experiments were performed to test its response to diagnostic X rays. The HDM was highly sensitive and showed a linear response down to doses of a few tens of microsieverts. Though dose rate, energy and angular dependence of the response were observed in some extreme conditions, the HDM was proved to be of practical use if it was appropriately calibrated. Since an HDM enables personnel to check their hand doses on a real-time basis, it would enable medical staff to control the exposure themselves. (author)

Preparedness for response to the challenges from orphan sources: nationwide environmental radiation mapping with state of the art monitoring systems

International Nuclear Information System (INIS)

Saindane, Shashank S.; Pradeepkumar, K.S.; Suri, M.M.K.; Sharma, D.N.

2008-01-01

Based on the various international reports on orphan sources, the potential for radiological emergencies in public domain is recognized as a cause of concern. To detect the presence of any such orphan sources and to strengthen the preparedness for response to any radiological emergencies in public domain, a nationwide radiation mapping programme was initiated in India. Various radiation monitoring systems, few of them integrated with Global Positioning System (GPS) installed in mobile monitoring vans were used for this purpose. This monitoring also helped in generating the base line dose rate data of the cities and also in demonstrating the methodology of environmental monitoring for locating the presence of orphan sources, if any. During the detailed monitoring of various cities of the country, different systems such as GSM based Radiation Monitoring System (GRaMS), Compact Radiation Monitoring system, Portable Mobile Gamma Spectrometry System, Gamma Tracer System etc. installed in a vehicle were made to continuously acquire the data at a varying rate from 10 sec to 1 minute acquisition time. These systems can measure dose rate in the range of 0.01 - 100 μGy h -1 and can detect 7.4 MBq (200 μCi) of 60 Co and 25 MBq (675 μCi) of 137 Cs from a distance of 5 metre. Average dose rate recorded during these environmental monitoring was 81 ± 07 nGy h -1 with a maximum of 210 ± 11 nGyh -1 at Bangalore (attributed to the presence of K-40). The digital topographic map and the data acquired from the radiation mapping are used to generate terrestrial radiation map. This radiation profile stored in the database can be used as reference while carrying out the impact assessment following any nuclear / radiological emergencies. These systems also help to tag the radiation levels along with positional coordinates online onto the GIS map of the area. GRaMS also demonstrated its capability for online transmission of the data to the centralized data acquisition Base Station

Radiological safety system based on real-time tritium-in-air monitoring indoors and in effluents

International Nuclear Information System (INIS)

Bidica, N.; Sofalca, N; Balteanu, O.; Srefan, I.

2006-01-01

Exposure to tritium is an important health hazard in any tritium processing facility so that implementing a real-time tritium monitoring system is necessary for its operation in safety conditions. The tritium processing facility operators need to be informed at any time about the in-air tritium concentration indoors or in the stack effluents, in order to detect immediately any leaks in tritium containments, or any releases inside the buildings or to the environment. This information is very important for adopting if necessary protection measures and correcting actions as quickly as possible. In this paper we describe an improved real-time tritium monitoring system designed for the Heavy Water Detritiation Pilot Plant of National Institute for Cryogenics and Isotopes Separation, Rm. Valcea, Romania. The design of the Radiological Safety System implemented for the ICIT Water Detritiation Pilot Plant is intended to provide the maximum safety level based on the ALARA concept. The main functions of tritium monitoring system are: - monitoring the working areas and gaseous effluents by determination of the tritium-in-air activity concentration; - local and remote data display; - assessing of environment dose equivalent rates and dose equivalents in the working environment (for personnel exposure control and work planning); - assessing the total tritium activity released to the environment through ventilation exhaust stack; - safety functions, i.e., local and remote, locking/unlocking personnel access, process shut-down in emergency conditions and start of the air cleaning systems. With all these features our tritium monitoring system is really a safety system adequate for personnel and environmental protection. (authors)

Extremity dosimetry in medical applications within Europe: an overview of doses and monitoring practices

International Nuclear Information System (INIS)

Donadille, Laurent; Carinou, E.; Ginjaume, M.; Jankowski, J.; Rimpler, A.; Sans Merce, M.; Vanhavere, F.

2008-01-01

Full text: Some activities of the EURADOS Working Group 9 (WG9) related to the radiation protection dosimetry of medical staff were funded by the European Commission in the framework of the CONRAD project, Work Package 7. The objective of WG9 was to promote and co-ordinate research activities for the assessment of occupational exposure to staff at workplaces in therapeutic and diagnostic radiology and nuclear medicine. At these workplaces, from the point of view of the individual monitoring for external radiation, the skin of the fingers is generally the limiting organ. Subgroup 1 of WG9 had as main objective the study of the use of extremity dosemeters in medical radiation fields. The wide variety of radiation field characteristics present in medicine together with the difficulties of measuring a local dose which should be representative for the maximum skin dose using one single detector, makes it difficult to perform extremity dosimetry with an accuracy similar to that of whole-body one. A recent intercomparison organised by WG9 showed that some types of dosemeters significantly underestimate or overestimate skin doses. Subgroup 1 carried out a thorough literature review on extremity dosimetry issues. It covered diagnostic and therapeutic nuclear medicine and PET, interventional radiology and cardiology, and brachytherapy. It has notably pointed out the consensus about the requirement of regular extremity dose monitoring for nuclear medicine and PET, and the great difficulty of measuring extremity doses for procedures in interventional radiology and cardiology, activities for which routine extremity dose monitoring has been found to be poor. Furthermore, information on the status of extremity dosimetry in medical applications and associated monitoring practices was gathered from 7 European countries: France, Germany, Greece, Ireland, Poland, Spain and Switzerland. Interpretation of the data was not easy because of the wide range of procedures involved and also

The Recent System of the Personal Monitoring in the Czech Republic

International Nuclear Information System (INIS)

Petrova, K.

2001-01-01

Full text: The paper is intended to provide with the overview of the recent situation concerned to the management of the personal monitoring in the Czech Republic in the context of the harmonisation process of legislation within the European Union. New legislation concerning the radiation protection, which is effective in the Czech Republic from 1997 year, arises already from the ICRP 60 and IAEA BSS and includes all new basic principles for protection of radiation workers which are established and recommended. The recent Czech legislation does not recognise the term 'outside worker' and there are no special demands for their protection. However the harmonisation of the Czech legislation with EU Directives takes in consideration also the Council Directive 90/641/EURATOM on radiation protection of outside workers. In the frame of the process of harmonisation the new terms will be implemented into the Czech Atomic Law and new radiation passports will be tested in the practice. The personal dosimetric service is identified as the practice very significant from the radiation protection point of view and shall be licensed by the State Office for Nuclear Safety (SONS). The licence application shall include the methodology of effective dose evaluation, the description of quality assurance (QA) and quality control (QC) of the service, the system of customer communication and dose recording and reporting. The results of intercomparisons are demanded. The attention is paid also to the appropriate qualification of workers performing the service. Recently three dosimetric services are approved by SONS for external monitoring (film, TLD, electronic), four services for internal monitoring (whole-body counter, thyroid and bio samples measurement), one for monitoring in uranium mines and one for dose calculation of air crew. In accordance with legislation demands, the licensee (or dosimetric service monitoring the licensee's workers) is obliged to report the personal and

The development of an on-site wastewater treatment system with monitoring capabilities

International Nuclear Information System (INIS)

Kubota, Hiroshi; Shigeizumi, Koga; Noguchi, Shuntaro; Kita, Shingo; Egawa, Moritoshi; Takeshima, Toshikatsu

2015-01-01

A compact Wastewater Treatment Unit that can monitor its own decontamination efficiency by using an underwater dosimeter and turbidity meter was developed. This equipment is so compact as to be able to be loaded up a 1t-class truck and is efficient enough to decrease radioactivity level of wastewater to under 10 Bq/L. There are high levels of correlation between radioactivity and turbidity and underwater radiation dose (URD). Turbidity has the advantage of measuring low radiation density, whilst URD can measure radioactive contamination independently of other factors affecting water quality. However experiments showed that the relationship between turbidity and radioactivity density was changed according to radioactivity of the suspensoid, and that air dose rate had an impact on determination limit of URD index. As this Wastewater Treatment Unit has a dual-meter system, it is possible to calibrate the turbidity index with the measured URD. This dual-meter system would be able to monitor low radioactivity levels in a range of wastewaters. (author)

The challenge of Ciemat internal dosimetry service for accreditation according to ISO/IEC 17025 standard, for in vivo and in vitro monitoring and dose assessment of internal exposures

International Nuclear Information System (INIS)

Lopez, M.A.; Martin, R.; Hernandez, C.; Navarro, J.F.; Navarro, T.; Perez, B.; Sierra, I.

2016-01-01

The accreditation of an Internal Dosimetry Service (IDS) according to ISO/IEC 17025 Standard is a challenge. The aim of this process is to guarantee the technical competence for the monitoring of radionuclides incorporated in the body and for the evaluation of the associated committed effective dose E(50). This publication describes the main accreditation issues addressed by CIEMAT IDS regarding all the procedures involving good practice in internal dosimetry, focussing in the difficulties to ensure the traceability in the whole process, the appropriate calculation of detection limit of measurement techniques, the validation of methods (monitoring and dose assessments), the description of all the uncertainty sources and the interpretation of monitoring data to evaluate the intake and the committed effective dose. CIEMAT Internal Dosimetry Service (IDS) has developed and implemented a quality system based on ISO/IEC 17025 to ensure compliance with the general requirements of this reference standard. The development of documentary support according to this quality system permitted to standardise the systematic activities performed within the whole body counter and in vitro bioassay laboratories as well as the procedures carried out by qualified staff in charge of internal dose assessment. There was no previous experience in the accreditation of other internal dosimetry services in Spain. Then, requirements from the national regulatory body (Nuclear Safety Council, CSN) and national accreditation entity (ENAC) have been considered. The main concerns were to guarantee the traceability in the whole process and to avoid possible charge of interpretation or subjectivity in the methodology of dose assessment due to intakes of radionuclides when calculating from monitoring data. All the related international standards dealing with internal dosimetry were taken into account: ISO 28218 'Performance criteria for radiobioassay', ISO 27048 'Dose Assessment for the

Monitoring Cray Cooling Systems

Energy Technology Data Exchange (ETDEWEB)

Maxwell, Don E [ORNL; Ezell, Matthew A [ORNL; Becklehimer, Jeff [Cray, Inc.; Donovan, Matthew J [ORNL; Layton, Christopher C [ORNL

2014-01-01

While sites generally have systems in place to monitor the health of Cray computers themselves, often the cooling systems are ignored until a computer failure requires investigation into the source of the failure. The Liebert XDP units used to cool the Cray XE/XK models as well as the Cray proprietary cooling system used for the Cray XC30 models provide data useful for health monitoring. Unfortunately, this valuable information is often available only to custom solutions not accessible by a center-wide monitoring system or is simply ignored entirely. In this paper, methods and tools used to harvest the monitoring data available are discussed, and the implementation needed to integrate the data into a center-wide monitoring system at the Oak Ridge National Laboratory is provided.

Drug-induced cellular death dynamics monitored by a highly sensitive organic electrochemical system.

Science.gov (United States)

Romeo, Agostino; Tarabella, Giuseppe; D'Angelo, Pasquale; Caffarra, Cristina; Cretella, Daniele; Alfieri, Roberta; Petronini, Pier Giorgio; Iannotta, Salvatore

2015-06-15

We propose and demonstrate a sensitive diagnostic device based on an Organic Electrochemical Transistor (OECT) for direct in-vitro monitoring cell death. The system efficiently monitors cell death dynamics, being able to detect signals related to specific death mechanisms, namely necrosis or early/late apoptosis, demonstrating a reproducible correlation between the OECT electrical response and the trends of standard cell death assays. The innovative design of the Twell-OECT system has been modeled to better correlate electrical signals with cell death dynamics. To qualify the device, we used a human lung adenocarcinoma cell line (A549) that was cultivated on the micro-porous membrane of a Transwell (Twell) support, and exposed to the anticancer drug doxorubicin. Time-dependent and dose-dependent dynamics of A549 cells exposed to doxorubicin are evaluated by monitoring cell death upon exposure to a range of doses and times that fully covers the protocols used in cancer treatment. The demonstrated ability to directly monitor cell stress and death dynamics upon drug exposure using simple electronic devices and, possibly, achieving selectivity to different cell dynamics is of great interest for several application fields, including toxicology, pharmacology, and therapeutics. Copyright © 2015 Elsevier B.V. All rights reserved.

Polymedication Electronic Monitoring System (POEMS) - a new technology for measuring adherence.

Science.gov (United States)

Arnet, Isabelle; Walter, Philipp N; Hersberger, Kurt E

2013-01-01

Reliable and precise measurement of patient adherence to medications is feasible by incorporating a microcircuitry into pharmaceutical packages of various designs, such that the maneuvers needed to remove a dose of drug are detected, time-stamped, and stored. The principle is called "electronic medication event monitoring" but is currently limited to the monitoring of a single drug therapy. Our aims were introducing a new technology; a clear, self-adhesive polymer film, with printed loops of conductive wires that can be affixed to multidrug punch cards for the electronic adherence monitoring of multiple medication regimens (Polymedication Electronic Monitoring System, POEMS), and illustrating potential benefits for patient care. We present a preliminary report with one patient experience. Our illustrative case was supplied with a pre-filled 7-day multiple medication punch card with unit-of-use doses for specific times of the day (six pills in the morning cavity, two pills in the evening cavity, and one pill in case of insomnia in the bedtime cavity), with the new electronic film affixed on it. The intake times over 1 week were extremely skewed (median intake hours at 2:00 pm for the morning doses and at 6:40 pm for the evening doses). After an intervention aimed at optimizing the timing adherence, the morning and evening intake hours became more balanced, with 42.3% of correct dosing intervals (±3 h) for drugs with twice daily intake (vs. 0% before the intervention). The electronic monitoring of the entire therapy revealed an intake pattern that would have remained undiscovered with any other device and allowed a personalized intervention to correct an inadequate medication intake behavior. POEMS may guide health professionals when they need to optimize a pharmacotherapy because of suspected insufficient adherence. Further, knowing the intake pattern of the entire pharmacotherapy can elucidate unreached clinical outcome, drug-drug interactions, and drug resistance

Application for verification of monitor units of the treatment planning system

International Nuclear Information System (INIS)

Suero Rodrigo, M. A.; Marques Fraguela, E.

2011-01-01

Current estimates algorithms achieve acceptable degree of accuracy. However, operate on the basis of un intuitive models. It is therefore necessary to verify the calculation of monitor units of the treatment planning system (TPS) with those obtained by other independent formalisms. To this end, we have developed an application based on factorization formalism that automates the calculation of dose.

Tracking and Monitoring with Dosimeter-Enabled ARG-US RFID System - 12009

Energy Technology Data Exchange (ETDEWEB)

Anderson, J.; Lee, H.; De Lurgio, P.; Kearney, C.M.; Craig, B.; Soos, I.H.; Tsai, H.; Liu, Y. [Argonne National Laboratory, Argonne, IL 60439 (United States); Shuler, J. [U.S. Department of Energy, Washington, D.C. 20585 (United States)

2012-07-01

Automated monitoring and tracking of materials with radio frequency identification (RFID) technology can significantly improve both the operating efficiency of radiological facilities and the application of the ALARA (as low as reasonably achievable) principle in them. One such system, called ARG-US, has been developed by Argonne National Laboratory for the U.S. Department of Energy (DOE) Packaging and Certification Program to use in managing sensitive nuclear and radioactive materials. Several ARG-US systems are in various stages of deployment and advanced testing across DOE sites. ARG-US utilizes sensors in the tags to continuously monitor the state of health of the packaging and promptly disseminates alarms to authorized users. In conjunction with global positioning system (GPS) tracking provided by TRANSCOM, the system can also monitor and track packages during transport. A compact dosimeter has been incorporated in the ARG-US tags via an onboard universal asynchronous receiver/transmitter interface. The detector has a wide measurement range for gamma radiation - from 0.1 mSv/h to 8 Sv/h. The detector is able to generate alarms for both high and low radiation and for a high cumulative dose. In a large installation, strategically located dosimeter-enabled tags can yield an accurate, real-time, 2D or 3D dose field map that can be used to enhance facility safety, security, and safeguards. This implementation can also lead to a reduced need for manned surveillance and reduced exposure of personnel to radiation, consistent with the ALARA principle at workplaces. (authors)

Monitoring and assessment of individual doses of occupationally exposed workers due to external radiation

International Nuclear Information System (INIS)

Kitaw, S. T.

2015-05-01

Exposure to external radiation occurs in many occupations. Any exposure to ionizing radiation has the tendency to change the biochemical make-up of the human body which may result in biological health effects of ionizing radiation. This study reviews the monitoring and assessment of external radiation doses in industrial radiography using thermoluminescence and direct reading dosimeters. Poor handling procedures such as inadequate engineering control of equipment, safety culture, management, and inadequate assessment and monitoring of doses are the causes of most of the reported cases of exposure to external radiation in industrial radiography. Occupational exposure data in industrial radiography from UNSCEAR report 2008 was discussed and recommendations were made to regulatory authorities, operating organizations and radiographers. (au)

Optimized dose distribution of a high dose rate vaginal cylinder

International Nuclear Information System (INIS)

Li Zuofeng; Liu, Chihray; Palta, Jatinder R.

1998-01-01

Purpose: To present a comparison of optimized dose distributions for a set of high-dose-rate (HDR) vaginal cylinders calculated by a commercial treatment-planning system with benchmark calculations using Monte-Carlo-calculated dosimetry data. Methods and Materials: Optimized dose distributions using both an isotropic and an anisotropic dose calculation model were obtained for a set of HDR vaginal cylinders. Mathematical optimization techniques available in the computer treatment-planning system were used to calculate dwell times and positions. These dose distributions were compared with benchmark calculations with TG43 formalism and using Monte-Carlo-calculated data. The same dwell times and positions were used for a quantitative comparison of dose calculated with three dose models. Results: The isotropic dose calculation model can result in discrepancies as high as 50%. The anisotropic dose calculation model compared better with benchmark calculations. The differences were more significant at the apex of the vaginal cylinder, which is typically used as the prescription point. Conclusion: Dose calculation models available in a computer treatment-planning system must be evaluated carefully to ensure their correct application. It should also be noted that when optimized dose distribution at a distance from the cylinder surface is calculated using an accurate dose calculation model, the vaginal mucosa dose becomes significantly higher, and therefore should be carefully monitored

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

Source term assessment using inverse modeling of radiation dose measured with environmental radiation monitors located at different positions

International Nuclear Information System (INIS)

Srinivas, C.V.; Rakesh, P.T.; Baskaran, R.; Venkatraman, B.

2018-01-01

Source term is an important input for consequence analysis using Decision Support Systems (DSS) to project radiological impact in the event of nuclear emergencies. A source term model called 'ASTER' is incorporated in the Online Nuclear Emergency Response System (ONERS) operational at Kalpakkam site for decision making during nuclear emergencies. This computes release rates using inverse method by employing an atmospheric dispersion model and gamma dose rates measured by environmental radiation monitors (ERM) deployed around the nuclear plant. The estimates may depend on the distribution of ERMs around the release location. In this work, data from various gamma monitors located at different radii 0.75 km and 1.5 km is used to assess the accuracy in the source term estimation for stack releases of MAPS-PHWR at Kalpakkam

Environmental and biological monitoring in the estimation of absorbed doses of pesticides.

Science.gov (United States)

Aprea, Maria Cristina

2012-04-25

Exposure to pesticides affects most of the population, not only persons occupationally exposed. In a context of high variability of exposure, biological monitoring is important because of the various routes by which exposure can occur and because it assesses both occupational and non-occupational exposure. The main aim of this paper was to critically compare estimates of absorbed dose measured by environmental and biological monitoring in situations in which they could both be applied. The combination of exposure measurements and biological monitoring was found to provide extremely important information on the behaviour of employees, and on the proper use and effectiveness of personal protection equipment. Copyright © 2011 Elsevier Ireland Ltd. All rights reserved.

SU-E-T-585: Optically-Stimulated Luminescent Dosimeters for Monitoring Pacemaker Dose in Radiation Therapy

International Nuclear Information System (INIS)

Apicello, L; Riegel, A; Jamshidi, A

2015-01-01

Purpose: A sufficient amount of ionizing radiation can cause failure to components of pacemakers. Studies have shown that permanent damage can occur after a dose of 10 Gy and minor damage to functionality occurs at doses as low as 2 Gy. Optically stimulated thermoluminescent dosimeters (OSLDs) can be used as in vivo dosimeters to predict dose to be deposited throughout the treatment. The purpose of this work is to determine the effectiveness of using OSLDs for in vivo dosimetry of pacemaker dose. Methods: As part of a clinical in vivo dosimetry experience, OSLDs were placed at the site of the pacemaker by the therapist for one fraction of the radiation treatment. OSLD measurements were extrapolated to the total dose to be received by the pacemaker during treatment. A total of 79 measurements were collected from November 2011 to December 2013 on six linacs. Sixty-six (66) patients treated in various anatomical sites had the dose of their pacemakers monitored. Results: Of the 79 measurements recorded, 76 measurements (96 %) were below 2 Gy. The mean and standard deviation were 50.12 ± 76.41 cGy. Of the 3 measurements that exceeded 2 Gy, 2 measurements matched the dose predicted in the treatment plan and 1 was repeated after an unexpectedly high Result. The repeated measurement yielded a total dose less than 2 Gy. Conclusion: This analysis suggests OSLDs may be used for in vivo monitoring of pacemaker dose. Further research should be performed to assess the effect of increased backscatter from the pacemaker device

SU-E-T-585: Optically-Stimulated Luminescent Dosimeters for Monitoring Pacemaker Dose in Radiation Therapy

Energy Technology Data Exchange (ETDEWEB)

Apicello, L [Hofstra University, Hempstead, NY (United States); Riegel, A; Jamshidi, A [North Shore LIJ Health System, Lake Success, NY (United States)

2015-06-15

Purpose: A sufficient amount of ionizing radiation can cause failure to components of pacemakers. Studies have shown that permanent damage can occur after a dose of 10 Gy and minor damage to functionality occurs at doses as low as 2 Gy. Optically stimulated thermoluminescent dosimeters (OSLDs) can be used as in vivo dosimeters to predict dose to be deposited throughout the treatment. The purpose of this work is to determine the effectiveness of using OSLDs for in vivo dosimetry of pacemaker dose. Methods: As part of a clinical in vivo dosimetry experience, OSLDs were placed at the site of the pacemaker by the therapist for one fraction of the radiation treatment. OSLD measurements were extrapolated to the total dose to be received by the pacemaker during treatment. A total of 79 measurements were collected from November 2011 to December 2013 on six linacs. Sixty-six (66) patients treated in various anatomical sites had the dose of their pacemakers monitored. Results: Of the 79 measurements recorded, 76 measurements (96 %) were below 2 Gy. The mean and standard deviation were 50.12 ± 76.41 cGy. Of the 3 measurements that exceeded 2 Gy, 2 measurements matched the dose predicted in the treatment plan and 1 was repeated after an unexpectedly high Result. The repeated measurement yielded a total dose less than 2 Gy. Conclusion: This analysis suggests OSLDs may be used for in vivo monitoring of pacemaker dose. Further research should be performed to assess the effect of increased backscatter from the pacemaker device.

Control and monitoring of doses to patients in a team of digital mammography

International Nuclear Information System (INIS)

Agulla Otero, M.; Torres Cabrera, R.; Hernando Gonzalez, I.

2013-01-01

In recent years is widespread use of imaging devices digital mammography. One of the advantages associated with this scanning is the ability to access a large amount of information contained in the headwaters of own digital images. The exploitation of this information allows the calculation of doses received by patients. This paper describes the methodology employed for this purpose and are presented the results of the control and monitoring of doses given in a digital mammography equipment. (Author)

Evaluating penetration-monitoring systems

International Nuclear Information System (INIS)

Markin, J.T.

1981-01-01

Evaluating the performance of a process monitoring system in detecting improper activities that could be related to material diversion requires a framework for addressing the complexity and statistical uncertainty of such systems. This report proposes a methodology that determines the optimal divertor strategy against a monitoring system and the system probability of detection. This method extends previous work by correctly modeling uncorrelated and correlated measurement errors for radiation monitors

Individual monitoring of external exposure in terms of personal dose equivalent, Hp(d)

International Nuclear Information System (INIS)

Fantuzzi, E.

2001-01-01

The institute for Radiation Protection of ENEA - Bologna has organised a one day-workshop on the subject: Individual monitoring of external exposure in terms of personal dose equivalent, H p (d). The aim of the workshop was the discussion of the new implications and modifications to be expected in the routine individual monitoring of external radiation, due to the issue of the Decree 241/00 (G.U. 31/8/2000) in charge since 01/01/2001. The decree set up in Italian law the standards contained in the European Directive EURATOM 96/29-Basic Standards for the Protection of Health of Workers and the General Public against Dangers arising from Ionizing Radiation. Among others, the definition of the operational quantities for external radiation for personal and environmental monitoring, H p (d) e H * (d) respectively as defined by ICRU (International Commission for Radiation Units and Measurements), requires to update the methods of measurements and calibration of the personal dosemeters and environmental monitors. This report collects the papers presented at the workshop dealing with the Personal Dose Equivalent, H p (d), the conversion coefficients, H p (d)/K a e H p (d)/ , obtained through Monte Carlo calculations published by ICRU and ICRP (International Commission for Radiation Protection), the new calibration procedures and the practical implication in the routine of individual monitoring in terms of H p (d). Eventually, in the last chapter, the answers to Frequently Asked Questions (FAQ) are briefly reported [it

Dosimetric accuracy at low monitor unit setting in electron beams at different dose rates

International Nuclear Information System (INIS)

Ravikumar, M.; Ravichandran, R.; Supe, Sanjay S.; Sharma, Anil K.

1999-01-01

As electron beam with low monitor unit (LMU) settings are used in some dosimetric studies, better understanding of accuracy in dose delivery at LMU setting is necessary. The dose measurements were carried out with 0.6 cm 3 farmer type ion chamber at d max in a polystyrene phantom. Measurements at different MUs show that the dose linearity ratio (DLR) increases as the MU setting decreases below 20 MU and DLRs are found to increase when the incident electron beams have higher energies. The increase in DLR is minimum for low dose rate setting for all five electron beam energies (6, 9, 12, 16 and 20 MeV). As the variation in dose delivery is machine-specific, a detailed study should be conducted before the low MU setting is implemented. Since errors in dose delivery are high at higher dose rates, low dose rate may be better at low MU unit setting. (author)

Nuclear power plant remote monitoring system of Hessen (KFUe Hessen) now fully available

International Nuclear Information System (INIS)

Lettmann, W.; Merkel, M.

1991-01-01

The remote monitoring system for the Biblis nuclear power station has commenced operation in 1990. It is intended to provide the radiological data and other information required by the supervisory Land authority for performing its supervisory functions in accordance with the Atomic Energy Act. The monitoring station records and reports emissions of the reactor station during specified normal operation and as a result of incidents or accidents, measures local dose rates at four measuring stations at the power plant fence, and records the meteorological conditions. The system is explained in detail, including illustration and graphs. (BBR) [de

Compliance monitoring system using screen printing technology based on conductive ink.

Science.gov (United States)

Hoshi, Kenji; Kawakami, Junko; Aoki, Sorama; Hamada, Kouji; Sato, Kenichi

2012-01-01

We developed a compliance monitoring system that electrically detects which drug among the multiple prescribed drugs a patient has taken and the date of drug-taking by a patient to prevent the patient from missing doses and taking drugs incorrectly at home. A conductive pattern is screen printed using conductive ink (silver paste) on the surface of a calendar-type pill organizer containing medications for as long as 1 week (4 times per day × 7 days, 28 doses) to create a sensor for detecting the opening of a pill organizer. Whenever the patient opens the pill organizer and removes a dose of the drug (pill), information about which of the 28 locations is opened and the date of opening are recorded in nonvolatile memory. This system is applicable to patients who take multiple drugs, for whom recording of drug-taking behavior is reportedly difficult. Specific benefits are that the user needs no additional manipulation to use the system: the user can take the drug from the pill organizer according to usual procedures.

Design of nuclear emergency decision-making support system based on the results of radiation monitoring

International Nuclear Information System (INIS)

Zheng Qiyan; Zhang Lijun; Huang Weiqi; Chen Lin

2010-01-01

For nuclear emergency decision-making support system based on the results of radiation monitoring, its main assignment is receiving radiation monitoring data and analyzing them, to accomplish some works such as environment influence evaluation, dose assessment for emergency responder, decision-making analyzing and effectiveness evaluation for emergency actions, etc.. This system is made up of server, communication terminal, data-analyzing terminal, GPRS modules, printer, and so on. The whole system make of a LAN. The system's software is made up of six subsystems: data-analyzing subsystem, reporting subsystem, GIS subsystem, communication subsystem, user-managing subsystem and data-base. (authors)

The Effect of Realtime Monitoring on Dose Exposure to Staff Within an Interventional Radiology Setting

Energy Technology Data Exchange (ETDEWEB)

Baumann, Frederic, E-mail: fredericbaumann@hotmail.com; Katzen, Barry T. [Baptist Hospital of Miami, Miami Cardiac & Vascular Institute (MCVI) (United States); Carelsen, Bart [Philips HealthCare, Clinical Science Interventional X-ray (Netherlands); Diehm, Nicolas [Kantonsspital Aarau, Clinical and Interventional Angiology (Switzerland); Benenati, James F.; Peña, Constantino S. [Baptist Hospital of Miami, Miami Cardiac & Vascular Institute (MCVI) (United States)

2015-10-15

PurposeThe purpose of this study is to evaluate a new device providing real-time monitoring on radiation exposure during fluoroscopy procedures intending to reduce radiation in an interventional radiology setting.Materials and MethodsIn one interventional suite, a new system providing a real-time radiation dose display and five individual wireless dosimeters were installed. The five dosimeters were worn by the attending, fellow, nurse, technician, and anesthesiologist for every procedure taking place in that suite. During the first 6-week interval the dose display was off (closed phase) and activated thereafter, for a 6-week learning phase (learning phase) and a 10-week open phase (open phase). During these phases, the staff dose and the individual dose for each procedure were recorded from the wireless dosimeter and correlated with the fluoroscopy time. Further subanalysis for dose exposure included diagnostic versus interventional as well as short (<10 min) versus long (>10 min) procedures.ResultsA total of 252 procedures were performed (n = 88 closed phase, n = 50 learning phase, n = 114 open phase). The overall mean staff dose per fluoroscopic minute was 42.79 versus 19.81 µSv/min (p < 0.05) comparing the closed and open phase. Thereby, anesthesiologists were the only individuals attaining a significant dose reduction during open phase 16.9 versus 8.86 µSv/min (p < 0.05). Furthermore, a significant reduction of total staff dose was observed for short 51 % and interventional procedures 45 % (p < 0.05, for both).ConclusionA real-time qualitative display of radiation exposure may reduce team radiation dose. The process may take a few weeks during the learning phase but appears sustained, thereafter.

The Effect of Realtime Monitoring on Dose Exposure to Staff Within an Interventional Radiology Setting

International Nuclear Information System (INIS)

Baumann, Frederic; Katzen, Barry T.; Carelsen, Bart; Diehm, Nicolas; Benenati, James F.; Peña, Constantino S.

2015-01-01

PurposeThe purpose of this study is to evaluate a new device providing real-time monitoring on radiation exposure during fluoroscopy procedures intending to reduce radiation in an interventional radiology setting.Materials and MethodsIn one interventional suite, a new system providing a real-time radiation dose display and five individual wireless dosimeters were installed. The five dosimeters were worn by the attending, fellow, nurse, technician, and anesthesiologist for every procedure taking place in that suite. During the first 6-week interval the dose display was off (closed phase) and activated thereafter, for a 6-week learning phase (learning phase) and a 10-week open phase (open phase). During these phases, the staff dose and the individual dose for each procedure were recorded from the wireless dosimeter and correlated with the fluoroscopy time. Further subanalysis for dose exposure included diagnostic versus interventional as well as short (<10 min) versus long (>10 min) procedures.ResultsA total of 252 procedures were performed (n = 88 closed phase, n = 50 learning phase, n = 114 open phase). The overall mean staff dose per fluoroscopic minute was 42.79 versus 19.81 µSv/min (p < 0.05) comparing the closed and open phase. Thereby, anesthesiologists were the only individuals attaining a significant dose reduction during open phase 16.9 versus 8.86 µSv/min (p < 0.05). Furthermore, a significant reduction of total staff dose was observed for short 51 % and interventional procedures 45 % (p < 0.05, for both).ConclusionA real-time qualitative display of radiation exposure may reduce team radiation dose. The process may take a few weeks during the learning phase but appears sustained, thereafter

Modification of beta dose evaluation algorithm for better accuracy in personnel monitoring

International Nuclear Information System (INIS)

Rakesh, R.B.; Kumar, Munish; Sneha, C.; Ratna, P.; Datta, D.

2016-01-01

Dose due to beta radiations is the main contributor to the skin dose. Assessment of individual dose (whole body, skin, extremity) in India is based on CaSO 4 :Dy based Teflon embedded TLD badge used for personnel monitoring. The design of the dosemeter enables identification of radiation type which, in turn, allows use of radiation specific algorithm for dose evaluation. The difference of response of three discs of the TLD badge to beta radiation in beta/beta-gamma fields is due to the presence of different filters corresponding to the three discs. The response of disc under metal filter (D 1 ) to beta being negligible while that of open disc (D 3 ) is the maximum. The ratio of response of open disc to that under Perspex (D 3 /D 2 ) to beta is highly dependent on its energy and angle of incidence. Therefore estimation of dose due to beta is based on response of open disc corrected for the energy of beta using D 3 /D 2

The development of web monitoring digital area monitor

International Nuclear Information System (INIS)

Jung, Hoon-Jin; Lee, Jun-Hee; Namkoong, Phil; Lee, Dong-Hoon; Lee, Su-Hong; Kim, We-Su

2005-01-01

As CCTV and radiation area monitor have been used separately to date, there have existed inconveniences in managing the view images and radiation dose rates from them. Thus we became to develop the web monitoring digital area monitor which incorporated the existing two factors, CCTV and radiation area monitor, into one. As incorporated with digitalisation, this device will usually become linked with PC, so that the view image and radiation dose rate can be concurrently identified in convenience. These measured figures automatically become data-based on PC by SW program, and become displayed in various format. Moreover, they can be monitored in remote and real time basis in the internet environment. Its local unit uses the cost-effective GM tube and CMOS image sensor, and has the small LCD which directly indicates the measured dose rate. The image sensor is designed to be operated with pan and tilt motion, thus can eliminate the dead view zone. It is thought that the developed device at this time could make the radiation safety management of each work field be done with low cost-high efficiency manner, making role of the CCTV inspection system

The development of web monitoring digital area monitor

Energy Technology Data Exchange (ETDEWEB)

Jung, Hoon-Jin; Lee, Jun-Hee; Namkoong, Phil; Lee, Dong-Hoon; Lee, Su-Hong; Kim, We-Su [Iljin Radiation Engineering Co., Seoul (Korea, Republic of)

2005-11-15

As CCTV and radiation area monitor have been used separately to date, there have existed inconveniences in managing the view images and radiation dose rates from them. Thus we became to develop the web monitoring digital area monitor which incorporated the existing two factors, CCTV and radiation area monitor, into one. As incorporated with digitalisation, this device will usually become linked with PC, so that the view image and radiation dose rate can be concurrently identified in convenience. These measured figures automatically become data-based on PC by SW program, and become displayed in various format. Moreover, they can be monitored in remote and real time basis in the internet environment. Its local unit uses the cost-effective GM tube and CMOS image sensor, and has the small LCD which directly indicates the measured dose rate. The image sensor is designed to be operated with pan and tilt motion, thus can eliminate the dead view zone. It is thought that the developed device at this time could make the radiation safety management of each work field be done with low cost-high efficiency manner, making role of the CCTV inspection system.

6LiF sandwich type detectors for low dose individual monitoring in mixed neutron-photon fields

International Nuclear Information System (INIS)

Olko, P.; Budzanowski, M.; Bilski, P.; Burgkhardt, B.; Piesch, E.

1994-01-01

ICRP Publication 60 recommends the reduction of the annual dose limit for occupational exposure from 50 to 20 mSv and a doubling of the quality factor for medium energy neutrons. If occupational doses are evaluated every month (which is obligatory e.g. in Germany and in Poland), the individual neutron dosemeter will have to measure neutron doses in the range of 100 μSv. No commercially available, automatic individual dosimetry monitoring system exists that fulfils this requirement. Some of the parameters which influence the evaluation of the neutron dose from readings of TL dosemeters have been studied in order to decrease the variance of the measured neutron signal. In mixed neutron-photon fields, clear separation of the neutron component from the total reading depends also on the uncertainty of the gamma dose measurements. While the thermal albedo neutrons are absorbed mostly at the surface of the 6 LiF detector, the reduction of the detector thickness results in a decrease of its photon sensitivity, while its neutron sensitivity is almost principally maintained. As a consequence, the uncertainty of gamma dose contributes with lower weight to the variance of the evaluated neutron signal. First tests of an optimised 200 μm thick sandwich detector and 0.9 mm thick standard LiF chips were made at low neutron and photon dose ranges using different readers, in order to determine the uncertainty versus dose for different neutron-photon combinations. The conditions under which the new sandwich type detectors may improve albedo neutron dosimetry are demonstrated. (Author)

Integrated photovoltaic (PV) monitoring system

Science.gov (United States)

Mahinder Singh, Balbir Singh; Husain, NurSyahidah; Mohamed, Norani Muti

2012-09-01

The main aim of this research work is to design an accurate and reliable monitoring system to be integrated with solar electricity generating system. The performance monitoring system is required to ensure that the PVEGS is operating at an optimum level. The PV monitoring system is able to measure all the important parameters that determine an optimum performance. The measured values are recorded continuously, as the data acquisition system is connected to a computer, and data is stored at fixed intervals. The data can be locally used and can also be transmitted via internet. The data that appears directly on the local monitoring system is displayed via graphical user interface that was created by using Visual basic and Apache software was used for data transmission The accuracy and reliability of the developed monitoring system was tested against the data that captured simultaneously by using a standard power quality analyzer device. The high correlation which is 97% values indicates the level of accuracy of the monitoring system. The aim of leveraging on a system for continuous monitoring system is achieved, both locally, and can be viewed simultaneously at a remote system.

Dose reader CD-02

International Nuclear Information System (INIS)

Jakowiuk, A.; Kaluska, I.; Machaj, B.

2005-01-01

Dose Reader CD-02 is designed for measurement of dose from a long narrow band of dosimetric foil used for check up and control of electron beam dose during sterilization of materials and products on conveyor belt. Irradiated foil after processing (heating) is inserted into foil driving (moving) system and when the foil is moved across focused light beam the absorbed dose is measured and displayed at the same time at computer monitor (in form of a diagram). The absorbed dose is measured on the principle of light attenuation at selected light wavelength (foil absorbance is measured). (author)

Cloud-based CT dose monitoring using the DICOM-structured report. Fully automated analysis in regard to national diagnostic reference levels

International Nuclear Information System (INIS)

Boos, J.; Rubbert, C.; Heusch, P.; Lanzman, R.S.; Aissa, J.; Antoch, G.; Kroepil, P.

2016-01-01

To implement automated CT dose data monitoring using the DICOM-Structured Report (DICOM-SR) in order to monitor dose-related CT data in regard to national diagnostic reference levels (DRLs). Materials and Methods: We used a novel in-house co-developed software tool based on the DICOM-SR to automatically monitor dose-related data from CT examinations. The DICOM-SR for each CT examination performed between 09/2011 and 03/2015 was automatically anonymized and sent from the CT scanners to a cloud server. Data was automatically analyzed in accordance with body region, patient age and corresponding DRL for volumetric computed tomography dose index (CTDI vol ) and dose length product (DLP). Results: Data of 36 523 examinations (131 527 scan series) performed on three different CT scanners and one PET/CT were analyzed. The overall mean CTDI vol and DLP were 51.3 % and 52.8 % of the national DRLs, respectively. CTDI vol and DLP reached 43.8 % and 43.1 % for abdominal CT (n = 10 590), 66.6 % and 69.6 % for cranial CT (n = 16 098) and 37.8 % and 44.0 % for chest CT (n = 10 387) of the compared national DRLs, respectively. Overall, the CTDI vol exceeded national DRLs in 1.9 % of the examinations, while the DLP exceeded national DRLs in 2.9 % of the examinations. Between different CT protocols of the same body region, radiation exposure varied up to 50 % of the DRLs. Conclusion: The implemented cloud-based CT dose monitoring based on the DICOM-SR enables automated benchmarking in regard to national DRLs. Overall the local dose exposure from CT reached approximately 50 % of these DRLs indicating that DRL actualization as well as protocol-specific DRLs are desirable. The cloud-based approach enables multi-center dose monitoring and offers great potential to further optimize radiation exposure in radiological departments.

The new German regulatory system of monitoring workers for intakes of radioactivity with special reference to thorium

International Nuclear Information System (INIS)

Henrichs, K.

1995-01-01

In Germany, the Association for Radiation Protection (member of IRPA) defined a new standard for the monitoring of workers occupationally exposed to radioactive material. During the last two years this draft has been accepted by the German government in the form of three directives. The purpose of our approach was the installation of a system defining clear criteria for the necessity of regular and special monitoring programs, giving directives for monitoring programs ensuring that dose assessments are as reliable as necessary with the lowest possible expenses, standardizing as far as possible the procedures of dose assessments, and guaranteeing the necessary quality standards. The most important features of these regulations will be discussed in this contribution and their application will be exemplified for the specially difficult monitoring of thorium intakes. (author). 2 figs., 2 tabs

Estimation of patient-specific imaging dose for real-time tumour monitoring in lung patients during respiratory-gated radiotherapy

Science.gov (United States)

Shiinoki, Takehiro; Onizuka, Ryota; Kawahara, Daisuke; Suzuki, Tatsuhiko; Yuasa, Yuki; Fujimoto, Koya; Uehara, Takuya; Hanazawa, Hideki; Shibuya, Keiko

2018-03-01

Purpose: To quantify the patient-specific imaging dose for real-time tumour monitoring in the lung during respiratory-gated stereotactic body radiotherapy (SBRT) in clinical cases using SyncTraX. Methods and Materials: Ten patients who underwent respiratory-gated SBRT with SyncTraX were enrolled in this study. The imaging procedure for real-time tumour monitoring using SyncTraX was simulated using Monte Carlo. We evaluated the dosimetric effect of a real-time tumour monitoring in a critical organ at risk (OAR) and the planning target volume (PTV) over the course of treatment. The relationship between skin dose and gating efficiency was also investigated. Results: For all patients, the mean D50 to the PTV, ipsilateral lung, liver, heart, spinal cord and skin was 118.3 (21.5–175.9), 31.9 (9.5–75.4), 15.4 (1.1–31.6), 10.1 (1.3–18.1), 25.0 (1.6–101.8), and 3.6 (0.9–7.1) mGy, respectively. The mean D2 was 352.0 (26.5–935.8), 146.4 (27.3–226.7), 90.7 (3.6–255.0), 42.2 (4.8–82.7), 88.0 (15.4–248.5), and 273.5 (98.3–611.6) mGy, respectively. The D2 of the skin dose was found to increase as the gating efficiency decreased. Conclusions: The additional dose to the PTV was at most 1.9% of the prescribed dose over the course of treatment for real-time tumour monitoring. For OARs, we could confirm the high dose region, which may not be susceptible to radiation toxicity. However, to reduce the skin dose from SyncTraX, it is necessary to increase the gating efficiency.

Radiation protection monitoring at the JOYO experimental fast reactor

International Nuclear Information System (INIS)

Ouchi, S.; Endo, K.; Susaki, T.

1979-01-01

This paper describes the radiation protection monitoring programme for the JOYO experimental fast reactor and some of the health physics problems experienced during the low-power nuclear tests. These include: a detailed description of the centralized radiation monitoring system; the methods and results of the individual monitoring systems; the results of operational monitoring for the handling of new plutonium fuel subassemblies; the evaluation of the external radiation dose rate around the primary coolant system; and the results of an experiment on the thermal dependence of some personnel dose meters. (author)

Development of automatic gamma and neutron monitoring system for PFBR fuel subassemblies at IFSB

International Nuclear Information System (INIS)

Krishnakumar, D.N.; Dhanasekaran, A.; Ajoy, K.C.; Jose, M.T.; Baskaran, R.; Sureshkumar, K.V.

2018-01-01

Health physics surveillance during PFBR fuel pin assembling operation at Interim Fuel Storage Building (IFSB) mandates scanning of the fuel assembly using Telector and Rem counter to find out the maximum gamma and neutron dose rates respectively. Throughout the process health physicist involved in the operation must hold the survey meter at a constant distance from the subassembly and simultaneously should make a note of dose rate values displayed. This practice might lead to the occupational exposures and also might induce human errors during measurements. To make this process more simple, faultless and effortless, an automatic Gamma Neutron Monitoring System (AGNMS) is designed and developed at RSD to measure, store and visualize instantaneous gamma and neutron dose rates of PFBR fuel subassembly. Development of the system, calibration and deployment of the system at IFSB and preliminary results obtained using the system is depicted in this paper

Long-term ingestion dose monitoring in a population group with increased 137Cs intake

International Nuclear Information System (INIS)

Bartuskova, M.; Lusnak, J.; Malatova, I.; Pfeiferova, V.; Pospisilova, H.

2008-01-01

137 Cs amounts and ingestion doses in Czech population have been monitored by whole-body counting since the Chernobyl accident. Indirect estimation of the retention through measurement of 137 Cs excreted with urine in 24 hours has also been performed since 1987. The 137 Cs content in human body can be calculated from the urine data provided that the intake of 137 Cs during the period of interest is constant. In a semi-natural environment, the 137 Cs content in mushrooms, wild berries and game decreases due to its natural decay solely. The 137 Cs content in people who mostly consume venison and have been living in an area with elevated contamination has been monitored, mostly through measurement of 137 Cs in urine. In parallel, measurements with a mobile whole-body counter have also been performed. Currently, annual doses from the ingestion of 137 Cs in the inhabitants are very low (0.001 to 0.002 mSv.year -1 ). In a group of hunters in the Jeseniky Mountains (Northern Moravia) the doses were estimated to 0.10 mSv.year -1 . (orig.)

Machine learning-based patient specific prompt-gamma dose monitoring in proton therapy

Science.gov (United States)

Gueth, P.; Dauvergne, D.; Freud, N.; Létang, J. M.; Ray, C.; Testa, E.; Sarrut, D.

2013-07-01

Online dose monitoring in proton therapy is currently being investigated with prompt-gamma (PG) devices. PG emission was shown to be correlated with dose deposition. This relationship is mostly unknown under real conditions. We propose a machine learning approach based on simulations to create optimized treatment-specific classifiers that detect discrepancies between planned and delivered dose. Simulations were performed with the Monte-Carlo platform Gate/Geant4 for a spot-scanning proton therapy treatment and a PG camera prototype currently under investigation. The method first builds a learning set of perturbed situations corresponding to a range of patient translation. This set is then used to train a combined classifier using distal falloff and registered correlation measures. Classifier performances were evaluated using receiver operating characteristic curves and maximum associated specificity and sensitivity. A leave-one-out study showed that it is possible to detect discrepancies of 5 mm with specificity and sensitivity of 85% whereas using only distal falloff decreases the sensitivity down to 77% on the same data set. The proposed method could help to evaluate performance and to optimize the design of PG monitoring devices. It is generic: other learning sets of deviations, other measures and other types of classifiers could be studied to potentially reach better performance. At the moment, the main limitation lies in the computation time needed to perform the simulations.

Machine learning-based patient specific prompt-gamma dose monitoring in proton therapy

International Nuclear Information System (INIS)

Gueth, P; Freud, N; Létang, J M; Sarrut, D; Dauvergne, D; Ray, C; Testa, E

2013-01-01

Online dose monitoring in proton therapy is currently being investigated with prompt-gamma (PG) devices. PG emission was shown to be correlated with dose deposition. This relationship is mostly unknown under real conditions. We propose a machine learning approach based on simulations to create optimized treatment-specific classifiers that detect discrepancies between planned and delivered dose. Simulations were performed with the Monte-Carlo platform Gate/Geant4 for a spot-scanning proton therapy treatment and a PG camera prototype currently under investigation. The method first builds a learning set of perturbed situations corresponding to a range of patient translation. This set is then used to train a combined classifier using distal falloff and registered correlation measures. Classifier performances were evaluated using receiver operating characteristic curves and maximum associated specificity and sensitivity. A leave-one-out study showed that it is possible to detect discrepancies of 5 mm with specificity and sensitivity of 85% whereas using only distal falloff decreases the sensitivity down to 77% on the same data set. The proposed method could help to evaluate performance and to optimize the design of PG monitoring devices. It is generic: other learning sets of deviations, other measures and other types of classifiers could be studied to potentially reach better performance. At the moment, the main limitation lies in the computation time needed to perform the simulations. (paper)

Dose profile monitoring with carbon ions by means of prompt-gamma measurements

Energy Technology Data Exchange (ETDEWEB)

Testa, E. [Institut de Physique Nucleaire de Lyon, Universite de Lyon, F-69003 Lyon, Universite Lyon 1 and IN2P3/CNRS, UMR 5822, F-69622 Villeurbanne (France)], E-mail: e.testa@ipnl.in2p3.fr; Bajard, M.; Chevallier, M.; Dauvergne, D.; Le Foulher, F. [Institut de Physique Nucleaire de Lyon, Universite de Lyon, F-69003 Lyon, Universite Lyon 1 and IN2P3/CNRS, UMR 5822, F-69622 Villeurbanne (France); Freud, N.; Letang, J.M. [Institut National des Sciences Appliquees de Lyon, Laboratoire de Controle Non-Destructif par Rayonnements Ionisants (France); Poizat, J.C.; Ray, C.; Testa, M. [Institut de Physique Nucleaire de Lyon, Universite de Lyon, F-69003 Lyon, Universite Lyon 1 and IN2P3/CNRS, UMR 5822, F-69622 Villeurbanne (France)

2009-03-15

A key point in the quality control of ion therapy is real-time monitoring and imaging of the dose delivered to the patient. Among the possible signals that can be used to make such a monitoring, prompt gamma-rays issued from nuclear fragmentation are possible candidates, provided the correlation between the emission profile and the primary beam range can be established. By means of simultaneous energy and time-of-flight discrimination, we could measure the longitudinal profile of the prompt gamma-rays emitted by 73 MeV/u carbon ions stopping inside a PMMA target. This technique allowed us to minimize the shielding against neutrons and scattered gamma rays, and to find a good correlation between the prompt-gamma profile and the ion range. This profile was studied as a function of the observation angle. By extrapolating our results to higher energies and realistic detection efficiencies, we showed that prompt gamma-ray measurements make it feasible to control in real time the longitudinal dose during ion therapy treatments.

Monitoring of congenital anomalies in Japan

International Nuclear Information System (INIS)

Kuroki, Y.; Konishi, H.

1992-01-01

Birth defects monitoring system is one of the most effective strategies to prevent birth defects mainly caused by environmental factors. Six different monitoring systems are working in Japan. Three of them are population-based and the other three hospital-based, both are widely scattered in Japan. Basic methodological designs of all birth defects monitoring systems are same. Therefore, the combination of them seems to be ideal. Total number of births surveyed in all systems are 283,000 annually. Each system has already accumulated relevant baseline data. Birth defects monitoring has another function to test the safety of widely exposed factors such as smoking, alcohol, low dose radiations, etc. Maternal smoking has some adverse effects on morphogenesis of the fetus. However, low dose radiations during or before pregnancy have no significant teratogenic effects on the fetus. The genetic effects of the Chernobyl nuclear power plant accident was studied. The annual effective dose equivalent to Japanese population due to radioactive fallout from the accident was assessed to be 5 μSv/y. No measurable mutagenic effects were recognized in Kanagawa by the analysis of three sentinel anomalies. (author)

Inductive Monitoring System (IMS)

Data.gov (United States)

National Aeronautics and Space Administration — IMS: Inductive Monitoring System The Inductive Monitoring System (IMS) is a tool that uses a data mining technique called clustering to extract models of normal...

CERN safety system monitoring - SSM

International Nuclear Information System (INIS)

Hakulinen, T.; Ninin, P.; Valentini, F.; Gonzalez, J.; Salatko-Petryszcze, C.

2012-01-01

CERN SSM (Safety System Monitoring) is a system for monitoring state-of-health of the various access and safety systems of the CERN site and accelerator infrastructure. The emphasis of SSM is on the needs of maintenance and system operation with the aim of providing an independent and reliable verification path of the basic operational parameters of each system. Included are all network-connected devices, such as PLCs (local purpose control unit), servers, panel displays, operator posts, etc. The basic monitoring engine of SSM is a freely available system-monitoring framework Zabbix, on top of which a simplified traffic-light-type web-interface has been built. The web-interface of SSM is designed to be ultra-light to facilitate access from hand-held devices over slow connections. The underlying Zabbix system offers history and notification mechanisms typical of advanced monitoring systems. (authors)

Verification of the calculation program for brachytherapy planning system of high dose rate (PLATO)

International Nuclear Information System (INIS)

Almansa, J.; Alaman, C.; Perez-Alija, J.; Herrero, C.; Real, R. del; Ososrio, J. L.

2011-01-01

In our treatments are performed brachytherapy high dose rate since 2007. The procedures performed include gynecological intracavitary treatment and interstitial. The treatments are performed with a source of Ir-192 activity between 5 and 10 Ci such that small variations in treatment times can cause damage to the patient. In addition the Royal Decree 1566/1998 on Quality Criteria in radiotherapy establishes the need to verify the monitor units or treatment time in radiotherapy and brachytherapy. All this justifies the existence of a redundant system for brachytherapy dose calculation that can reveal any abnormality is present.

[Monitoring medication errors in personalised dispensing using the Sentinel Surveillance System method].

Science.gov (United States)

Pérez-Cebrián, M; Font-Noguera, I; Doménech-Moral, L; Bosó-Ribelles, V; Romero-Boyero, P; Poveda-Andrés, J L

2011-01-01

To assess the efficacy of a new quality control strategy based on daily randomised sampling and monitoring a Sentinel Surveillance System (SSS) medication cart, in order to identify medication errors and their origin at different levels of the process. Prospective quality control study with one year follow-up. A SSS medication cart was randomly selected once a week and double-checked before dispensing medication. Medication errors were recorded before it was taken to the relevant hospital ward. Information concerning complaints after receiving medication and 24-hour monitoring were also noted. Type and origin error data were assessed by a Unit Dose Quality Control Group, which proposed relevant improvement measures. Thirty-four SSS carts were assessed, including 5130 medication lines and 9952 dispensed doses, corresponding to 753 patients. Ninety erroneous lines (1.8%) and 142 mistaken doses (1.4%) were identified at the Pharmacy Department. The most frequent error was dose duplication (38%) and its main cause inappropriate management and forgetfulness (69%). Fifty medication complaints (6.6% of patients) were mainly due to new treatment at admission (52%), and 41 (0.8% of all medication lines), did not completely match the prescription (0.6% lines) as recorded by the Pharmacy Department. Thirty-seven (4.9% of patients) medication complaints due to changes at admission and 32 matching errors (0.6% medication lines) were recorded. The main cause also was inappropriate management and forgetfulness (24%). The simultaneous recording of incidences due to complaints and new medication coincided in 33.3%. In addition, 433 (4.3%) of dispensed doses were returned to the Pharmacy Department. After the Unit Dose Quality Control Group conducted their feedback analysis, 64 improvement measures for Pharmacy Department nurses, 37 for pharmacists, and 24 for the hospital ward were introduced. The SSS programme has proven to be useful as a quality control strategy to identify Unit

Dose linearity and uniformity of a linear accelerator designed for implementation of multileaf collimation system-based intensity modulated radiation therapy

International Nuclear Information System (INIS)

Saw, Cheng B.; Li Sicong; Ayyangar, Komanduri M.; Yoe-Sein, Maung; Pillai, Susha; Enke, Charles A.; Celi, Juan C.

2003-01-01

The dose linearity and uniformity of a linear accelerator designed for multileaf collimation system- (MLC) based IMRT was studied as a part of commissioning and also in response to recently published data. The linear accelerator is equipped with a PRIMEVIEW, a graphical interface and a SIMTEC IM-MAXX, which is an enhanced autofield sequencer. The SIMTEC IM-MAXX sequencer permits the radiation beam to be 'ON' continuously while delivering intensity modulated radiation therapy subfields at a defined gantry angle. The dose delivery is inhibited when the electron beam in the linear accelerator is forced out of phase with the microwave power while the MLC configures the field shape of a subfield. This beam switching mechanism reduces the overhead time and hence shortens the patient treatment time. The dose linearity, reproducibility, and uniformity were assessed for this type of dose delivery mechanism. The subfields with monitor units ranged from 1 MU to 100 MU were delivered using 6 MV and 23 MV photon beams. The doses were computed and converted to dose per monitor unit. The dose linearity was found to vary within 2% for both 6 MV and 23 MV photon beam using high dose rate setting (300 MU/min) except below 2 MU. The dose uniformity was assessed by delivering 4 subfields to a Kodak X-OMAT TL film using identical low monitor units. The optical density was converted to dose and found to show small variation within 3%. Our results indicate that this linear accelerator with SIMTEC IM-MAXX sequencer has better dose linearity, reproducibility, and uniformity than had been reported

Performance of a GM tube based environmental dose rate monitor operating in the Time-To-Count mode

Energy Technology Data Exchange (ETDEWEB)

Zickefoose, J.; Kulkarni, T.; Martinson, T.; Phillips, K.; Voelker, M. [Canberra Industries Inc. (United States)

2015-07-01

The events at the Fukushima Daiichi power plant in the aftermath of a natural disaster underline the importance of a large array of networked environmental monitors to cover areas around nuclear power plants. These monitors should meet a few basic criteria: have a uniform response over a wide range of gamma energies, have a uniform response over a wide range of incident angles, and have a large dynamic range. Many of these criteria are met if the probe is qualified to the international standard IEC 60532 (Radiation protection instrumentation - Installed dose rate meters, warning assemblies and monitors - X and gamma radiation of energy between 50 keV and 7 MeV), which specifically deals with energy response, angle of incidence, dynamic range, response time, and a number of environmental characteristics. EcoGamma is a dual GM tube environmental gamma radiation monitor designed specifically to meet the requirements of IEC 60532 and operate in the most extreme conditions. EcoGamma utilizes two energy compensated GM tubes operating with a Time-To-Count (TTC) collection algorithm. The TTC algorithm extends the lifetime and range of a GM tube significantly and allows the dual GM tube probe to achieve linearity over approximately 10 decades of gamma dose rate (from the Sv/hr range to 100 Sv/hr). In the TTC mode of operation, the GM tube is not maintained in a biased condition continuously. This is different from a traditional counting system where the GM tube is held at a constant bias continuously and the total number of strikes that the tube registers are counted. The traditional approach allows for good sensitivity, but does not lend itself to a long lifetime of the tube and is susceptible to linearity issues at high count rates. TTC on the other hand only biases the tube for short periods of time and in effect measures the time between events, which is statistically representative of the total strike rate. Since the tube is not continually biased, the life of the tube

Performance of a GM tube based environmental dose rate monitor operating in the Time-To-Count mode

International Nuclear Information System (INIS)

Zickefoose, J.; Kulkarni, T.; Martinson, T.; Phillips, K.; Voelker, M.

2015-01-01

The events at the Fukushima Daiichi power plant in the aftermath of a natural disaster underline the importance of a large array of networked environmental monitors to cover areas around nuclear power plants. These monitors should meet a few basic criteria: have a uniform response over a wide range of gamma energies, have a uniform response over a wide range of incident angles, and have a large dynamic range. Many of these criteria are met if the probe is qualified to the international standard IEC 60532 (Radiation protection instrumentation - Installed dose rate meters, warning assemblies and monitors - X and gamma radiation of energy between 50 keV and 7 MeV), which specifically deals with energy response, angle of incidence, dynamic range, response time, and a number of environmental characteristics. EcoGamma is a dual GM tube environmental gamma radiation monitor designed specifically to meet the requirements of IEC 60532 and operate in the most extreme conditions. EcoGamma utilizes two energy compensated GM tubes operating with a Time-To-Count (TTC) collection algorithm. The TTC algorithm extends the lifetime and range of a GM tube significantly and allows the dual GM tube probe to achieve linearity over approximately 10 decades of gamma dose rate (from the Sv/hr range to 100 Sv/hr). In the TTC mode of operation, the GM tube is not maintained in a biased condition continuously. This is different from a traditional counting system where the GM tube is held at a constant bias continuously and the total number of strikes that the tube registers are counted. The traditional approach allows for good sensitivity, but does not lend itself to a long lifetime of the tube and is susceptible to linearity issues at high count rates. TTC on the other hand only biases the tube for short periods of time and in effect measures the time between events, which is statistically representative of the total strike rate. Since the tube is not continually biased, the life of the tube

Annual dose distribution of Nuclear Malaysia radiation workers for monitoring period from year 2003 to 2007

International Nuclear Information System (INIS)

Hairul Nizam Idris; Azimawati Ahmad; Norain Ab Rahman

2008-08-01

Estimation of radiation dose (external exposure) received by Nuklear Malaysia's radiation workers are measured by using personal dosimetry device which are provided by SSDL-Nuklear Malaysia. Dose assessment report for monitoring period from year 2003 - 2007 shows that almost all radiation workers received annual doses less than 20 mSv, only in very small percentage of radiation workers received annual doses between 20.1 to 50 mSv and none of the workers received doses higher than 50 mSv/year. Exposure dose below 20 mSv/year (the new annual dose limit to be used in Malaysia soon) could be fully achieved by improving the compliance with the safety regulations and enhancing the awareness about radiation safety among the workers. (Author)

Copilot: Monitoring Embedded Systems

Science.gov (United States)

Pike, Lee; Wegmann, Nis; Niller, Sebastian; Goodloe, Alwyn

2012-01-01

Runtime verification (RV) is a natural fit for ultra-critical systems, where correctness is imperative. In ultra-critical systems, even if the software is fault-free, because of the inherent unreliability of commodity hardware and the adversity of operational environments, processing units (and their hosted software) are replicated, and fault-tolerant algorithms are used to compare the outputs. We investigate both software monitoring in distributed fault-tolerant systems, as well as implementing fault-tolerance mechanisms using RV techniques. We describe the Copilot language and compiler, specifically designed for generating monitors for distributed, hard real-time systems. We also describe two case-studies in which we generated Copilot monitors in avionics systems.

Oblique incidence of electron beams - comparisons between calculated and measured dose distributions

International Nuclear Information System (INIS)

Karcher, J.; Paulsen, F.; Christ, G.

2005-01-01

Clinical applications of high-energy electron beams, for example for the irradiation of internal mammary lymph nodes, can lead to oblique incidence of the beams. It is well known that oblique incidence of electron beams can alter the depth dose distribution as well as the specific dose per monitor unit. The dose per monitor unit is the absorbed dose in a point of interest of a beam, which is reached with a specific dose monitor value (DIN 6814-8[5]). Dose distribution and dose per monitor unit at oblique incidence were measured with a small-volume thimble chamber in a water phantom, and compared to both normal incidence and calculations of the Helax TMS 6.1 treatment planning system. At 4 MeV and 60 degrees, the maximum measured dose per monitor unit at oblique incidence was decreased up to 11%, whereas at 18MeV and 60 degrees this was increased up to 15% compared to normal incidence. Comparisons of measured and calculated dose distributions showed that the predicted dose at shallow depths is usually higher than the measured one, whereas it is smaller at depths beyond the depth of maximum dose. On the basis of the results of these comparisons, normalization depths and correction factors for the dose monitor value were suggested to correct the calculations of the dose per monitor unit. (orig.)

Waste monitoring system for effluents

International Nuclear Information System (INIS)

Macdonald, J.M.; Gomez, B.; Trujillo, L.; Malcom, J.E.; Nekimken, H.; Pope, N.; Bibeau, R.

1995-07-01

The waste monitoring system in use at Los Alamos National Laboratory's Plutonium Facility, TA-55, is a computer-based system that proves real-time information on industrial effluents. Remote computers monitor discharge events and data moves from one system to another via a local area network. This report describes the history, system design, summary, instrumentation list, displays, trending screens, and layout of the waste monitoring system

Criteria for calculation of effective dose from the individual monitoring; Criterios para calculo de dose efetiva a partir da monitoracao individual

Energy Technology Data Exchange (ETDEWEB)

NONE

2005-11-15

This Regulation refers to the requirements of the Regulation CNEN-NN.3.01. 'Basic Act of Radiological Protection', as expressed in the section 5.9, and its application to the effective dose calculation for individual occupationally exposed. from the internal and external individual monitoring data

TH-C-18A-08: A Management Tool for CT Dose Monitoring, Analysis, and Protocol Review

International Nuclear Information System (INIS)

Wang, J; Chan, F; Newman, B; Larson, D; Leung, A; Fleischmann, D; Molvin, L; Marsh, D; Zorich, C; Phillips, L

2014-01-01

Purpose: To develop a customizable tool for enterprise-wide managing of CT protocols and analyzing radiation dose information of CT exams for a variety of quality control applications Methods: All clinical CT protocols implemented on the 11 CT scanners at our institution were extracted in digital format. The original protocols had been preset by our CT management team. A commercial CT dose tracking software (DoseWatch,GE healthcare,WI) was used to collect exam information (exam date, patient age etc.), scanning parameters, and radiation doses for all CT exams. We developed a Matlab-based program (MathWorks,MA) with graphic user interface which allows to analyze the scanning protocols with the actual dose estimates, and compare the data to national (ACR,AAPM) and internal reference values for CT quality control. Results: The CT protocol review portion of our tool allows the user to look up the scanning and image reconstruction parameters of any protocol on any of the installed CT systems among about 120 protocols per scanner. In the dose analysis tool, dose information of all CT exams (from 05/2013 to 02/2014) was stratified on a protocol level, and within a protocol down to series level, i.e. each individual exposure event. This allows numerical and graphical review of dose information of any combination of scanner models, protocols and series. The key functions of the tool include: statistics of CTDI, DLP and SSDE, dose monitoring using user-set CTDI/DLP/SSDE thresholds, look-up of any CT exam dose data, and CT protocol review. Conclusion: our inhouse CT management tool provides radiologists, technologists and administration a first-hand near real-time enterprise-wide knowledge on CT dose levels of different exam types. Medical physicists use this tool to manage CT protocols, compare and optimize dose levels across different scanner models. It provides technologists feedback on CT scanning operation, and knowledge on important dose baselines and thresholds

Comparison of 3-dimensional dose reconstruction system between fluence-based system and dose measurement-guided system

Energy Technology Data Exchange (ETDEWEB)

Nakaguchi, Yuji, E-mail: nkgc2003@yahoo.co.jp [Department of Radiological Technology, Kumamoto University Hospital, Kumamoto (Japan); Ono, Takeshi [Faculty of Life Sciences, Kumamoto University, Kumamoto (Japan); Onitsuka, Ryota [Graduate School of Health Sciences, Kumamoto University, Kumamoto (Japan); Maruyama, Masato; Shimohigashi, Yoshinobu; Kai, Yudai [Department of Radiological Technology, Kumamoto University Hospital, Kumamoto (Japan)

2016-10-01

COMPASS system (IBA Dosimetry, Schwarzenbruck, Germany) and ArcCHECK with 3DVH software (Sun Nuclear Corp., Melbourne, FL) are commercial quasi-3-dimensional (3D) dosimetry arrays. Cross-validation to compare them under the same conditions, such as a treatment plan, allows for clear evaluation of such measurement devices. In this study, we evaluated the accuracy of reconstructed dose distributions from the COMPASS system and ArcCHECK with 3DVH software using Monte Carlo simulation (MC) for multi-leaf collimator (MLC) test patterns and clinical VMAT plans. In a phantom study, ArcCHECK 3DVH showed clear differences from COMPASS, measurement and MC due to the detector resolution and the dose reconstruction method. Especially, ArcCHECK 3DVH showed 7% difference from MC for the heterogeneous phantom. ArcCHECK 3DVH only corrects the 3D dose distribution of treatment planning system (TPS) using ArcCHECK measurement, and therefore the accuracy of ArcCHECK 3DVH depends on TPS. In contrast, COMPASS showed good agreement with MC for all cases. However, the COMPASS system requires many complicated installation procedures such as beam modeling, and appropriate commissioning is needed. In terms of clinical cases, there were no large differences for each QA device. The accuracy of the compass and ArcCHECK 3DVH systems for phantoms and clinical cases was compared. Both systems have advantages and disadvantages for clinical use, and consideration of the operating environment is important. The QA system selection is depending on the purpose and workflow in each hospital.

Daily dose monitoring with atlas-based auto-segmentation on diagnostic quality CT for prostate cancer

International Nuclear Information System (INIS)

Li, Wen; Vassil, Andrew; Xia, Ping; Zhong, Yahua

2013-01-01

Purpose: To evaluate the feasibility of daily dose monitoring using a patient specific atlas-based autosegmentation method on diagnostic quality verification images.Methods: Seven patients, who were treated for prostate cancer with intensity modulated radiotherapy under daily imaging guidance of a CT-on-rails system, were selected for this study. The prostate, rectum, and bladder were manually contoured on the first six and last seven sets of daily verification images. For each patient, three patient specific atlases were constructed using manual contours from planning CT alone (1-image atlas), planning CT plus first three verification CTs (4-image atlas), and planning CT plus first six verification CTs (7-image atlas). These atlases were subsequently applied to the last seven verification image sets of the same patient to generate the auto-contours. Daily dose was calculated by applying the original treatment plans to the daily beam isocenters. The autocontours and manual contours were compared geometrically using the dice similarity coefficient (DSC), and dosimetrically using the dose to 99% of the prostate CTV (D99) and the D5 of rectum and bladder.Results: The DSC of the autocontours obtained with the 4-image atlases were 87.0%± 3.3%, 84.7%± 8.6%, and 93.6%± 4.3% for the prostate, rectum, and bladder, respectively. These indices were higher than those from the 1-image atlases (p 0.05). Daily prostate D99 of the autocontours was comparable to those of the manual contours (p= 0.55). For the bladder and rectum, the daily D5 were 95.5%± 5.9% and 99.1%± 2.6% of the planned D5 for the autocontours compared to 95.3%± 6.7% (p= 0.58) and 99.8%± 2.3% (p < 0.01) for the manual contours.Conclusions: With patient specific 4-image atlases, atlas-based autosegmentation can adequately facilitate daily dose monitoring for prostate cancer

Daily dose monitoring with atlas-based auto-segmentation on diagnostic quality CT for prostate cancer

Energy Technology Data Exchange (ETDEWEB)

Li, Wen; Vassil, Andrew; Xia, Ping [Department of Radiation Oncology, Cleveland Clinic Foundation, Cleveland, Ohio 44106 (United States); Zhong, Yahua [Department of Radiation Oncology, Zhongnan Hospital, Wuhan 430071 (China)

2013-11-15

Purpose: To evaluate the feasibility of daily dose monitoring using a patient specific atlas-based autosegmentation method on diagnostic quality verification images.Methods: Seven patients, who were treated for prostate cancer with intensity modulated radiotherapy under daily imaging guidance of a CT-on-rails system, were selected for this study. The prostate, rectum, and bladder were manually contoured on the first six and last seven sets of daily verification images. For each patient, three patient specific atlases were constructed using manual contours from planning CT alone (1-image atlas), planning CT plus first three verification CTs (4-image atlas), and planning CT plus first six verification CTs (7-image atlas). These atlases were subsequently applied to the last seven verification image sets of the same patient to generate the auto-contours. Daily dose was calculated by applying the original treatment plans to the daily beam isocenters. The autocontours and manual contours were compared geometrically using the dice similarity coefficient (DSC), and dosimetrically using the dose to 99% of the prostate CTV (D99) and the D5 of rectum and bladder.Results: The DSC of the autocontours obtained with the 4-image atlases were 87.0%± 3.3%, 84.7%± 8.6%, and 93.6%± 4.3% for the prostate, rectum, and bladder, respectively. These indices were higher than those from the 1-image atlases (p < 0.01) and comparable to those from the 7-image atlases (p > 0.05). Daily prostate D99 of the autocontours was comparable to those of the manual contours (p= 0.55). For the bladder and rectum, the daily D5 were 95.5%± 5.9% and 99.1%± 2.6% of the planned D5 for the autocontours compared to 95.3%± 6.7% (p= 0.58) and 99.8%± 2.3% (p < 0.01) for the manual contours.Conclusions: With patient specific 4-image atlases, atlas-based autosegmentation can adequately facilitate daily dose monitoring for prostate cancer.

Biophysical Monitoring and dose response characteristics of irradiated hemoglobin

International Nuclear Information System (INIS)

Elshemey, W.M; Selim, N.S.; Desouky, O.

2003-01-01

The present work aims to move a step forward towards a deeper understanding of the scattering of x-ray, from lyophilized biological samples. Comparative study has been performed using LAXS and UV-visible spectrophotometry for monitoring the dose response characteristics of the hemoglobin molecule of irradiated blood. Blood samples were irradiated at doses ranging from 5 up to 100 Gy. Diluted hemoglobin solution was scanned in the UV- visible range (200-700 nm), and lyophilized hemoglobin was prepared for LAXS measurement. The radiation-induced changes in the hemoglobin structure have been evaluated. The LAXS profile of hemoglobin molecule is characterized by the presence of two peaks in the forward direction of scattering. These peaks were found to be sensitive to the variations in the molecular structure of a given sample. The obtained results suggest that the 1 s t peak, recorded at 4.65 o , is sensitive to the tertiary and quaternary structure of the globin part, while the major peak, recorded at 10.5 o , appeared to be related to its primary and secondary structure

Dose calculation system for remotely supporting radiotherapy

International Nuclear Information System (INIS)

Saito, K.; Kunieda, E.; Narita, Y.; Kimura, H.; Hirai, M.; Deloar, H. M.; Kaneko, K.; Ozaki, M.; Fujisaki, T.; Myojoyama, A.; Saitoh, H.

2005-01-01

The dose calculation system IMAGINE is being developed keeping in mind remotely supporting external radiation therapy using photon beams. The system is expected to provide an accurate picture of the dose distribution in a patient body, using a Monte Carlo calculation that employs precise models of the patient body and irradiation head. The dose calculation will be performed utilising super-parallel computing at the dose calculation centre, which is equipped with the ITBL computer, and the calculated results will be transferred through a network. The system is intended to support the quality assurance of current, widely carried out radiotherapy and, further, to promote the prevalence of advanced radiotherapy. Prototypes of the modules constituting the system have already been constructed and used to obtain basic data that are necessary in order to decide on the concrete design of the system. The final system will be completed in 2007. (authors)

Remote system for monitoring and control of controlled area of nuclear installation

Energy Technology Data Exchange (ETDEWEB)

Assuncao, Daniel Gomes de; Minhoni, Danilo Carlos Rossetto [Departamento de Ciencias da Administracao e Tecnologia. Centro Universitario de Araraquara (UNIARA) Araraquara, SP (Brazil); Farias, Marcos Sant' anna de; Santos, Isaac J.A. Luquetti dos, E-mail: luquetti@ien.gov.br [Instituto Engenharia Nuclear (IEN/CNEN-RJ), Rio Janeiro, RJ (Brazil). Divisao de Instrumentacao e Confiabilidade Humana

2011-07-01

The maintenance activities in controlled areas of nuclear facilities require adequate planning and control so that these activities do not cause to the worker an undue exposure to radioactivity. For maximum safety of workers from these places, there are standards that determine the maximum radiation dose that a worker can receive. From this context, the objective of this research is to develop a remote system that shows remotely the maintenance tasks being carried out in this work environment; monitors information provided by radiation monitoring devices installed at workplace; tracks the time to carry out scheduled maintenance, reporting alarm if this time is exceeded or not. The system has video camera, radiation monitoring device, interface card to transmit data via ethernet and graphical user interface, developed using the LABVIEW application. The principal objective is to improve the safety and to preserve the worker's health. (author)

Remote system for monitoring and control of controlled area of nuclear installation

International Nuclear Information System (INIS)

Assuncao, Daniel Gomes de; Minhoni, Danilo Carlos Rossetto; Farias, Marcos Sant'anna de; Santos, Isaac J.A. Luquetti dos

2011-01-01

The maintenance activities in controlled areas of nuclear facilities require adequate planning and control so that these activities do not cause to the worker an undue exposure to radioactivity. For maximum safety of workers from these places, there are standards that determine the maximum radiation dose that a worker can receive. From this context, the objective of this research is to develop a remote system that shows remotely the maintenance tasks being carried out in this work environment; monitors information provided by radiation monitoring devices installed at workplace; tracks the time to carry out scheduled maintenance, reporting alarm if this time is exceeded or not. The system has video camera, radiation monitoring device, interface card to transmit data via ethernet and graphical user interface, developed using the LABVIEW application. The principal objective is to improve the safety and to preserve the worker's health. (author)

Determination of the delivered hemodialysis dose using standard methods and on-line clearance monitoring

Directory of Open Access Journals (Sweden)

Vlatković Vlastimir

2006-01-01

Full Text Available Background/aim: Delivered dialysis dose has a cumulative effect and significant influence upon the adequacy of dialysis, quality of life and development of co-morbidity at patients on dialysis. Thus, a great attention is given to the optimization of dialysis treatment. On-line Clearance Monitoring (OCM allows a precise and continuous measurement of the delivered dialysis dose. Kt/V index (K = dialyzer clearance of urea; t = dialysis time; V = patient's total body water, measured in real time is used as a unit for expressing the dialysis dose. The aim of this research was to perform a comparative assessment of the delivered dialysis dose by the application of the standard measurement methods and a module for continuous clearance monitoring. Methods. The study encompassed 105 patients who had been on the chronic hemodialysis program for more than three months, three times a week. By random choice, one treatment per each controlled patient was taken. All the treatments understood bicarbonate dialysis. The delivered dialysis dose was determined by the calculation of mathematical models: Urea Reduction Ratio (URR singlepool index Kt/V (spKt/V and by the application of OCM. Results. Urea Reduction Ratio was the most sensitive parameter for the assessment and, at the same time, it was in the strongest correlation with the other two, spKt/V indexes and OCM. The values pointed out an adequate dialysis dose. The URR values were significantly higher in women than in men, p < 0.05. The other applied model for the delivered dialysis dose measurement was Kt/V index. The obtained values showed that the dialysis dose was adequate, and that, according to this parameter, the women had significantly better dialysis, then the men p < 0.05. According to the OCM, the average value was slightly lower than the adequate one. The women had a satisfactory dialysis according to this index as well, while the delivered dialysis dose was insufficient in men. The difference

Development of dose calibrators Tandem systems and establishment of beta dosimetry in nuclear medicine

International Nuclear Information System (INIS)

Cecatti, Sonia Garcia Pereira

2004-01-01

A quality control program at Nuclear Medicine Services includes the checking of all equipment used for diagnostics and treatment, and the individual monitoring of the workers occupationally exposed to ionizing radiations. In this work the main quality control tests were performed with three dose calibrators using standard radiation sources of 57 Co, 133 Ba, 137 Cs and 60 Co. Tandem systems of dose calibrators were established and characterized using four cylindrical absorbers of different materials for an additional quality control test in Nuclear Medicine. The main utility of this new test is the possibility of impurity detection in radiopharmaceuticals, when the ratio of the measurements with different absorbers is different from that obtained at the laboratory in ideal conditions. The dosimetric characteristics of three types of CaS0 4 :Dy + Teflon pellets were studied for an appropriate choice of the material to be used for individual monitoring of workers. The thermoluminescent detectors were irradiated using beta sources of 90 Sr+ 90 Y, 204 TI, 147 Pm, 153 Sm and 32 P. A wrist badge for beta individual monitoring was developed for workers that handle beta radiopharmaceuticals in Nuclear Medicine Services. (author)

Integrated systems of monitoring and environmental data processing for nuclear facilities

International Nuclear Information System (INIS)

Diaconu, C.; Guta, V.; Oprea, I.; Oprea, M.; Stoica, M.; Pirvu, V.; Vasilache, E.; Pirvu, I.

2001-01-01

The processing of huge amount of data necessary to assess the real radiological situation both in normal operational conditions and during accidents requires an efficient system of monitoring and data processing. It must be able to secure information for the complex systems of radioactivity control aiming at evaluating the nuclear accident consequences and establishing a basis for correct decision making in the field of civil protection. The integrated environmental monitoring systems are based on a number of fixed and mobile installations, a meteorological parameter measurement station, a center for data processing and a communication network, working all under the control of a real-time operation system. They collect, and process the radioactivity level and meteorological data and transmit them through the communication network. The local monitoring stations are made of detector ensembles with pressurized ionization chambers and autonomous units providing continuously information on dose and integrated rates, average values as well as the current state of the station. The meteorological data acquisition station supplies information concerning wind direction and speed, the temperature and precipitation level. The information processing center is based on a PC integrated in a local network which collects data from the radiation monitoring equipment, meteorological station as well as other work stations which process various dosimetric parameters. It is connected to Internet, so ensuring fast transfer of information towards interested authorities. The communication network consists in a local or extended Ethernet network, radio or serial connections for radioactivity level monitoring units which can be stationary, portable or mobile. Requirements raised by the application of geographic information system (GIS) and the real time operation system (QNX) ensuring multiuser and multitask operations are discussed

The Design of a γ-dose rate monitoring meter Based on C8051F020

International Nuclear Information System (INIS)

Tan Wei; Liu Chong; Wu Longxiong; Yang Binhua

2009-01-01

This paper presents the design of γ-dose-rate monitoring meter based on C8051F020 single chip microcomputer (SCM), and also describes the solution of hardware and software. The peripheral circuit of USB is also included. This meter can rapidly measure γ-dose-rate and store more data in power failure. In addition, it is featured with low power, small size, strong anti-interference and accurate measurement. (authors)

VME system monitor board

Energy Technology Data Exchange (ETDEWEB)

NONE

1996-02-01

Much of the machinery throughout the APS will be controlled by VME based computers. In order to increase the reliability of the system, it is necessary to be able to monitor the status of each VME crate. In order to do this, a VME System Monitor was created. In addition to being able to monitor and report the status (watchdog timer, temperature, CPU (Motorola MVME 167) state (status, run, fail), and the power supply), it includes provisions to remotely reset the CPU and VME crate, digital I/O, and parts of the transition module (serial port and ethernet connector) so that the Motorla MVME 712 is not needed. The standard VME interface was modified on the System Monitor so that in conjunction with the Motorola MVME 167 a message based VXI interrupt handler could is implemented. The System Monitor is a single VME card (6U). It utilizes both the front panel and the P2 connector for I/O. The front panel contains a temperature monitor, watchdog status LED, 4 general status LEDs, input for a TTL interrupt, 8 binary inputs (24 volt, 5 volt, and dry contact sense), 4 binary outputs (dry contact, TTL, and 100 mA), serial port (electrical RS-232 or fiber optic), ethernet transceiver (10 BASE-FO or AUI), and a status link to neighbor crates. The P2 connector is used to provide the serial port and ethernet to the processor. In order to abort and read the status of the CPU, a jumper cable must be connected between the CPU and the System Monitor.

Portable radiation monitors

International Nuclear Information System (INIS)

Masui, Kaoru; Ishikura, Takeshi; Inui, Daisuke

2007-01-01

This paper presents an overview of typical portable radiation monitors and introduces Fuji Electric's latest models. The overview describes the types, uses and performance of ion chamber survey meters, GM survey meters and neutron ambient dose equivalent rate meters. Fuji Electric's new model of a wide-energy-range X/gamma ray survey meter which measures low energy X-rays up to 8 keV, a battery-powered environmental dosemeter system which measures dose history and is capable of continuous measurement with batteries over a year, and a portable monitoring post which measures dose rates from background to 10 8 nGy/h and transmits data by cellular phone are introduced, and their specifications and performance are described. (author)

Environmental monitoring and information systems

International Nuclear Information System (INIS)

Gibbert, R.

1998-01-01

Environmental monitoring and information systems installed by Dornier are summarized. A broad spectrum of environmental areas from air quality and water to radioactivity is covered. Nuclear power plant monitoring systems, either as remote or plant-internal monitoring systems, form an important element of the work undertaken. The systems delivered covered local, regional or national areas. The range of services provided, and hardware and software platforms are listed. (R.P.)

Treatment dose-response in amblyopia therapy: the Monitored Occlusion Treatment of Amblyopia Study (MOTAS).

Science.gov (United States)

Stewart, Catherine E; Moseley, Merrick J; Stephens, David A; Fielder, Alistair R

2004-09-01

Amblyopia is the commonest visual disorder of childhood. Yet the contributions of the two principal treatments (spectacle wear and occlusion) to outcome are unknown. This study was undertaken to investigate the dose-response relationship of amblyopia therapy. The study comprised three distinct phases: baseline, in which repeat measures of visual function were undertaken to confirm the initial visual deficit; refractive adaptation: an 18-week period of spectacle wear with six weekly measurements of logarithm of the minimum angle of resolution (logMAR) visual acuity; occlusion: in which participants were prescribed 6 hours of "patching" per day. In the latter phase, occlusion was objectively monitored and logMAR visual acuity recorded at 2-week intervals until any observed gains had ceased. Data were obtained from 94 participants (mean age, 5.1 +/- 1.4 years) with amblyopia associated with strabismus (n = 34), anisometropia (n = 23), and both anisometropia and strabismus (n = 37). Eighty-six underwent refractive adaptation. Average concordance with patching was 48%. The relationship between logMAR visual acuity gain and total occlusion dose was monotonic and linear. Increasing dose rate beyond 2 h/d hastened the response but did not improve outcome. More than 80% of the improvement during occlusion occurred within 6 weeks. Treatment outcome was significantly better for children younger than 4 years (n = 17) than in those older than 6 years (n = 24; P = 0.0014). Continuous objective monitoring of the amount of patching therapy received has provided insight into the dose-response relationship of occlusion therapy for amblyopia. Patching is most effective within the first few weeks of treatment, even for those in receipt of a relatively small dose. Further studies are needed to elucidate the neural basis for the dose-response functions. Copyright Association for Research in Vision and Ophthalmology

Data monitoring system of technical diagnosis system for EAST

International Nuclear Information System (INIS)

Qian Jing; Weng Peide; Chen Zhuomin; Wu Yu; Xi Weibin; Luo Jiarong

2010-01-01

Technical diagnosis system (TDS) is an important subsystem to monitor status parameters of EAST (experimental advanced superconducting tokamak). The upgraded TDS data monitoring system is comprised of management floor, monitoring floor and field floor.. Security protection, malfunction record and analysis are designed to make the system stable, robust and friendly. During the past EAST campaigns, the data monitoring system has been operated reliably and stably. The signal conditioning system and software architecture are described. (authors)

The JOYO remote monitoring system

International Nuclear Information System (INIS)

Damico, Joseph P.; Hashimoto, Yu

2000-01-01

The evolution of the personal computer, operating systems and applications software and the Internet has brought drastic change and many benefits worldwide. Remote monitoring systems benefit from computer network and other modern software technologies. The availability of fast, inexpensive and secure communications enables new solutions for monitoring system applications. The JOYO Remote Monitoring System (RMS) utilizes computer network communications and modular software design to provide a distributed integrated solution for monitoring multiple storage locations. This paper describes the remote monitoring system installed at the JOYO Fast Reactor. The system combines sensors, software, and computer network technologies to create a powerful data collection, storage and dissemination capability. The RMS provides a flexible, scalable solution for a variety of applications. The RMS integrates a variety of state of the art technologies from several sources and serves as a test bed for cutting edge technologies that can be shared with outside users. This paper describes the system components and their operation and discusses system benefits. Current activities and future plants for the JOYO RMS will be discussed. (author)

Unattended Monitoring System Design Methodology

International Nuclear Information System (INIS)

Drayer, D.D.; DeLand, S.M.; Harmon, C.D.; Matter, J.C.; Martinez, R.L.; Smith, J.D.

1999-01-01

A methodology for designing Unattended Monitoring Systems starting at a systems level has been developed at Sandia National Laboratories. This proven methodology provides a template that describes the process for selecting and applying appropriate technologies to meet unattended system requirements, as well as providing a framework for development of both training courses and workshops associated with unattended monitoring. The design and implementation of unattended monitoring systems is generally intended to respond to some form of policy based requirements resulting from international agreements or domestic regulations. Once the monitoring requirements are established, a review of the associated process and its related facilities enables identification of strategic monitoring locations and development of a conceptual system design. The detailed design effort results in the definition of detection components as well as the supporting communications network and data management scheme. The data analyses then enables a coherent display of the knowledge generated during the monitoring effort. The resultant knowledge is then compared to the original system objectives to ensure that the design adequately addresses the fundamental principles stated in the policy agreements. Implementation of this design methodology will ensure that comprehensive unattended monitoring system designs provide appropriate answers to those critical questions imposed by specific agreements or regulations. This paper describes the main features of the methodology and discusses how it can be applied in real world situations

Oral dosing of chemical indicators for in vivo monitoring of Ca2+ dynamics in insect muscle.

Directory of Open Access Journals (Sweden)

Ferdinandus

Full Text Available This paper proposes a remarkably facile staining protocol to visually investigate dynamic physiological events in insect tissues. We attempted to monitor Ca2+ dynamics during contraction of electrically stimulated living muscle. Advances in circuit miniaturization and insect neuromuscular physiology have enabled the hybridization of living insects and man-made electronic components, such as microcomputers, the result of which has been often referred as a Living Machine, Biohybrid, or Cyborg Insect. In order for Cyborg Insects to be of practical use, electrical stimulation parameters need to be optimized to induce desired muscle response (motor action and minimize the damage in the muscle due to the electrical stimuli. Staining tissues and organs as well as measuring the dynamics of chemicals of interest in muscle should be conducted to quantitatively and systematically evaluate the effect of various stimulation parameters on the muscle response. However, existing staining processes require invasive surgery and/or arduous procedures using genetically encoded sensors. In this study, we developed a non-invasive and remarkably facile method for staining, in which chemical indicators can be orally administered (oral dosing. A chemical Ca2+ indicator was orally introduced into an insect of interest via food containing the chemical indicator and the indicator diffused from the insect digestion system to the target muscle tissue. We found that there was a positive relationship between the fluorescence intensity of the indicator and the frequency of electrical stimulation which indicates the orally dosed indicator successfully monitored Ca2+ dynamics in the muscle tissue. This oral dosing method has a potential to globally stain tissues including neurons, and investigating various physiological events in insects.

Oral dosing of chemical indicators for in vivo monitoring of Ca2+ dynamics in insect muscle.

Science.gov (United States)

Ferdinandus; Arai, Satoshi; Ishiwata, Shin'ichi; Suzuki, Madoka; Sato, Hirotaka

2015-01-01

This paper proposes a remarkably facile staining protocol to visually investigate dynamic physiological events in insect tissues. We attempted to monitor Ca2+ dynamics during contraction of electrically stimulated living muscle. Advances in circuit miniaturization and insect neuromuscular physiology have enabled the hybridization of living insects and man-made electronic components, such as microcomputers, the result of which has been often referred as a Living Machine, Biohybrid, or Cyborg Insect. In order for Cyborg Insects to be of practical use, electrical stimulation parameters need to be optimized to induce desired muscle response (motor action) and minimize the damage in the muscle due to the electrical stimuli. Staining tissues and organs as well as measuring the dynamics of chemicals of interest in muscle should be conducted to quantitatively and systematically evaluate the effect of various stimulation parameters on the muscle response. However, existing staining processes require invasive surgery and/or arduous procedures using genetically encoded sensors. In this study, we developed a non-invasive and remarkably facile method for staining, in which chemical indicators can be orally administered (oral dosing). A chemical Ca2+ indicator was orally introduced into an insect of interest via food containing the chemical indicator and the indicator diffused from the insect digestion system to the target muscle tissue. We found that there was a positive relationship between the fluorescence intensity of the indicator and the frequency of electrical stimulation which indicates the orally dosed indicator successfully monitored Ca2+ dynamics in the muscle tissue. This oral dosing method has a potential to globally stain tissues including neurons, and investigating various physiological events in insects.

Occupational radiation doses in Portugal from 1994 to 1998

International Nuclear Information System (INIS)

Alves, J.G.; Martins, M.B.; Amaral, E.M.

2000-01-01

This work reports on the occupational radiation doses for external radiation received in 1994-1998 by the radiation workers monitored by the Radiological Protection and Nuclear Safety Department (DPRSN) in Portugal. Individual monitoring for external radiation is carried out in Portugal by DPRSN since the 60s, and the workers are monitored on a monthly or quarterly bases. In 1995 DPRSN monitored approximately 8000 people and was the only laboratory carrying out this sort of activity in Portugal. In 1998 the number of monitored people increased to nearly 8500 from 860 facilities, which leads us to state that the results shown in this work are well representative of the universe of radiation workers in Portugal. Until 1996, the dose measurement procedure was based only on film dosimetry and the results reported for the 1994-1995 period were obtained with this methodology. Since 1996, thermoluminescent dosimetry (TLD) was gradually introduced and since then an effort has been made to transfer the monitored workers from film to TLD. In 1998, both film and TLD dosimetry systems were running simultaneously, with average numbers of 4500 workers monitored with film dosimetry, while 4000 were monitored with TLD. The data presented from 1996 to 1998 were obtained with both methodologies. This work reports the annual mean effective doses received from external radiation, for the monitored and exposed workers in the different fields of activity, namely, industry, research laboratories, health and mining. The distribution of the annual effective dose by dose intervals is also reported. The collective annual dose by field of activity is estimated and the contribution to the total annual collective dose is determined. The collective dose estimates for the period 1994 to 1998 demonstrated that the health sector is the most representative exposed group in Portugal. (author)

Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

Energy Technology Data Exchange (ETDEWEB)

Yussup, F., E-mail: nolida@nm.gov.my; Ibrahim, M. M., E-mail: maslina-i@nm.gov.my; Soh, S. C.; Hasim, H. [Instrumentation and Automation Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Haris, M. F. [Information Technology Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Azman, A. [Prototype and Development Centre, Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Razalim, F. A. A.; Yapp, R. [Health Physics Group, Radiation Safety and Health Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia); Ramli, A. A. M. [Technical Support Division, Malaysian Nuclear Agency, Bangi, 43000 Kajang. Selangor (Malaysia)

2016-01-22

With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering.

Upgrading of data acquisition software for centralized radiation monitoring system in Malaysian Nuclear Agency

International Nuclear Information System (INIS)

Yussup, F.; Ibrahim, M. M.; Soh, S. C.; Hasim, H.; Haris, M. F.; Azman, A.; Razalim, F. A. A.; Yapp, R.; Ramli, A. A. M.

2016-01-01

With the growth of technology, many devices and equipments can be connected to the network and internet to enable online data acquisition for real-time data monitoring and control from monitoring devices located at remote sites. Centralized radiation monitoring system (CRMS) is a system that enables area radiation level at various locations in Malaysian Nuclear Agency (Nuklear Malaysia) to be monitored centrally by using a web browser. The Local Area Network (LAN) in Nuclear Malaysia is utilized in CRMS as a communication media for data acquisition of the area radiation levels from radiation detectors. The development of the system involves device configuration, wiring, network and hardware installation, software and web development. This paper describes the software upgrading on the system server that is responsible to acquire and record the area radiation readings from the detectors. The recorded readings are called in a web programming to be displayed on a website. Besides the main feature which is acquiring the area radiation levels in Nuclear Malaysia centrally, the upgrading involves new features such as uniform time interval for data recording and exporting, warning system and dose triggering

Savannah River Plant remote environmental monitoring system

International Nuclear Information System (INIS)

Schubert, J.F.

1987-01-01

The SRP remote environmental monitoring system consists of separations facilities stack monitors, production reactor stack monitors, twelve site perimeter monitors, river and stream monitors, a geostationary operational environmental satellite (GOES) data link, reactor cooling lake thermal monitors, meteorological tower system, Weather Information and Display (WIND) system computer, and the VANTAGE data base management system. The remote environmental monitoring system when fully implemented will provide automatic monitoring of key stack releases and automatic inclusion of these source terms in the emergency response codes

The environmental radiation monitoring system and in-situ measurements for early notification and OIL (Operational Intervention Levels) calculations

International Nuclear Information System (INIS)

Haquin, G.; Ne'eman, E.; Brenner, S.; Lavi, N.

1997-01-01

The efficiency of the environmental radiation monitoring, low level laboratory and in-situ gamma-ray spectrometry are evaluated as the systems for early notification and for determination of dose rate in air, surface contamination and activity concentration in food during emergencies for Operational Intervention Levels (OIL) recalculation.The National Environmental Radiation Monitoring System has proved its efficiency in the early detection of unregistered radiography work. A mobile station of the network can be used for absorbed dose rate measurement during emergencies in contaminated areas. The calibrated in-situ gamma-ray spectrometry system in an open phosphate ore mine has showed the efficiency of this technique for fast and accurate determination of soil activity concentration. The calibration for an uniform depth distribution can be easily mathematically converted to an exponential depth distribution in cases of radioactive material fallout

Internal quality control program for individual monitoring service

Energy Technology Data Exchange (ETDEWEB)

Mauricio, Claudia L.P.; Moura Junior, Jose; Patrao, Karla C.S. [Instituto de Radioprotecao e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil)]. E-mail: claudia@ird.gov.br; moura@ird.gov.br; karla@ird.gov.br

2007-07-01

With a focus on continuous improvement, since 2002, a special internal procedure for following and checking the performance of our individual monitoring services has been implemented. A fictitious installation, named 'Fantasma' has been created, initially, with 4 film badges and 7 thermoluminescent dosimetric ring users. Since 2005, this quality control program includes also the albedo neutron individual monitoring service. Monthly, the 'Fantasma' test monitors are irradiated by traceable Cs-137 and Am-Be sources. The calibration quantities are: the photon dose equivalent (H{sub x}) for the photographic individual monitor, the maximum dose equivalent (MADE) for the albedo neutron individual monitor and the personal dose equivalent at 0.07 mm depth (H{sub p}(0.07)) for ring monitor. Up to now, all results show compliance with the specific trumpet curves acceptance limits. Once, a small sub-evaluation tendency has been noted and this information was used to improve the film system. For the photographic film system, the evaluated value to reference dose ratios range from 0.71 to 1.12, with a mean value of 0.91 {+-} 0.12. For the ring system, the ratio ranges from 0.69 to 1.40, with a mean value of 1.02 {+-} 0.07. For the neutron system, which presents intrinsic larger uncertainties, the ratio ranged from 0.67 to 1.88, with mean value of 1.16 {+-} 0.27. (author)

Cumulative high doses of inhaled formoterol have less systemic effects in asthmatic children 6-11 years-old than cumulative high doses of inhaled terbutaline.

Science.gov (United States)

Kaae, Rikke; Agertoft, Lone; Pedersen, Sören; Nordvall, S Lennart; Pedroletti, Christophe; Bengtsson, Thomas; Johannes-Hellberg, Ingegerd; Rosenborg, Johan

2004-10-01

To evaluate high dose tolerability and relative systemic dose potency between inhaled clinically equipotent dose increments of formoterol and terbutaline in children. Twenty boys and girls (6-11 years-old) with asthma and normal ECGs were studied. Ten doses of formoterol (Oxis) 4.5 microg (F4.5) or terbutaline (Bricanyl) 500 microg (T500) were inhaled cumulatively via a dry powder inhaler (Turbuhaler) over 1 h (three patients) or 2.5 h (17 patients) and compared to a day of no treatment, in a randomised, double-blind (active treatments only), crossover trial. Blood pressure (BP), ECG, plasma potassium, glucose, lactate, and adverse events were monitored up to 10 h to assess tolerability and relative systemic dose potency. Formoterol and terbutaline had significant beta2-adrenergic effects on most outcomes. Apart from the effect on systolic BP, QRS duration and PR interval, the systemic effects were significantly more pronounced with terbutaline than with formoterol. Thus, mean minimum plasma potassium, was suppressed from 3.56 (95% confidence interval, CI: 3.48-3.65) mmol l(-1) on the day of no treatment to 2.98 (CI: 2.90-3.08) after 10 x F4.5 and 2.70 (CI: 2.61-2.78) mmol l(-1) after 10 x T500, and maximum Q-Tc (heart rate corrected Q-T interval [Bazett's formula]) was prolonged from 429 (CI: 422-435) ms on the day of no treatment, to 455 (CI: 448-462) ms after 10 x F4.5 and 470 (CI: 463-476) ms after 10 x T500. Estimates of relative dose potency indicated that F4.5 microg had the same systemic activity as the clinically less effective dose of 250 microg terbutaline. The duration of systemic effects differed marginally between treatments. Spontaneously reported adverse events (most frequently tremor) were fewer with formoterol (78% of the children) than with terbutaline (95%). A serious adverse event occurred after inhalation of 45 microg formoterol over the 1 h dosing time, that prompted the extension of dosing time to 2.5 h. Multiple inhalations over 2.5 h of

Arduino Based Infant Monitoring System

Science.gov (United States)

Farhanah Mohamad Ishak, Daing Noor; Jamil, Muhammad Mahadi Abdul; Ambar, Radzi

2017-08-01

This paper proposes a system for monitoring infant in an incubator and records the relevant data into a computer. The data recorded by the system can be further referred by the neonatal intensive care unit (NICU) personnel for diagnostic or research purposes. The study focuses on designing the monitoring system that consists of an incubator equipped with humidity sensor to measure the humidity level, and a pulse sensor that can be attached on an infant placed inside the incubator to monitor infant’s heart pulse. The measurement results which are the pulse rate and humidity level are sent to the PC via Arduino microcontroller. The advantage of this system will be that in the future, it may also enable doctors to closely monitor the infant condition through local area network and internet. This work is aimed as an example of an application that contributes towards remote tele-health monitoring system.

Fast skin dose estimation system for interventional radiology.

Science.gov (United States)

Takata, Takeshi; Kotoku, Jun'ichi; Maejima, Hideyuki; Kumagai, Shinobu; Arai, Norikazu; Kobayashi, Takenori; Shiraishi, Kenshiro; Yamamoto, Masayoshi; Kondo, Hiroshi; Furui, Shigeru

2018-03-01

To minimise the radiation dermatitis related to interventional radiology (IR), rapid and accurate dose estimation has been sought for all procedures. We propose a technique for estimating the patient skin dose rapidly and accurately using Monte Carlo (MC) simulation with a graphical processing unit (GPU, GTX 1080; Nvidia Corp.). The skin dose distribution is simulated based on an individual patient's computed tomography (CT) dataset for fluoroscopic conditions after the CT dataset has been segmented into air, water and bone based on pixel values. The skin is assumed to be one layer at the outer surface of the body. Fluoroscopic conditions are obtained from a log file of a fluoroscopic examination. Estimating the absorbed skin dose distribution requires calibration of the dose simulated by our system. For this purpose, a linear function was used to approximate the relation between the simulated dose and the measured dose using radiophotoluminescence (RPL) glass dosimeters in a water-equivalent phantom. Differences of maximum skin dose between our system and the Particle and Heavy Ion Transport code System (PHITS) were as high as 6.1%. The relative statistical error (2 σ) for the simulated dose obtained using our system was ≤3.5%. Using a GPU, the simulation on the chest CT dataset aiming at the heart was within 3.49 s on average: the GPU is 122 times faster than a CPU (Core i7-7700K; Intel Corp.). Our system (using the GPU, the log file, and the CT dataset) estimated the skin dose more rapidly and more accurately than conventional methods.

The system for automatic dose rate measurements by mobile groups in field

International Nuclear Information System (INIS)

Drabova, D.; Filgas, R.; Cespirova, I.; Ejemova, M.

1998-01-01

The comparison of characteristics between a pressurized ionization chamber, plastic scintillator and proportional counter is given. Based on requirements and comparison of properties of various probes, the system for automatic dose rate measurement and integration of geographic co-ordinates in field was designed and tested.The system consists of proportional counter. This is so-called intelligent probe can be easily connected to a personal computer. The probe measures in the energy range 30 keV - 1.3 MeV with reasonable energy and angular response, it can measure the dose rate in the range 50 nSv/h - 1 Sv/h with the typical efficiency 9.5 imp/s/μSv/h. The probe is fixed in the holder placed on the front mask of a car. For the simultaneous determination of geographical co-ordinates the personal GPS navigator Garmin 95 is used. Both devices are controlled by a notebook via two serial ports. The second serial port that is not quite common in notebook can be easily realised by a PCMCIA card. The notebook is used in the field by a mobile group can be transmitted to the assessment centre by the cellular GSM phone. The system Nokia 2110 connected to notebook by PCMCIA card is used. The whole system is powered up from the car battery. The system is controlled by specially developed software. The software was developed in the FoxPro 2.5 environment and works under MS-DOS 6.22. It has no problems to work in Windows 95 DOS window. The results of dose rate measurements obtained during route monitoring are stored in files. They can be displayed on a graphic screen, presenting the geographical distribution of the dose rate values colour coded on a map and the time sequence of the measured data. (authors)