GENII (Generation II): The Hanford Environmental Radiation Dosimetry Software System: Volume 3, Code maintenance manual: Hanford Environmental Dosimetry Upgrade Project

Energy Technology Data Exchange (ETDEWEB)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-09-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). This coupled system of computer codes is intended for analysis of environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil, on through the calculation of radiation doses to individuals or populations. GENII is described in three volumes of documentation. This volume is a Code Maintenance Manual for the serious user, including code logic diagrams, global dictionary, worksheets to assist with hand calculations, and listings of the code and its associated data libraries. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. 7 figs., 5 tabs.

Hanford Internal Dosimetry Project manual. Revision 1

International Nuclear Information System (INIS)

Carbaugh, E.H.; Bihl, D.E.; MacLellan, J.A.; Long, M.P.

1994-07-01

This document describes the Hanford Internal Dosimetry Project, as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy and its Hanford contractors. Project services include administrating the bioassay monitoring program, evaluating and documenting assessment of potential intakes and internal dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. Specific chapters deal with the following subjects: practices of the project, including interpretation of applicable DOE Orders, regulations, and guidance into criteria for assessment, documentation, and reporting of doses; assessment of internal dose, including summary explanations of when and how assessments are performed; recording and reporting practices for internal dose; selection of workers for bioassay monitoring and establishment of type and frequency of bioassay measurements; capability and scheduling of bioassay monitoring services; recommended dosimetry response to potential internal exposure incidents; quality control and quality assurance provisions of the program

Hanford Internal Dosimetry Project manual. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Carbaugh, E.H.; Bihl, D.E.; MacLellan, J.A.; Long, M.P.

1994-07-01

This document describes the Hanford Internal Dosimetry Project, as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy and its Hanford contractors. Project services include administrating the bioassay monitoring program, evaluating and documenting assessment of potential intakes and internal dose, ensuring that analytical laboratories conform to requirements, selecting and applying appropriate models and procedures for evaluating radionuclide deposition and the resulting dose, and technically guiding and supporting Hanford contractors in matters regarding internal dosimetry. Specific chapters deal with the following subjects: practices of the project, including interpretation of applicable DOE Orders, regulations, and guidance into criteria for assessment, documentation, and reporting of doses; assessment of internal dose, including summary explanations of when and how assessments are performed; recording and reporting practices for internal dose; selection of workers for bioassay monitoring and establishment of type and frequency of bioassay measurements; capability and scheduling of bioassay monitoring services; recommended dosimetry response to potential internal exposure incidents; quality control and quality assurance provisions of the program.

Quality assurance manual for the Department of Energy laboratory accreditation program for personnel dosimetry systems

International Nuclear Information System (INIS)

1987-02-01

The overall purpose of this document is to establish a uniform approach to quality assurance. This will ensure that uniform, high-quality personnel dosimetry practices are followed by the participating testing laboratories. The document presents guidelines for calibrating and maintaining measurement and test equipment (M and TE), calibrating radiation fields, and subsequently irradiating and handling personnel dosimeters in laboratories involved in the DOE dosimetry systems testing program. Radiation energies for which the test procedures apply are photons with approximately 15 keV to 2 MeV, beta particles above 0.3 MeV, neutrons with approximately 1 keV to 2 MeV. 12 refs., 4 tabs

WIPP radiation dosimetry program

International Nuclear Information System (INIS)

Wu, C.F.

1991-01-01

Radiation dosimetry is the process by which various measurement results and procedures are applied to quantify the radiation exposure of an individual. Accurate and precise determination of radiation dose is a key factor to the success of a radiation protection program. The Waste Isolation Pilot Plant (WIPP), a Department of Energy (DOE) facility designed for permanent repository of transuranic wastes in a 2000-foot-thick salt bed 2150 feet underground, has established a dosimetry program developed to meet the requirements of DOE Order 5480.11, ''Radiation Protection for Occupational Workers''; ANSI/ASME NQA-1, ''Quality Assurance Program Requirements for Nuclear Facilities''; DOE Order 5484.1, ''Environmental Protection, Safety, and Health Protection Information Reporting Requirements''; and other applicable regulations

Student Perceptions of an Online Medical Dosimetry Program

International Nuclear Information System (INIS)

Lenards, Nishele

2011-01-01

The University of Wisconsin-La Crosse offers the first online medical dosimetry program in the nation. There is no data to research a program of this type. This research consisted of the evaluation of other distance education programs including health profession programs in addition to face-to-face medical dosimetry programs. There was a need to collect and analyze student perceptions of online learning in medical dosimetry. This research provided a guide for future implementation by other programs as well as validated the University of Wisconsin-La Crosse program. Methodology used consisted of an electronic survey sent to all previous and currently enrolled students in the University of Wisconsin-La Crosse medical dosimetry program. The survey was both quantitative and qualitative in demonstrating attitudinal perceptions of students in the program. Quantitative data was collected and analyzed using a 5-point Likert scale. Qualitative data was gathered based on the open-ended responses and the identifying themes from the responses. The results demonstrated an overall satisfaction with this program, the instructor, and the online courses. Students felt a sense of belonging to the courses and the program. Considering that a majority of the students had never taken an online course previously, the students felt there were no technology issues. Future research should include an evaluation of board exam statistics for students enrolled in the online and face-to-face medical dosimetry programs.

Hanford External Dosimetry Program

International Nuclear Information System (INIS)

Fix, J.J.

1990-10-01

This document describes the Hanford External Dosimetry Program as it is administered by Pacific Northwest Laboratory (PNL) in support of the US Department of Energy (DOE) and its Hanford contractors. Program services include administrating the Hanford personnel dosimeter processing program and ensuring that the related dosimeter data accurately reflect occupational dose received by Hanford personnel or visitors. Specific chapters of this report deal with the following subjects: personnel dosimetry organizations at Hanford and the associated DOE and contractor exposure guidelines; types, characteristics, and procurement of personnel dosimeters used at Hanford; personnel dosimeter identification, acceptance testing, accountability, and exchange; dosimeter processing and data recording practices; standard sources, calibration factors, and calibration processes (including algorithms) used for calibrating Hanford personnel dosimeters; system operating parameters required for assurance of dosimeter processing quality control; special dose evaluation methods applied for individuals under abnormal circumstances (i.e., lost results, etc.); and methods for evaluating personnel doses from nuclear accidents. 1 ref., 14 figs., 5 tabs

Survey of international personnel radiation dosimetry programs

International Nuclear Information System (INIS)

Swaja, R.E.

1985-04-01

In September of 1983, a mail survey was conducted to determine the status of external personnel gamma and neutron radiation dosimetry programs at international agencies. A total of 130 agencies participated in this study including military, regulatory, university, hospital, laboratory, and utility facilities. Information concerning basic dosimeter types, calibration sources, calibration phantoms, corrections to dosimeter responses, evaluating agencies, dose equivalent reporting conventions, ranges of typical or expected dose equivalents, and degree of satisfaction with existing systems was obtained for the gamma and neutron personnel monitoring programs at responding agencies. Results of this survey indicate that to provide the best possible occupational radiation monitoring programs and to improve dosimetry accuracy in performance studies, facility dosimetrists, regulatory and standards agencies, and research laboratories must act within their areas of responsibility to become familiar with their radiation monitoring systems, establish common reporting guidelines and performance standards, and provide opportunities for dosimetry testing and evaluation. 14 references, 10 tables

The US Department of Energy Personnel Dosimetry Evaluation and Upgrade Program

International Nuclear Information System (INIS)

Faust, L.G.; Stroud, C.M.; Swinth, K.L.; Vallario, E.J.

1987-11-01

The US Department of Energy (DOE) Personnel Dosimetry Evaluation and Upgrade Program is designed to identify and evaluate dosimetry deficiencies and to conduct innovative research and development programs that will improve overall capabilities, thus ensuring that DOE can comply with applicable standards and regulations for dose measurement. To achieve these goals, two programs were initiated to evaluate and upgrade beta measurement and neutron dosimetry. 3 refs

Role of secondary standard dosimetry laboratory in radiation protection program

International Nuclear Information System (INIS)

Rahman, Sohaila; Ali, Noriah Mohd.

2008-01-01

Full text: The radiation dosimetry program is an important element of operational radiation protection. Dosimetry data enable workers and radiation protection professionals to evaluate and control work practices to eliminate unnecessary exposure to ionizing radiation. The usefulness of the data produced however depends on its quality and traceability. The emphasis of the global dosimetry program is focused through the IAEA/WHO network of secondary standard dosimetry laboratories (SSDLs), which aims for the determination of SI quantities through proper traceable calibration of radiation protection equipment. The responsibility of SSDL-NUCLEAR MALAYSIA to guarantee a reliable dosimetry service, which is traceable to international standards, is elucidated. It acts as the basis for harmonized occupational radiation monitoring in Malaysia.

Trends in light water reactor dosimetry programs

International Nuclear Information System (INIS)

Rahn, F.J.; Serpan, C.Z.; Fabry, A.; McElroy, W.N.; Grundl, J.A.; Debrue, J.

1977-01-01

Dosimetry programs and techniques play an essential role in the continued assurance of the safety and reliability of components of light water reactors. Primary concern focuses on the neutron irradiation embrittlement of reactor pressure vessels and methods by which the integrity of a pressure vessel can be predicted and monitored throughout its service life. Research in these areas requires a closely coordinated program which integrates the elements of the calculational and material sciences, the development of advanced dosimetric techniques and the use of benchmarks and validation of these methods. The paper reviews the status of the various international efforts in the dosimetry area

Guidelines for the preparation of a quality manual for external audit groups on dosimetry in radiotherapy

International Nuclear Information System (INIS)

Izewska, Joanna; Arib, M.; Saravi, M.

2002-01-01

This document has been prepared within the framework of a Co-ordinated Research Programme (CRP) on Development of Quality Assurance Programme for Radiation Therapy Dosimetry in Developing Countries, during two Meetings at the IAEA Headquarters in Vienna (11-14 November 1996 and 6-10 October 1997). It is based on the recommendations of ISO 9000 series and ISO/IEC guide No. 25. The document can be used as a guide on how to prepare a quality manual for national External Audit Groups (EAG), i.e., a nationally recognised group in charge of operating external quality audits for radiotherapy dosimetry. The EAG of a given country includes the SSDL, a Measuring Group and a Medical Physics Group, who work in close co-operation at all steps of the audit. The content herein should be considered as a suggestion and additions or deletions can be made in accordance with the specific conditions in each country. It is preferable that the manual itself be as concise as possible, limiting it to the core scope. Detailed working sheets describing the procedures should be included in Appendices together with data sheets, questionnaires and reporting forms. The quality manual of each country should be carefully reviewed by all members of the EAG and, as far as possible, should be approved by relevant professional bodies and supported by health authorities. It has long been recognised that accurate knowledge of the dose in radiotherapy is vital to ensure safe and effective radiation treatments. To achieve this goal, comprehensive quality assurance programmes should be established to cover all steps from dose prescription to dose delivery. These programmes should include internal checks performed by the radiotherapy centres and external audits made by independent external bodies. It is estimated that not more than 50% of radiotherapy facilities world-wide have participated in some level of dose quality audit by an independent expert. Genuine concern exists that some, or even many

Design of an internal dosimetry program

International Nuclear Information System (INIS)

Wu, C.F.; Goff, T.E.

2004-01-01

Measurement of radiation dose is an essential element of radiation protection programs at nuclear facilities. To protect workers and demonstrate compliance with regulatory requirements, dosimetry programs must be established based on sound technical basis. Historically, external exposure was controlled by occupational dose limits. Internal exposure to radionuclides was limited by maximum permissible body burden and maximum permissible concentration. With the issuance of ICRP 26, ICRP 30, DOE Order 5480.11, DOE/EH-0256T, and the new 10 CFR 20, it has become a requirement that internal dose be assessed and the sum of internal and external doses be maintained below regulatory limits. Nuclear facilities are required to have internal dose evaluation programs adequate to demonstrate compliance with radiation protection standards (RPSs). The Waste Isolation Pilot Plant is a DOE facility designed to demonstrate safe disposal of transuranic (TRU) wastes in an ancient salt bed 2,150 feet underground. Internal dose measurement is required to support waste handling activities. This paper describes the technical basis for the WIPP Internal Dosimetry Program. (author)

Fire Protection Program Manual

Energy Technology Data Exchange (ETDEWEB)

Sharry, J A

2012-05-18

This manual documents the Lawrence Livermore National Laboratory (LLNL) Fire Protection Program. Department of Energy (DOE) Orders 420.1B, Facility Safety, requires LLNL to have a comprehensive and effective fire protection program that protects LLNL personnel and property, the public and the environment. The manual provides LLNL and its facilities with general information and guidance for meeting DOE 420.1B requirements. The recommended readers for this manual are: fire protection officers, fire protection engineers, fire fighters, facility managers, directorage assurance managers, facility coordinators, and ES and H team members.

The U.S. Department of Energy Laboratory Accreditation Program for testing the performance of extremity dosimetry systems: a summary of the program status

International Nuclear Information System (INIS)

Cummings, F.M.; Carlson, R.D.; Gesell, T.F.; Loesch, R.M.

1992-01-01

In 1986, The U.S. Department of Energy (DOE) implemented a program to test the performance of its personnel whole-body dosimetry systems. This program was the DOE Laboratory Accreditation Program (DOELAP). The program parallels the performance testing program specified in the American National Standard for Dosimetry - Personnel Dosimetry Performance -Criteria for Testing (ANSI N13.11-1983), but also addresses the additional dosimetry needs of DOE facilities. As an extension of the whole-body performance testing program, the DOE is now developing a program to test the performance of personnel extremity dosimetry systems. The draft DOE standard for testing extremity dosimetry systems is much less complex than the whole-body dosimetry standard and reflects the limitations imposed on extremity dosimetry by dosimeter design and irradiation geometry. A pilot performance test session has been conducted to evaluate the proposed performance-testing standard. (author)

State Energy Program Operations Manual

Energy Technology Data Exchange (ETDEWEB)

Office of Building Technology, State and Community Programs

1999-03-17

The State Energy Program Operations Manual is a reference tool for the states and the program officials at the U.S. Department of Energy's Office of Building Technology, State and Community Programs and Regional Support Offices as well as State Energy Offices. The Manual contains information needed to apply for and administer the State Energy Program, including program history, application rules and requirements, and program administration and monitoring requirements.

Personnel radiation dosimetry symposium: program and abstracts

Energy Technology Data Exchange (ETDEWEB)

1984-10-01

The purpose was to provide applied and research dosimetrists with sufficient information to evaluate the status and direction of their programs relative to the latest guidelines and techniques. A technical program was presented concerning experience, requirements, and advances in gamma, beta, and neutron personnel dosimetry.

Personnel radiation dosimetry symposium: program and abstracts

International Nuclear Information System (INIS)

1984-10-01

The purpose was to provide applied and research dosimetrists with sufficient information to evaluate the status and direction of their programs relative to the latest guidelines and techniques. A technical program was presented concerning experience, requirements, and advances in gamma, beta, and neutron personnel dosimetry

[Automatic Extraction and Analysis of Dosimetry Data in Radiotherapy Plans].

Science.gov (United States)

Song, Wei; Zhao, Di; Lu, Hong; Zhang, Biyun; Ma, Jun; Yu, Dahai

To improve the efficiency and accuracy of extraction and analysis of dosimetry data in radiotherapy plans for a batch of patients. With the interface function provided in Matlab platform, a program was written to extract the dosimetry data exported from treatment planning system in DICOM RT format and exported the dose-volume data to an Excel file with the SPSS compatible format. This method was compared with manual operation for 14 gastric carcinoma patients to validate the efficiency and accuracy. The output Excel data were compatible with SPSS in format, the dosimetry data error for PTV dose interval of 90%-98%, PTV dose interval of 99%-106% and all OARs were -3.48E-5 ± 3.01E-5, -1.11E-3 ± 7.68E-4, -7.85E-5 ± 9.91E-5 respectively. Compared with manual operation, the time required was reduced from 5.3 h to 0.19 h and input error was reduced from 0.002 to 0. The automatic extraction of dosimetry data in DICOM RT format for batch patients, the SPSS compatible data exportation, quick analysis were achieved in this paper. The efficiency of clinical researches based on dosimetry data analysis of large number of patients will be improved with this methods.

Dosimetry program for characterization of the FMIT facility

International Nuclear Information System (INIS)

Gold, R.; McElroy, W.N.; Fuller, J.L.; Sheen, E.M.; Dierckx, R.

1979-01-01

The environmental characterization program for the Fusion Materials Irradiaton Test (FMIT) facility is presented. Requirements for the development and testing of Magnetic Fusion Energy (MFE) materials together with the complexity of the FMIT (d,Li) generated radiation field warrant a multifaceted dosimetric approach. Specific passive, active and calculational dosimetry efforts comprising this multifaceted approach are described. Special emphasis is given to those dosimetry capabilities uniquely required to characterize FMIT

Manual of food irradiation dosimetry

International Nuclear Information System (INIS)

1977-01-01

Following items are discussed: Fundamentals of dosimetry; description of irradiators; dose distribution in the product and commissioning the process; plant operation and process control; detailed instructions on using various dose-meter systems; references; glossary of some basic terms and concepts

A Computerized QC Analysis of TLD Glow Curves for Personal Dosimetry Measurements Using Tag QC Program

International Nuclear Information System (INIS)

Primo, S.; Datz, H.; Dar, A.

2014-01-01

The External Dosimetry Lab (EDL) at the Radiation Safety Division at Soreq Nuclear Research Center (SNRC) is ISO 17025 certified and provides its services to approximately 13,000 users throughout the country from various sectors such as medical, industrial and academic. About 95% of the users are monitored monthly for X-rays, radiation using Thermoluminescence Dosimeter (TLD) cards that contain three LiF:Mg,Ti elements and the other users, who work also with thermal neutrons, use TLD cards that contain four LiF:Mg,Ti elements. All TLD cards are measured with the Thermo 8800pc reader. Suspicious TLD glow curve (GC) can cause wrong dose estimation so the EDL makes great efforts to ensure that each GC undergoes a careful QC procedure. The current QC procedure is performed manually and through a few steps using different softwares and databases in a long and complicated procedure: EDL staff needs to export all the results/GCs to be checked to an Excel file, followed by finding the suspicious GCs, which is done in a different program (WinREMS), According to the GC shapes (Figure 1 illustrates suitable and suspicious GC shapes) and the ratio between the elements result values, the inspecting technician corrects the data. The motivation for developing the new program is the complicated and time consuming process of our the manual procedure to the large amount of TLDs each month (13,000), similarly to other Dosimetry services that use computerized QC GC analysis. it is important to note that only ~25% of the results are above the EDL recorded level (0.10 mSv) and need to be inspected. Thus, the purpose of this paper is to describe a new program, TagQC, which allows a computerized QC GC analysis that identifies automatically, swiftly, and accurately suspicious TLD GC

System of data management in 'Dosis' personal dosimetry

International Nuclear Information System (INIS)

Manzano de Armas, Jose; Diaz Bernal, Efren; Capote Ferrera, Eduardo; Molina Perez, Daniel; Lopez Bejerano, Gladys

2001-01-01

The storage and control of the data of a service of personal dosimetry is a task that requires specify care in data handling and manipulation. This activity becomes more annoying of making manually when the volume of users of the service is significant. The External Dosimetric Laboratory of the Center for Radiation Protection and Hygiene has developed a system of administration of data that allows the storage, control and analysis of the data generated by the Service of Personal Dosimetry in an efficient and reliable way. This paper describes the characteristics of the System for Administration of Data in Personal Dosimetry 'Dosis', as well as their design and programming. The importance of this System for the laboratory and the advantages of their application are described. The characteristics of the different modules are also described. (author)

Technical basis for the internal dosimetry program at the Y-12 Plant

International Nuclear Information System (INIS)

Ashley, J.C.; Barber, J.M.; Snapp, L.M.; Turner, J.E.

1992-01-01

Since the beginning of plant operations. almost all work with radioactive materials has involved isotopes associated with uranium, enriched or depleted in U 235 . While limited quantities of isotopes of elements other than uranium are present, workplace monitoring and precess knowledge have established that internal exposure from these other isotopes is insignificant in comparison with uranium. While the changing plant mission may necessitate the consideration of internal exposure from other isotopes at some point in time, only enriched and depleted uranium will be considered in this basis document. The portions of the internal dosimetry technical basis which may be unique to the Y-12 Plant is considered in this manual. This manual presents the technical basis of the routine in vivo and in vitro bioassay programs including choice of frequency, participant selection criteria, and action level guidelines. Protocols for special bioassay will be presented in the chapters which described the basis for intake, uptake, and dam assessment. A discussion of the factors which led to the need to develop a special biokinetic model for uranium at the Y-12 Plant, as well as a description of the model's basic parameters, are included in this document

US Department of Energy Laboratory Accredition Program (DOELAP) for personnel dosimetry systems

Energy Technology Data Exchange (ETDEWEB)

Cummings, F.M.; Carlson, R.D.; Loesch, R.M.

1993-12-31

Accreditation of personnel dosimetry systems is required for laboratories that conduct personnel dosimetry for the U.S. Department of Energy (DOE). Accreditation is a two-step process which requires the participant to pass a proficiency test and an onsite assessment. The DOE Laboratory Accreditation Program (DOELAP) is a measurement quality assurance program for DOE laboratories. Currently, the DOELAP addresses only dosimetry systems used to assess the whole body dose to personnel. A pilot extremity DOELAP has been completed and routine testing is expected to begin in January 1994. It is expected that participation in the extremity program will be a regulatory requirement by January 1996.

International beta-dosimetry symposium. Program and abstracts

International Nuclear Information System (INIS)

1983-02-01

Abstracts of the presentations at the symposium are contained in this volume. Problems associated with beta dosimetry, beta detectors and dosemeters, and current development programs are described. Each abstract has been indexed separately for inclusion in the Energy Data Base

Program Management System manual

International Nuclear Information System (INIS)

1986-01-01

The Program Management System (PMS), as detailed in this manual, consists of all the plans, policies, procedure, systems, and processes that, taken together, serve as a mechanism for managing the various subprograms and program elements in a cohesive, cost-effective manner. The PMS is consistent with the requirements of the Nuclear Waste Policy Act of 1982 and the ''Mission Plan for the Civilian Radioactive Waste Management Program'' (DOE/RW-0005). It is based on, but goes beyond, the Department of Energy (DOE) management policies and procedures applicable to all DOE programs by adapting these directives to the specific needs of the Civilian Radioactive Waste Management program. This PMS Manual describes the hierarchy of plans required to develop and maintain the cost, schedule, and technical baselines at the various organizational levels of the Civilian Radioactive Waste Management Program. It also establishes the management policies and procedures used in the implementation of the Program. These include requirements for internal reports, data, and other information; systems engineering management; regulatory compliance; safety; quality assurance; and institutional affairs. Although expanded versions of many of these plans, policies, and procedures are found in separate documents, they are an integral part of this manual. The PMS provides the basis for the effective management that is needed to ensure that the Civilian Radioactive Waste Management Program fulfills the mandate of the Nuclear Waste Policy Act of 1982. 5 figs., 2 tabs

Fourth conference on radiation protection and dosimetry: Proceedings, program, and abstracts

Energy Technology Data Exchange (ETDEWEB)

Casson, W.H.; Thein, C.M.; Bogard, J.S. [eds.

1994-10-01

This Conference is the fourth in a series of conferences organized by staff members of Oak Ridge National Laboratory in an effort to improve communication in the field of radiation protection and dosimetry. Scientists, regulators, managers, professionals, technologists, and vendors from the United States and countries around the world have taken advantage of this opportunity to meet with their contemporaries and peers in order to exchange information and ideas. The program includes over 100 papers in 9 sessions, plus an additional session for works in progress. Papers are presented in external dosimetry, internal dosimetry, radiation protection programs and assessments, developments in instrumentation and materials, environmental and medical applications, and on topics related to standards, accreditation, and calibration. Individual papers are indexed separately on EDB.

Radiological control technician: Training program management manual

International Nuclear Information System (INIS)

1992-10-01

This manual defines and describes the DOE Radiological Control Technician Core Training Program qualification and training process, material development requirements, standards and policies, and administration. The manual applies to Radiological Control Technician Training Programs at all DOE contractor sites

GENMOD - A program for internal dosimetry calculations

International Nuclear Information System (INIS)

Dunford, D.W.; Johnson, J.R.

1987-12-01

The computer code GENMOD was created to calculate the retention and excretion, and the integrated retention for selected radionuclides under a variety of exposure conditions. Since the creation of GENMOD new models have been developed and interfaced to GENMOD. This report describes the models now included in GENMOD, the dosimetry factors database, and gives a brief description of the GENMOD program

The program of international intercomparison of accident dosimetry

International Nuclear Information System (INIS)

2002-06-01

The French institute of radioprotection and nuclear safety (IRSN) has carried out in June 2002 an international intercomparison program for the testing of the physical and biological accident dosimetry techniques. The intercomparison is jointly organized by the IRSN and the OECD-NEA with the sustain of the European commission and the collaboration of the CEA centre of Valduc (France). About 30 countries have participated to this program. Each country has supplied its own dosimeters and biological samples which have been irradiated using the Silene reactor of CEA-Valduc or a 60 Co source. These experiments allow to test the new dosimetric techniques that have been developed since the previous intercomparison program (1993) and to confirm or improve the performances of older techniques. Aside from the intercomparison exercise, this report makes a status of the known radiological accidents and of the effects of high doses of ionizing radiations on human health (symptoms, therapeutics). It explains the phenomenology of criticality accidents, the prevention means, and the history of such accidents up to the Tokai-Mura one in 1999. Finally, the dosimetry of criticality is presented with its physical and biological techniques. (J.S.)

Internal Dosimetry for Nuclear Power Program

International Nuclear Information System (INIS)

Wo, Y.M.

2011-01-01

Internal dosimetry which refers to dosage estimation from internal part of an individual body is an important and compulsory component in order to ensure the safety of the personnel involved in operational of a Nuclear Power Program. Radionuclides particle may deposit in the human being through several pathways and release wave and/or particle radiation to irradiate that person and give dose to body until it been excreted or completely decayed from the body. Type of radionuclides of concerning, monitoring program, equipment's and technique used to measure the concentration level of such radionuclides and dose calculation will be discussed in this article along with the role and capability of Malaysian Nuclear Agency. (author)

Dosimetry and Calibration Section

International Nuclear Information System (INIS)

Otto, T.

1999-01-01

The Dosimetry and Calibration Section fulfils two tasks within CERN's Radiation Protection Group: the Individual Dosimetry Service monitors more than 5000 persons potentially exposed to ionizing radiation on the CERN sites, and the Calibration Laboratory verifies throughout the year, at regular intervals, over 1000 instruments, monitors, and electronic dosimeters used by RP Group. The establishment of a Quality Assurance System for the Individual Dosimetry Service, a requirement of the new Swiss Ordinance for personal dosimetry, put a considerable workload on the section. Together with an external consultant it was decided to identify and then describe the different 'processes' of the routine work performed in the dosimetry service. The resulting Quality Manual was submitted to the Federal Office for Public Health in Bern in autumn. The CERN Individual Dosimetry Service will eventually be officially endorsed after a successful technical test in March 1999. On the technical side, the introduction of an automatic development machine for gamma films was very successful. It processes the dosimetric films without an operator being present, and its built-in regeneration mechanism keeps the concentration of the processing chemicals at a constant level

The IROC Houston Quality Assurance Program: Potential benefits of 3D dosimetry

International Nuclear Information System (INIS)

Followill, D S; Molineu, H A; Lafratta, R; Ibbott, G S

2017-01-01

The IROC Houston QA Center has provided QA core support for NCI clinical trials by ensuring that radiation doses delivered to trial patients are accurate and comparable between participating institutions. Within its QA program, IROC Houston uses anthropomorphic QA phantoms to credential sites. It is these phantoms that have the highest potential to benefit from the use of 3D dosimeters. Credentialing is performed to verify that institutions that are using advanced technologies to deliver complex treatment plans that conform to targets. This makes it increasingly difficult to assure the intended calculated dose is being delivered correctly using current techniques that are 2D-based. A 3D dosimeter such as PRESAGE® is able to provide a complete 3D measured dosimetry dataset with one treatment plan delivery. In our preliminary studies, the 3D dosimeters in our H and N and spine phantoms were found to be appropriate for remote dosimetry for relative dose measurements. To implement 3D dosimetry in IROC Houston’s phantoms, the benefit of this significant change to its current infrastructure would have to be assessed and further work would be needed before bringing 3D dosimeters into the phantom dosimetry program. (paper)

Patient dosimetry quality assurance program with a commerical diode system

International Nuclear Information System (INIS)

Lee, P.C.; Sawicka, J.M.; Glasgow, G.P.

1994-01-01

The purpose was to evaluate a commercial silicone diode dosimeter for a patient dosimetry quality assurance program. The diode dosimeter was calibrated against an ion chamber, and percentage depth dose, linearity, anisotrophy, virtual source position, and field size factor studies were performed. Correction factors for lack of full scatter medium in the diode entrance and exit dose measurements were acquired. Dosimetry equations were proposed for calculation of dose delivered at isocenter. Diode dose accuracy and reproducibility were tested on phantom and on four patients. A patient dosimetry quality assurance program based on diode-measured dose was instituted and patient dose data were collected. Diode measured percentage depth dose and field factors agreed to within 3% with those measured with an ion chamber. The diode exhibited less than 1.7% angular dose anisotrophy and less than 0.5% nonlinearity up to 4 Gy. Diode dose measurements in phantom showed that the calculated doses differed from the prescribed dose by less than 1.%; the diode exhibited a daily dose reproducibility of better than 0.2%. On four selected patients, the measured dose reproducibility was 1.5%; the average calculated doses were all within ± 7% of the prescribed doses. For 33 of 40 patients treated with a 6 MW beam, measured doses were within ± 7% of the prescribed doses. For 11 out of 12 patients, a second repeat measurements yielded doses within ± 7% of the prescribed doses. The proposed diode-based patient dosimetry quality assurance program with dose tolerance at ± 7% is simple and feasible. It is capable of detecting certain serious treatment errors such as incorrect daily dose greater than 7%, incorrect wedge use, incorrect photon energy and patient setup errors involving some incorrect source-to-surface-distance vs. source-to-axis-distance treatments. 13 refs., 5 figs., 5 tabs

User's guide for survey-meter- and film-badge-dosimetry data bases

International Nuclear Information System (INIS)

Phillips, W.G.; Sherman, S.; Young, R.

1981-05-01

This manual describes the data storage and retrieval system designed by Environmental Monitoring Systems Laboratory Las Vegas (EMSL-LV) for radiation exposure data recorded in offsite areas during and after nuclear weapons tests conducted at the Nevada Test Site in the 1950's and early 1960's. Referred to hereinafter as the EMSL-LV system, this system contains two distinct subsets of offsite radiological measurements collected during early nuclear atmospheric tests at the Nevada Test Site. The purpose of the manual is to present the methods for using the EMSL-LV system to examine all or any portion of either data subset. The two distinct subsets which comprise the EMSL-LV system are survey meter data and film badge dosimetry data. The survey meter data consist of readings obtained from portable radiation monitoring instruments used around the Nevada Test Site during the 1950's and early 1960's to measure radiation exposure rates resulting from the nuclear testing program. The dosimetry data consist of measurements of integrated radiation exposure made with film badge type dosimeters in areas surrounding the Nevada Test Site

TAP 1, Training Program Manual

International Nuclear Information System (INIS)

1991-01-01

Training programs at DOE nuclear facilities should provide well-trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor nuclear facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically determined job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two companion manuals provide additional information to assist contractors in their efforts to accredit training programs

The Martin Marietta Energy Systems personnel neutron dosimetry program

International Nuclear Information System (INIS)

McMahan, K.L.

1991-01-01

Martin Marietta Energy Systems, Inc. (Energy Systems), manages five sites for the US Department of Energy. Personnel dosimetry for four of the five sites is coordinated through a Centralized External Dosimetry System (CEDS). These four sites are the Oak Ridge National Laboratory (ORNL), the Oak Ridge Y-12 Plant (Y-12), the Oak Ridge K-25 Site (K-25), and the Paducah Gaseous Diffusion Plant (PGDP). The fifth Energy Systems site, Portsmouth Gaseous Diffusion Plant, has an independent personnel dosimetry program. The current CEDS personnel neutron dosimeter was first issued in January 1989, after an evaluation and characterization of the dosimeters' response in the workplaces was performed. For the workplace characterization, Energy Systems contracted with Pacific Northwest Laboratory (PNL) to perform neutron measurements at selected locations at ORNL and Y-12. K-25 and PGDP were not included because their neutron radiation fields were similar to others already planned for characterization at ORNL and Y-12. Since the initial characterization, PNL has returned to Oak Ridge twice to perform follow up measurements, and another visit is planned in the near future

Calculations in cytogenetic dosimetry by means of the dosgen program

International Nuclear Information System (INIS)

Garcia Lima, O.; Zerquera, J.T.

1996-01-01

The DOSGEN program sums up the different calculations routing that are more often used in cytogenetic dosimetry. It can be implemented in a compatible IBM PC by cytogenetic experts having a basic knowledge of computing. The programs has been successfully applied using experimental data and its advantages have been acknowledge by Latin American and Asian Laboratories dealing with this medical branch. The program is written in Pascal Language and requires 42 K bytes

Automation of radiation dosimetry using PTW dosemeter and LabVIEWTM

International Nuclear Information System (INIS)

Weiss, C.; Al-Frouh, K.; Anjak, O.

2011-01-01

Automation of UNIDOS 'Dosemeter' using personal computer (PC) is discussed in this paper. In order to save time and eliminate human operation errors during the radiation dosimetry, suitable software, using LabVIEW TM graphical programming language, was written to automate and facilitate the processes of measurements, analysis and data storage. The software calculates the calibration factor of the ionization chamber in terms of air kerma or absorbed dose to water according to IAEA dosimetry protocols. It also has the ability to print a calibration certificate. The obtained results using this software are found to be more reliable and flexible than those obtained by manual methods previously employed. Using LabVIEW TM as a development tool is extremely convenient to make things easier when software modifications and improvements are needed.

Rural Gas Program manual

Energy Technology Data Exchange (ETDEWEB)

1987-11-01

The intent and purpose of this manual is to describe the various guideliness and administrative procedures associated with the Alberta Rural Gas Program and to consolidate and expand upon the legislation under which the Program has been developed. It is intended primarily for the use and information of rural gas distributors, their agents, and other private or government parties having an interest in the Rural Gas Program. Information is presented on: rural gas franchises, technical applications, contracts and tenders, determination of system capital costs for grant support, grants, Gas Alberta brokerage arrangements, insurance coverage, utility rights-of-way, and lien notes.

Report of the Intercomparison program by thermoluminescent dosimetry for Secondary Standard Dosimetry Laboratories

International Nuclear Information System (INIS)

Papadopulos, Susana

2000-01-01

In this report the results of an intercomparison program within a research coordinated program are presented. This is a third phase of the study that consisted in to evaluate the implementation of the new ICRU quantities for individual monitoring by the SSDLs, their capabilities to perform irradiations in different angles and the interpretation of the standard ISO 4370-3. This phase as well the first one was coordinated by Argentina through the Autoridad Regulatoria Nuclear that verified the performance of the participant laboratories. The SSDL of Argentina calibrated the dosimetric system to be used, and sent a set of tld dosimeters for irradiation at the SSDL or dosimetry laboratories of nine countries of latin america

User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

International Nuclear Information System (INIS)

Kumada, Hiroaki; Torii, Yoshiya

2002-09-01

A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0). (author)

US Department of Energy Laboratory Accreditation Program for personnel dosimetry systems (DOELAP)

International Nuclear Information System (INIS)

Carlson, R.D.; Gesell, T.F.; Kalbeitzer, F.L.; Roberson, P.L.; Jones, K.L.; MacDonald, J.C.; Vallario, E.J.; Pacific Northwest Lab., Richland, WA; USDOE Assistant Secretary for Nuclear Energy, Washington, DC

1988-01-01

The US Department of Energy (DOE) Office of Nuclear Safety has developed and initiated the DOE Laboratory Accreditation Program (DOELAP) for personnel dosimetry systems to assure and improve the quality of personnel dosimetry at DOE and DOE contractor facilities. It consists of a performance evaluation program that measures current performance and an applied research program that evaluates and recommends additional or improved test and performance criteria. It also provides guidance to DOE, identifying areas where technological improvements are needed. The two performance evaluation elements in the accreditation process are performance testing and onsite assessment by technical experts. Performance testing evaluates the participant's ability to accurately and reproducibly measure dose equivalent. Tests are conducted in accident level categories for low- and high-energy photons as well as protection level categories for low- and high-energy photons, beta particles, neutrons and mixtures of these

Super Phenix. Monitoring of structures subject to irradiation. Neutron dosimetry measurement and calculation program

International Nuclear Information System (INIS)

Cabrillat, J.C.; Arnaud, G.; Calamand, D.; Manent, G.; Tavassoli, A.A.

1984-09-01

For the Super Phenix reactor, the evolution, versus the irradiation of the mechanical properties of the core diagrid steel is the object of studies and is particularly monitored. The specimens irradiated, now in PHENIX and will be later irradiated in SUPER PHENIX as soon as the first operating cycles. An important dosimetry program coupling calculation and measurement, is parallely carried out. This paper presents the reasons, the definition of the structure, of the development and of materials used in this program of dosimetry, as also the first results of a calculation-measurement comparison [fr

Minutes of the 13th light water reactor pressure vessel surveillance dosimetry improvement program (LWR-PV-SDIP) meeting

International Nuclear Information System (INIS)

1984-04-01

Information is presented concerning ASTM LWR standards and program documentation; trend curves, PSF, and other test reactor metallurgical programs; PSF dosimetry and metallurgical capsule neutron and gamma environment characterization and metallurgical studies; PVS characterization program; other neutron fields; surveillance dosimetry measurement facility (SDMF) and perturbation studies; transport theory calculations; gamma field benchmarks and photo-reaction studies; and fission and non-fission sensor inventories and quality assurance

Performance testing of dosimetry processors, status of NRC rulemaking for improved personnel dosimetry processing, and some beta dosimetry and instrumentation problems observed by NRC regional inspectors

International Nuclear Information System (INIS)

Dennis, N.A.; Kinneman, J.D.; Costello, F.M.; White, J.R.; Nimitz, R.L.

1983-01-01

Early dosimetry processor performance studies conducted between 1967 and 1979 by several different investigators indicated that a significant percentage of personnel dosimetry processors may not be performing with a reasonable degree of accuracy. Results of voluntary performance testing of US personnel dosimetry processors against the final Health Physics Society Standard, Criteria for Testing Personnel Dosimetry Performance by the University of Michigan for the Nuclear Regulatory Commission (NRC) will be summarized with emphasis on processor performance in radiation categories involving beta particles and beta particles and photon mixtures. The current status of the NRC's regulatory program for improved personnel dosimetry processing will be reviewed. The NRC is proposing amendments to its regulations, 10 CFR Part 20, that would require its licensees to utilize specified personnel dosimetry services from processors accredited by the National Voluntary Laboratory Accreditation Program of the National Bureau of Standards. Details of the development and schedule for implementation of the program will be highlighted. Finally, selected beta dosimetry and beta instrumentation problems observed by NRC Regional Staff during inspections of NRC licensed facilities will be discussed

Neutron dosimetry system SAIPS: Manual for users and programmers (Version 87-02)

International Nuclear Information System (INIS)

Berzonis, M.A.; Bondars, Kh.Ya.; Niedritis, A.M.

1988-07-01

SAIPS is a system used for neutron dosimetry by foil activation, containing a package of programs and a data base of neutron activation cross-sections. A description is given of the SAIPS indexed procedures and users language, which are designed for producing input data for programs unfolding neutron spectra from reaction rate measurements, for carrying out calculations and processing and comparing the results obtained, for utilizing the additional capabilities of the system, and for setting up a working version of the system from the magnetic tapes used for distribution. A description is given of the logical structure of the data sets containing the libraries of neutron cross-section and a priori spectra and also the libraries of calculated spectra. The annexes give examples of SAIPS in use, of the contents of the a priori spectra and neutron cross-section libraries, and of the contents of the SAIPS distribution tapes. SAIPS contains programs in PL/1 (opt), FORTRAN IV(H) and ASSEMBLER. 25 refs

The U.S. food and drug administration's dosimetry program

International Nuclear Information System (INIS)

Baratta, E.

2005-01-01

Full text: The U. S. Public Health Service's (PHS) Food and Drug Administration (FDA) (part of the PHS) has had a Dosimetry Program at the Winchester Engineering and Analytical Center (WEAC) (formerly the Northeastern Radiological Health Laboratory). This Dosimetry Program has been in place since 1961. In 1967 it was augmented by the construction of a Whole Body Counter at WEAC for measuring internal dose. The FDA's Center for Medical Devices and Radiological Health had been handling these dosimeters since 1961 and in 2000 the WEAC took over total responsibility for this program for the FDA's Office of Regulatory affairs. This program was originally setup for the radiation workers (analysts and support personnel) and later included investigators personnel working in the medical and dental x-ray field. The field laboratories began using radionuclides in 1972 and were also issued radiation dosimeters. Investigators station at border import station alter 2003 were issued as well as radiation pages as a precaution when checking imported food and other FDA regulated products. This paper will discuss the results of radiation exposure received by analyst (including whole body measurements) at WEAC and field laboratories. Also discussed will be exposures to investigators in the medical and dental field. The exposure to the investigators at the import border stations will be included even though they have not been carrying dosimeters for slightly more than a year. In general, the exposures have been well below the Nuclear Regulatory Commission regulations for radiation workers. (author)

TAP 3, Training Program Support Manual

International Nuclear Information System (INIS)

1991-07-01

Training programs at DOE facilities should provide well-trained, qualified personnel to safely and efficiently operate the facilities in accordance with DOE requirements. A need has been identified for guidance regarding analysis, design, development, implementation, and evaluation of consistent and reliable performance-based training programs. Accreditation of training programs at Category A reactors and high-hazard and selected moderate-hazard nonreactor nuclear facilities will assure consistent, appropriate, and cost-effective training of personnel responsible for the operation, maintenance, and technical support of these facilities. Training programs that are designed and based on systematically determined job requirements, instead of subjective estimation of trainee needs, yield training activities that are consistent and develop or improve knowledge, skills, and abilities that can be directly related to the work setting. Because the training is job-related, the content of these programs more efficiently and effectively meets the needs of the employee. Besides a better trained work force, a greater level of operational reactor safety can be realized. This manual is intended to provide an overview of the accreditation process and a brief description of the elements necessary to construct and maintain training programs that are based on the requirements of the job. Two companion manuals provide additional information to assist contractors in their efforts to accredit training programs

Quality assurance program in the External dosimetry laboratory of the CPHR

International Nuclear Information System (INIS)

Molina P, D.; Pernas S, R.; Martinez H, E.; Cardenas H, J.

2006-01-01

From 1999 the Laboratory of External Dosimetry of the Radiation Protection and Hygiene Center comes applying in its service of personal dosimetry a Program of Quality Assurance. This program was designed according to the recommendations of national and international organizations as the National Assuring Office of the Republic of Cuba (ONARC), the International Standards Organization (ISO), the International Electro technique Commission (IEC) and the International Atomic Energy Agency (IAEA). In this work it is presented in a summarized way the operation of this Program of Quality Assurance which includes the administration and conservation of the results and the documentation of the service, the controls that are carried out to the equipment, the acceptance tests that are applied to the equipment and new dosemeters, the shipment and prosecution of the dosemeters, the evaluation, storage and conservation of the doses, the report of the results, the traceability and reproducibility of the measurements, the attention to the reclamations and the clients complaints and the internal and external audits to those that it undergoes periodically the laboratory. (Author)

Textbook of dosimetry. 4. ed.

International Nuclear Information System (INIS)

Ivanov, V.I.

1999-01-01

This textbook of dosimetry is devoted to the students in physics and technical physics of high education institutions, confronted with different application of atomic energy as well as with protection of population and environment against ionizing radiations. Atomic energy is highly beneficial for man but unfortunately incorporates potential dangers which manifest in accidents, the source of which is either insufficient training of the personnel, a criminal negligence or insufficient reliability of the nuclear facilities. The majority of the incident and accident events have had as origin the personnel errors. This was the case with both the 'Three Miles Island' (1979) and Chernobyl (1986) NPP accidents. The dosimetry science acquires a vital significance in accident situations since the data obtained by its procedures are essential in choosing the correct immediate actions, behaviour tactics, orientation of liquidation of accident consequences as well as in ensuring the health of population. An important accent is placed in this manual on clarification of the nature of physical processes taken place in dosimetric detectors, in establishing the relation between radiation field characteristics and the detector response as well as in defining different dosimetric quantities. The terminology and the units of physical quantities is based on the international system of units. The book contains the following 15 chapters: 1. Ionizing radiation field; 2. Radiation doses; 3. Physical bases of gamma radiation dosimetry; 4. Ionization dosimetric detectors; 5. Semiconductor dosimetric detectors; 6. Scintillation detection in the gamma radiation dosimetry; 7. Luminescent methods in dosimetry; 8. The photographic and chemical methods of gamma radiation dosimetry; 9. Neutron dosimetry; 10. Dosimetry of high intensity radiation; 11. Dosimetry of high energy Bremsstrahlung; 12. Measurement of the linear energy transfer; 13. Microdosimetry; 14. Dosimetry of incorporated

SNL/CA Environmental Management System Program Manual.

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2005-09-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program was developed in accordance with Department of Energy (DOE) Order 450.1 and incorporates the elements of the International Standard on Environmental Management Systems, ISO 14001.

Dosimetry of internal emitters

International Nuclear Information System (INIS)

Anon.

1982-01-01

The Dosimetry of Internal Emitter Program endeavors to refine the correlation between radiation dose and observed biological effects. The program is presently engaged in the development of studies that will demonstrate the applicability of microdosimetry models developed under the Microdosimetry of Internal Sources Program. The program also provides guidance and assistance to Pacific Northwest Laboratory's Biology Department in the dosimetric analysis of internally deposited radionuclides. This report deals with alpha particle dosimetry plutonium 239 inhalation, and in vitro studies of chromosomal observations

Program management system manual

International Nuclear Information System (INIS)

1989-08-01

OCRWM has developed a program management system (PMS) to assist in organizing, planning, directing and controlling the Civilian Radioactive Waste Management Program. A well defined management system is necessary because: (1) the Program is a complex technical undertaking with a large number of participants, (2) the disposal and storage facilities to be developed by the Program must be licensed by the Nuclear Regulatory Commission (NRC) and hence are subject to rigorous quality assurance (QA) requirements, (3) the legislation mandating the Program creates a dichotomy between demanding schedules of performance and a requirement for close and continuous consultation and cooperation with external entities, (4) the various elements of the Program must be managed as parts of an integrated waste management system, (5) the Program has an estimated total system life cycle cost of over $30 billion, and (6) the Program has a unique fiduciary responsibility to the owners and generators of the nuclear waste for controlling costs and minimizing the user fees paid into the Nuclear Waste Fund. This PMS Manual is designed and structured to facilitate strong, effective Program management by providing policies and requirements for organizing, planning, directing and controlling the major Program functions

SNL/CA Environmental Management System Program Manual.

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2007-04-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004. Elements of the ISO standard overlap with those of Department of Energy (DOE) Order 450.1, thus SNL/CA's EMS program also meets the DOE requirements.

ALGORITHM VERIFICATION FOR A TLD PERSONAL DOSIMETRY SYSTEM

International Nuclear Information System (INIS)

SHAHEIN, A.; SOLIMAN, H.A.; MAGHRABY, A.

2008-01-01

Dose algorithms are used in thermoluminescence personnel dosimetry for the interpretation of the dosimeter response in terms of equivalent dose. In the present study, an automated Harshaw 6600 reader was vigorously tested prior to the use for dose calculation algorithm according to the standard established by the US Department of Energy Laboratory Accreditation Program (DOELAP). Also, manual Harshaw 4500 reader was used along with the ICRU slab phantom and the RANDO phantom in experimentally determining the photon personal doses in terms of deep dose; Hp(10), shallow dose; Hp(0.07), and eye lens dose; Hp(3). Also, a Monte Carlo simulation program (VMC-dc) free code was used to simulate RANDO phantom irradiation process. The accuracy of the automated system lies well within DOELAP tolerance limits in all test categories

User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

Energy Technology Data Exchange (ETDEWEB)

Kumada, Hiroaki; Torii, Yoshiya [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

2002-09-01

A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to simulate the state of a head after its surgical processes such as skin flap opening and bone removal for the BNCT with craniotomy that are being performed in Japan. JCDS can provide information for the Patient Setting System to set the patient in an actual irradiation position swiftly and accurately. This report describes basic design and procedure of dosimetry, operation manual, data and library structure for JCDS (ver.1.0). (author)

C.T. scan based dosimetry in treating carcinoma of oral tongue

International Nuclear Information System (INIS)

Sudarshan, G.; Ranganathan, Vanisehree

1999-01-01

It is a well established norm that a combination of external radiation and iridium implant in early stage squamous cell carcinoma (SCC) of oral tongue gives good results. We have treated 10 consecutive patients of SCC of anterior 2/3 of tongue staged T1-2 NO by giving 4000 cGy external radiation and 3000 cGy boost with iridium-192 implant. Traditionally, orthogonal radiographs have been taken to determine the spatial distribution of sources. As we do not have a simulator, we have taken 2-4 C.T. scan images perpendicular to the axis of implant. By using this cross-sectional information, we identified the source points and a basal dose rate was calculated manually by following the geometric principles of Paris system as our T.P.S. did not have the required software. Clinically, 9 out of the 10 patients are in remission (N.E.D. = No evidence of disease) at 18 months follow-up. Our aim of this presentation is to compare manual dosimetry with T.P.S. generated dosimetry and to show that manual dosimetry is also dependable. (author)

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 1, Conceptual representation

Energy Technology Data Exchange (ETDEWEB)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-12-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes code logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 72 refs., 15 figs., 34 tabs.

GENII: The Hanford Environmental Radiation Dosimetry Software System: Volume 1, Conceptual representation

International Nuclear Information System (INIS)

Napier, B.A.; Peloquin, R.A.; Strenge, D.L.; Ramsdell, J.V.

1988-12-01

The Hanford Environmental Dosimetry Upgrade Project was undertaken to incorporate the internal dosimetry models recommended by the International Commission on Radiological Protection (ICRP) in updated versions of the environmental pathway analysis models used at Hanford. The resulting second generation of Hanford environmental dosimetry computer codes is compiled in the Hanford Environmental Dosimetry System (Generation II, or GENII). The purpose of this coupled system of computer codes is to analyze environmental contamination resulting from acute or chronic releases to, or initial contamination of, air, water, or soil. This is accomplished by calculating radiation doses to individuals or populations. GENII is described in three volumes of documentation. The first volume describes the theoretical considerations of the system. The second volume is a Users' Manual, providing code structure, users' instructions, required system configurations, and QA-related topics. The third volume is a Code Maintenance Manual for the user who requires knowledge of code detail. It includes code logic diagrams, global dictionary, worksheets, example hand calculations, and listings of the code and its associated data libraries. 72 refs., 15 figs., 34 tabs

Oak Ridge National Laboratory Embrittlement Data Base (EDB) and Dosimetry Evaluation (DE) program

International Nuclear Information System (INIS)

Pace, J.V. III; Remec, I.; Wang, J.A.; White, J.E.

1996-01-01

The objective of this program is to develop, maintain, and upgrade computerized data bases, calculational procedures, and standards relating to reactor pressure vessel fluence spectra determinations and embrittlement assessments. As part of this program, the information from radiation embrittlement research on nuclear reactor pressure vessel steels and from power reactor surveillance reports is maintained in a data base published on a periodic basis. The Embrittlement Data Base (EDB) effort consists of verifying the quality of the EDB, providing user-friendly software to access and process the data, and exploring and assessing embrittlement prediction models. The Dosimetry Evaluation effort consists of maintaining and upgrading validated neutron and gamma radiation transport procedures, maintaining cross-section libraries with the latest evaluated nuclear data, and maintaining and updating validated dosimetry procedures and data bases. The information available from this program provides data for assisting the Office of Nuclear Reactor Regulation, with support from the Office of Nuclear Regulatory Research, to effectively monitor current procedures and data bases used by vendors, utilities, and service laboratories in the pressure vessel irradiation surveillance program

Standardized physics-dosimetry for US pressure vessel cavity surveillance programs

International Nuclear Information System (INIS)

Ruddy, F.H.; McElroy, W.N.; Lippincott, E.P.

1984-01-01

This paper summarizes the applications of ASTM standard methods, guides and practices to define the selection and deployment of recommended dosimetry sets, the selection of dosimetry capsules and thermal neutron shields, the placement of dosimetry, the methods of measurement of dosimetry sensor reaction products, data analysis procedures, and uncertainty evaluation procedures. It also describes the validation of these standards both by in-reactor testing of advanced PV cavity surveillance physics-dosimetry and by data development. The use of these standards to guide selection and development of advanced dosimetry sets for commercial reactors is also summarized. (Auth.)

General Employee Radiological Training and Radiological Worker Training: Program management manual

International Nuclear Information System (INIS)

1992-10-01

This manual defines and describes the DOE General Employee Radiological Training (GERT) and Radiological Worker I and II (RW I and II) Training programs. It includes material development requirements, standards and policies, and program administration. This manual applies to General Employee Radiological Training and Radiological Worker Training at all DOE contractor sites. The training materials of both GERT and RW I and II training reflect the requirements identified in the DOE Radiological Control Manual and DOE Order 5480.11. The training programs represent the minimum requirement for the standardized core materials. Each contractor shall implement the program in its entirety and may augment the standardized core materials to increase the general employee and radiological worker level of competency

DOE Radiological Control Manual Core Training Program

International Nuclear Information System (INIS)

Scott, H.L.; Maisler, J.

1993-01-01

Over the past year, the Department of Energy (DOE) Office of Health (EH-40) has taken a leading role in the development of new standardized radiological control training programs for use throughout the DOE complex. The Department promulgated its Radiological Control (RadCon) Manual in June 1992. To ensure consistent application of the criteria presented in the RadCon Manual, standardized radiological control core training courses and training materials have been developed for implementation at all DOE facilities. In producing local training programs, standardized core courses are to be supplemented with site-specific lesson plans, viewgraphs, student handbooks, qualification standards, question banks, and wallet-sized training certificates. Training programs for General Employee Radiological Training, Radiological Worker I and II Training, and Radiological Control Technician Training have been disseminated. Also, training committees under the direction of the Office of Health (EH-40) have been established for the development of additional core training courses, development of examination banks, and the update of the existing core training courses. This paper discusses the current activities and future direction of the DOE radiological control core training program

Computer Program for Calculation of Complex Chemical Equilibrium Compositions and Applications II. Users Manual and Program Description. 2; Users Manual and Program Description

Science.gov (United States)

McBride, Bonnie J.; Gordon, Sanford

1996-01-01

This users manual is the second part of a two-part report describing the NASA Lewis CEA (Chemical Equilibrium with Applications) program. The program obtains chemical equilibrium compositions of complex mixtures with applications to several types of problems. The topics presented in this manual are: (1) details for preparing input data sets; (2) a description of output tables for various types of problems; (3) the overall modular organization of the program with information on how to make modifications; (4) a description of the function of each subroutine; (5) error messages and their significance; and (6) a number of examples that illustrate various types of problems handled by CEA and that cover many of the options available in both input and output. Seven appendixes give information on the thermodynamic and thermal transport data used in CEA; some information on common variables used in or generated by the equilibrium module; and output tables for 14 example problems. The CEA program was written in ANSI standard FORTRAN 77. CEA should work on any system with sufficient storage. There are about 6300 lines in the source code, which uses about 225 kilobytes of memory. The compiled program takes about 975 kilobytes.

Standardized physics-dosimetry for US pressure vessel cavity surveillance programs

International Nuclear Information System (INIS)

Ruddy, F.H.; McElroy, W.N.; Lippincott, E.P.

1984-01-01

Standardized Physics-Dosimetry procedures and data are being developed and tested for monitoring the neutron doses accumulated by reactor pressure vessels (PV) and their support structures. These procedures and data are governed by a set of 21 ASTM standard practices, guides, and methods for the prediction of neutron-induced changes in light water reactor (LWR) PVs and support structure steels throughout the service life of the PV. This paper summarizes the applications of these standards to define the selection and deployment of recommended dosimetry sets, the selection of dosimetry capsules and thermal neutron shields, the placement of dosimetry, the methods of measurement of dosimetry sensor reaction products, data analysis procedures, and uncertainty evaluation procedures. It also describes the validation of these standards both by in-reactor testing of advanced PV cavity surveillance physics-dosimetry and by data development. The use of these standards to guide selection and deployment of advanced dosimetry sets for commercial reactors is also summarized

Home audit program: management manual

Energy Technology Data Exchange (ETDEWEB)

1980-09-01

Many public power systems have initiated home energy audit programs in response to the requests of their consumers. The manual provides smaller public power systems with the information and specific skills needed to design and develop a program of residential energy audits. The program is based on the following precepts: locally owned public systems are the best, and in many cases the only agencies available to organize and coordinate energy conservation programs in many smaller communities; consumers' rights to energy conservation information and assistance should not hinge on the size of the utility that serves them; in the short run, public power systems of all sizes should offer residential energy conservation assistance to their consumers, because such assistance is desirable, necessary, and in the public interest; and in the long run, such programs will complement national energy goals and will produce economic benefits for both consumers and the public power system. A detailed description of home audit program planning, organization, and management are given. (MCW)

Experimental verification of internal dosimetry calculations. Annual progress report

International Nuclear Information System (INIS)

1980-05-01

During the past year a dosimetry research program has been established in the School of Nuclear Engineering at the Georgia Institute of Technology. The major objective of this program has been to provide research results upon which a useful internal dosimetry system could be based. The important application of this dosimetry system will be the experimental verification of internal dosimetry calculations such as those published by the MIRD Committee

Latinamerican Biological Dosimetry Network (LBDNET). International Biological Dosimetry intercomparison Program (exercise 2007-2008)

International Nuclear Information System (INIS)

Di Giorgio, Marina; Vallerga, Maria B.; Radl, A.; Taja, Maria R.

2009-01-01

This paper describes the International Biological Dosimetry Intercomparison Program (exercise 2007-2008) - developed within the framework of the IAEA regional project - RLA/9/054 (Establishment of national capabilities for response to radiological and nuclear emergency) whose general objectives are: assess reproducibility inter-laboratory; identify problems and provide the necessary modifications for collaborative work in accidental situations requiring activation of mutual assistance mechanisms which will form the basis of the Organization of LBDNET. This exercise involves the laboratories of the region: Argentina (laboratory support), Brazil, Chile, Cuba, Mexico, Peru and Uruguay and the laboratory of the Autonomous University of Barcelona-Espana (Joan Francesc Barquinero and staff). Finally, these countries will meet the next time for the drafting of a final report and later publication. (author)

Radiation dosimetry and radiation biophysics

International Nuclear Information System (INIS)

Anon.

1979-01-01

Radiation dosimetry and radiation biophysics are two closely integrated programs whose joint purpose is to explore the connections between the primary physical events produced by radiation and their biological consequences in cellular systems. The radiation dosimetry program includes the theoretical description of primary events and their connection with the observable biological effects. This program also is concerned with design and measurement of those physical parameters used in the theory or to support biological experiments. The radiation biophysics program tests and makes use of the theoretical developments for experimental design. Also, this program provides information for further theoretical development through experiments on cellular systems

LWR-PV Surveillance Dosimetry Improvement Program review graphics

International Nuclear Information System (INIS)

McElroy, W.N.; Gold, R.; Gutherie, G.L.

1979-10-01

A primary objective of the multilaboratory program is to prepare an updated and improved set of dosimetry, damage correlation, and the associated reactor analysis ASTM standards for LWR-PV irradiation surveillance programs. Supporting this objective are a series of analytical and experimental validation and calibration studies in Benchmark Neutron Fields, reactor Test Regions, and operating power reactor Surveillance Positions. These studies will establish and certify the precision and accuracy of the measurement and predictive methods which are recommended for use in these standards. Consistent and accurate measurement and data analysis techniques and methods, therefore, will have been developed and validated along with guidelines for required neutron field calculations that are used to (1) correlate changes in material properties with the characteristics of the neutron radiation field and (2) predict pressure vessel steel toughness and embrittlement from power reactor surveillance data

Sandia National Laboratories, California Environmental Management System program manual.

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2013-04-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004 and Department of Energy (DOE) Order 436.1.

Sandia National Laboratories, California Environmental Management System program manual

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2014-04-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004 and Department of Energy (DOE) Order 436.1.

Impact Parent Program Workshop Leader's Manual.

Science.gov (United States)

Marvelle, John D., Comp.; And Others

This program manual provides a series of eight two-hour sessions designed to further parents' abilities to teach and communicate with their young children and to build supportive family school relationships. Session I introduces the series and emphasizes the important role parents have as teachers of their children. In Session II an overview of…

Highway Safety Program Manual: Volume 3: Motorcycle Safety.

Science.gov (United States)

National Highway Traffic Safety Administration (DOT), Washington, DC.

Volume 3 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on aspects of motorcycle safety. The purpose and specific objectives of a State motorcycle safety program are outlined. Federal authority in the highway safety area and general policies…

Radiation dosimetry and radiation biophysics

International Nuclear Information System (INIS)

Anon.

1981-01-01

Radiation dosimetry and radiation biophysics are two closely integrated programs whose joint purpose is to explore the connections between the primary physical events produced by radiation and their biological consequences in cellular systems. The radiation dosimetry program includes the theoretical description of primary events and their connection with the observable biological effects. This program also is concerned with the design and measurement of physical parameters used in theory or to support biological experiments. The radiation biophysics program tests and uses the theoretical developments for experimental design, and provides information for further theoretical development through experiments on cellular systems

The program of international intercomparison of accident dosimetry; Le programme d'intercomparaison internationale de dosimetrie d'accident 10-12 juin 2002

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-06-01

The French institute of radioprotection and nuclear safety (IRSN) has carried out in June 2002 an international intercomparison program for the testing of the physical and biological accident dosimetry techniques. The intercomparison is jointly organized by the IRSN and the OECD-NEA with the sustain of the European commission and the collaboration of the CEA centre of Valduc (France). About 30 countries have participated to this program. Each country has supplied its own dosimeters and biological samples which have been irradiated using the Silene reactor of CEA-Valduc or a {sup 60}Co source. These experiments allow to test the new dosimetric techniques that have been developed since the previous intercomparison program (1993) and to confirm or improve the performances of older techniques. Aside from the intercomparison exercise, this report makes a status of the known radiological accidents and of the effects of high doses of ionizing radiations on human health (symptoms, therapeutics). It explains the phenomenology of criticality accidents, the prevention means, and the history of such accidents up to the Tokai-Mura one in 1999. Finally, the dosimetry of criticality is presented with its physical and biological techniques. (J.S.)

Computer program user's manual for FIREFINDER digital topographic data verification library dubbing system

Science.gov (United States)

Ceres, M.; Heselton, L. R., III

1981-11-01

This manual describes the computer programs for the FIREFINDER Digital Topographic Data Verification-Library-Dubbing System (FFDTDVLDS), and will assist in the maintenance of these programs. The manual contains detailed flow diagrams and associated descriptions for each computer program routine and subroutine. Complete computer program listings are also included. This information should be used when changes are made in the computer programs. The operating system has been designed to minimize operator intervention.

Minutes of the 14th Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Program (LWR-PV-SDIP) meeting, October 1-5, 1984

International Nuclear Information System (INIS)

1984-01-01

Topics discussed include: ASTM LWR standards; trend curves, PSF, and other test reactor metallurgical programs; PSF dosimetry and metallurgical capsule neutron and gamma characterization and metallurgical studies; PVS characterization program; other neutron fields; Surveillance Dosimetry Measurement Facility (SDMF) and perturbation studies; transport theory calculations; gamma field benchmarks and photo-reaction studies; and fission and non-fission sensor inventories and quality assurance

In vivo dosimetry in radiation therapy in Sweden; In vivo-dosimetri inom straalbehandling i Sverige

Energy Technology Data Exchange (ETDEWEB)

Eriksson, Jacob; Blomquist, Michael (Norrlands universitetssjukhus, Umeaa (Sweden))

2010-07-15

A prerequisite for achieving high radiation safety for patients receiving external beam radiation therapy is that the hospitals have a quality assurance program. The program should include include monitoring of the radiation dose given to the patient. Control measurements are performed both at the system level and at the individual level. Control measurement is normally performed using in vivo dosimetry, e.g. a method to measure the radiation dose at the individual level during the actual radiation treatment time. In vivo dosimetry has proven to be an important tool to detect and prevent serious errors in patient treatment. The purpose of this research project was to identify the extent to which vivo dosimetry is used and the methods available for this at Swedish radiation therapy clinics. The authority also wanted to get an overall picture of how hospitals manage results of in vivo dosimetry, and how clinics control radiation dose when using modern treatment techniques. The report reflects the situation in Swedish radiotherapy clinics 2007. The report shows that all hospitals use some form of in vivo dosimetry. The instruments used are mainly diodes and termoluminiscence dosimeters

Finite element program Lamcal. (User's manual)

International Nuclear Information System (INIS)

Lamain, L.G.; Blanckenburg, J.F.G.

1982-01-01

The present user's manual gives the input formats, job control and an input example for the finite element part of the Lamcal program. The input data have been organized in a more or less self explaining way, using keywords and standard input formats and is printed at the beginning of every run. To simplify the use of the whole program and to avoid unecessary data handling, all three parts of the Lamcal program, meshgeneration, plotting and, FE, are combined into one load module. This setup allows to do all calculations in one single run. However, preprocessing, postprocessing and restarts can be made in separate runs as well. The same reserved space for the dynamic core storage is used in all three parts, if the available space is not sufficient the FE program will stop

Standardization of dosimetry and damage analysis work for U.S. LWR, FBR, and MFR development program

International Nuclear Information System (INIS)

McElroy, W.N.; Doran, D.G.; Gold, R.; Morgan, W.C.; Grundl, J.A.; McGarry, E.D.; Kam, F.B.K.; Swank, J.H.; Odette, G.R.

1978-01-01

The accuracy requirements for various measured/calculated exposure and correlation parameters associated with current dosimetry and damage analysis procedures and practices depend on the accuracy needs of reactor development efforts in testing, design, safety, operations, and surveillance programs. Present state-of-the-art accuracies are estimated to be in the range of +-2 to 30 percent (1 sigma), depending on the particular parameter. There now appears to be international agreement, at least for the long term, that most reactor fuels and materials programs will not be able to accept an uncertainty greater than about +5 percent (1 sigma). The current status of dosimetry and damage analysis standardization work within the U.S. for LWR, FBR and MFR is reviewed in this paper

Computer-assisted planning and dosimetry for radiation treatment of head and neck cancer in Cameroon

International Nuclear Information System (INIS)

Yomi, J.; Ngniah, A.; Kingue, S.; Muna, W.F.T.; Durosinmi-Etti, F.A.

1995-01-01

This evaluation was part of a multicenter, multinational study sponsored by the International Agency for Atomic Energy (Vienna) to investigate a simple, reliable computer-assisted planning and dosimetry system for radiation treatment of head and neck cancers in developing countries. Over a 13-month period (April 1992-April 1993), 120 patients with histologically-proven head or neck cancer were included in the evaluation. In each patient, planning and dosimetry were done both manually and using the computer-assisted system. The manual and computerized systems were compared on the basis of accuracy of determination of the outer contour, target volume, and critical organs; volume inequality resolution; structure heterogeneity correction; selection of the number, angle, and size of beams; treatment time calculation; availability of dosimetry predictions; and duration and cost of the procedure. Results demonstrated that the computer-assisted procedure was superior over the manual procedure, despite less than optimal software. The accuracy provided by the completely computerized procedure is indispensable for Level II radiation therapy, which is particularly useful in tumors of the sensitive, complex structures in the head and neck. (authors). 7 refs., 3 tabs

Revision of the protective action guides manual for nuclear incidents

International Nuclear Information System (INIS)

DeCair, S.; MacKinney, J.

2007-01-01

EPA's 1992 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, referred to as the PAG Manual, is a radiological emergency planning and response tool for emergency management officials at the Federal, state, tribal, and local levels. A Protective Action Guide is defined as, the projected dose to reference man, or other defined individual, from a release of radioactive material at which a specific protective action to reduce or avoid that dose is recommended'. The updated version of the PAG Manual accomplishes these key objectives: applying the existing 1992 protective action guides and protective actions to new radiological and nuclear scenarios of concern; updating the dosimetry basis; lowering the recommended dose for administration of stable iodine; providing new guidance concerning consumption of drinking water during or after a radiological emergency; updating the dosimetry basis for all derived levels, and, adding guidance for dealing with long-term site restoration following a major radiological release. (author)

75 FR 52976 - Issuance of Revised Users' Manual for Commission Mediation Program for Investigations Under...

Science.gov (United States)

2010-08-30

... INTERNATIONAL TRADE COMMISSION Issuance of Revised Users' Manual for Commission Mediation Program... 65615 (Nov. 8, 2008). The Commission has determined to issue a revised Users' Manual for its program for the mediation of investigations under section 337 of the Tariff Act of 1930. The revised Users' Manual...

Annual course of retraining for the occupational exposure personnel of the laboratory of internal dosimetry

International Nuclear Information System (INIS)

Alfaro L, M.M.

2002-09-01

The general objective of this report is to instruct the personnel in the basic concepts of radiological protection and in the Manual of Procedures of Radiological Safety of the Laboratory of Internal Dosimetry. Also, to exchange experiences during the activities that are carried out in the laboratory and in the knowledge of abnormal situations. The referred Manual consists of 14 procedures and 5 instructions which are listed in annex of this document. The content of this course consists of three topics: 1. Basic principles of radiological protection to reduce the received dose equivalent. 2. Use of radiation measurer equipment. 3. Emergency procedures of the laboratory of internal dosimetry. (Author)

National Uranium Resource Evaluation Program. Hydrogeochemical and Stream Sediment Reconnaissance Basic Data Reports Computer Program Requests Manual

International Nuclear Information System (INIS)

1980-01-01

This manual is intended to aid those who are unfamiliar with ordering computer output for verification and preparation of Uranium Resource Evaluation (URE) Project reconnaissance basic data reports. The manual is also intended to help standardize the procedures for preparing the reports. Each section describes a program or group of related programs. The sections are divided into three parts: Purpose, Request Forms, and Requested Information

Synfuel program analysis. Volume 2: VENVAL users manual

Science.gov (United States)

Muddiman, J. B.; Whelan, J. W.

1980-07-01

This volume is intended for program analysts and is a users manual for the VENVAL model. It contains specific explanations as to input data requirements and programming procedures for the use of this model. VENVAL is a generalized computer program to aid in evaluation of prospective private sector production ventures. The program can project interrelated values of installed capacity, production, sales revenue, operating costs, depreciation, investment, dent, earnings, taxes, return on investment, depletion, and cash flow measures. It can also compute related public sector and other external costs and revenues if unit costs are furnished.

Real-Time Multiprocessor Programming Language (RTMPL) user's manual

Science.gov (United States)

Arpasi, D. J.

1985-01-01

A real-time multiprocessor programming language (RTMPL) has been developed to provide for high-order programming of real-time simulations on systems of distributed computers. RTMPL is a structured, engineering-oriented language. The RTMPL utility supports a variety of multiprocessor configurations and types by generating assembly language programs according to user-specified targeting information. Many programming functions are assumed by the utility (e.g., data transfer and scaling) to reduce the programming chore. This manual describes RTMPL from a user's viewpoint. Source generation, applications, utility operation, and utility output are detailed. An example simulation is generated to illustrate many RTMPL features.

Dosimetry; La dosimetrie

Energy Technology Data Exchange (ETDEWEB)

Le Couteulx, I.; Apretna, D.; Beaugerie, M.F. [Electricite de France (EDF), 75 - Paris (France)] [and others

2003-07-01

Eight articles treat the dosimetry. Two articles evaluate the radiation doses in specific cases, dosimetry of patients in radiodiagnosis, three articles are devoted to detectors (neutrons and x and gamma radiations) and a computer code to build up the dosimetry of an accident due to an external exposure. (N.C.)

Quality assurance program manual for nuclear power plants. Volume I. Policies

International Nuclear Information System (INIS)

1976-01-01

The Consumers Power Company Quality Assurance Program Manual for Nuclear Power Plants consists of policies and procedures which comply with current NRC regulatory requirements and industry codes and standards in effect during the design, procurement, construction, testing, operation, refueling, maintenance, repair and modification activities associated with nuclear power plants. Specific NRC and industry documents that contain the requirements, including the issue dates in effect, are identified in each nuclear power plant's Safety Analysis Report. The requirements established by these documents form the basis for the Consumer Power Quality Assurance Program, which is implemented to control those structures, systems, components and operational safety actions listed in each nuclear power plant's Quality List (Q-List). As additional and revised requirements are issued by the NRC and professional organizations involved in nuclear activities, they will be reviewed for their impact on this manual, and changes will be made where considered necessary. CP Co 1--Consumers Power Company QA Program Topical Report is Volume I of this manual and contains Quality Assurance Program Policies applicable during all phases of nuclear power plant design, construction and operation

Super Summer Safari Manual: 1989 Summer Library Program. Bulletin No. 9240.

Science.gov (United States)

Roeber, Jane A., Ed.

Based on the theme, "Super Summer Safari: Make Books Your Big Game," this manual describes library activities intended to stimulate family explorations of local and regional natural environments, of urban parks, and of agricultural settings. The manual is divided into 6 sections: (1) "Planning and Promoting Programs"; (2)…

Cuerpo de Paz Manual de Sistema de Programacion y Capacitacion (Peace Corps Programming and Training System Manual): T0063.

Science.gov (United States)

Peace Corps, Washington, DC.

This Spanish version of the Peace Corps Programming and Training System Manual is designed to help field staff members of the Peace Corps train volunteers. Its task descriptions, guidelines, examples, and definitions are intended to be practical and informative rather than restrictive. The manual is divided into six major sections: (1)…

Peace Corps Aquaculture Training Manual. Training Manual T0057.

Science.gov (United States)

Peace Corps, Washington, DC. Information Collection and Exchange Div.

This Peace Corps training manual was developed from two existing manuals to provide a comprehensive training program in fish production for Peace Corps volunteers. The manual encompasses the essential elements of the University of Oklahoma program that has been training volunteers in aquaculture for 25 years. The 22 chapters of the manual are…

Third conference on radiation protection and dosimetry

International Nuclear Information System (INIS)

1991-01-01

This conference has been designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection and providing them with sufficient information to evaluate their programs. To partly fulfill these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection has been prepared. General topics include external dosimetry, internal dosimetry, instruments, regulations and standards, accreditation and test programs, research advances, and applied program experience. This publication provides a summary of the technical program and a collection of abstracts of the oral presentations

Guide for dosimetry for sterile insect release programs. 2. ed.

International Nuclear Information System (INIS)

2004-01-01

This guide outlines dosimetric procedures to be followed for the radiation sterilization of live insects for use in pest management programs. The primary use of irradiated, reproductively sterile insects is in the Sterile Insect Technique, where large numbers of sterile insects are released into the field to mate with and thus control pest populations of the same species. A secondary use of sterile insects is as benign hosts for rearing insect parasitoids. The procedures outlined in this guide will help ensure that insects processed with ionizing radiation from gamma, electron, or X-ray sources receive absorbed doses within a predetermined range. Information on effective dose ranges for specific applications of insect sterilization, or on methodology for determining effective dose ranges, is not within the scope of this guide. Note: Dosimetry is only one component of a total quality control program to ensure that irradiated insects are adequately sterilized and sufficiently competitive or otherwise suitable for their intended purpose. This guide covers dosimetry in the irradiation of insects for these types of irradiators: self-contained dry-storage 137 Cs or 60 Co irradiators, large-scale gamma irradiators, and electron accelerators. Additional, detailed information on dosimetric procedures to be followed in installation qualification, operational qualification, performance qualification, and routine product processing can be found in ISO/ASTM Practices 51608 (X-ray [bremsstrahlung] facilities), 51649 (electron beam facilities), 51702 (large-scale gamma facilities), and ASTM Practice E 2116 (self-contained dry-storage gamma facilities). The absorbed dose for insect sterilization is typically within the range of 20 Gy to 600 Gy

National Waste Terminal Storage Program, planning and control system manual

International Nuclear Information System (INIS)

1976-09-01

This manual contains a brief description of the NWTS program in order to define the environment within which the system must function; an overview of the system, and the concepts and techniques that were utilized in its development; and OWI implementation on the NWTS Program

A Computerized QC Analysis of TLD Glow Curves for Personal Dosimetry Measurements Using TagQC Program

International Nuclear Information System (INIS)

Primo, S.; Datz, H.; Dar, A.

2014-01-01

The External Dosimetry Lab (EDL) at the Radiation Safety Division at Soreq Nuclear Research Center (SNRC) is ISO 17025 certified and provides its services to approximately 13,000 users throughout the country from various sectors such as medical, industrial and academic. About 95% of the users are monitored monthly for X-rays, and radiation using Thermoluminescence Dosimeter (TLD) cards that contain three LiF:Mg,Ti elements and the other users, who work also with thermal neutrons, use TLD cards that contain four LiF:Mg,Ti elements. All TLD cards are measured with the Thermo 8800pc reader.Suspicious TLD glow curve (GC) can cause wrong dose estimation so the EDL makes great efforts to ensure that each GC undergoes a careful QC procedure. The current QC procedure is performed manually and through a few steps using different softwares and databases in a long and complicated procedure: EDL staff needs to export all the results/GCs to be checked to an Excel file, followed by finding the suspicious GCs, which is done in a different program (WinREMS), According to the GC shapes (Figure 1 illustrates suitable and suspicious GC shapes) and the ratio between the elements result values, the inspecting technician corrects the data

Aquifer thermal energy storage reference manual: seasonal thermal energy storage program

Energy Technology Data Exchange (ETDEWEB)

Prater, L.S.

1980-01-01

This is the reference manual of the Seasonal Thermal Energy Storage (STES) Program, and is the primary document for the transfer of technical information of the STES Program. It has been issued in preliminary form and will be updated periodically to include more technical data and results of research. As the program progresses and new technical data become available, sections of the manual will be revised to incorporate these data. This primary document contains summaries of: the TRW, incorporated demonstration project at Behtel, Alaska, Dames and Moore demonstration project at Stony Brook, New York, and the University of Minnesota demonstration project at Minneapolis-St. Paul, Minnesota; the technical support programs including legal/institutional assessment; economic assessment; environmental assessment; field test facilities; a compendia of existing information; numerical simulation; and non-aquifer STES concepts. (LCL)

Technical basis for external dosimetry at the Waste Isolation Pilot Plant (WIPP)

International Nuclear Information System (INIS)

Bradley, E.W.; Wu, C.F.; Goff, T.E.

1993-01-01

The WIPP External Dosimetry Program, administered by Westinghouse Electric Corporation, Waste Isolation Division, for the US Department of Energy (DOE), provides external dosimetry support services for operations at the Waste Isolation Pilot Plant (WIPP) Site. These operations include the receipt, experimentation with, storage, and disposal of transuranic (TRU) wastes. This document describes the technical basis for the WIPP External Radiation Dosimetry Program. The purposes of this document are to: (1) provide assurance that the WIPP External Radiation Dosimetry Program is in compliance with all regulatory requirements, (2) provide assurance that the WIPP External Radiation Dosimetry Program is derived from a sound technical base, (3) serve as a technical reference for radiation protection personnel, and (4) aid in identifying and planning for future needs. The external radiation exposure fields are those that are documented in the WIPP Final Safety Analysis Report

QA experience at the University of Wisconsin accredited dosimetry calibration laboratory

Energy Technology Data Exchange (ETDEWEB)

DeWard, L.A.; Micka, J.A. [Univ. of Wisconsin, Madison, WI (United States)

1993-12-31

The University of Wisconsin Accredited Dosimetry Calibration Laboratory (UW ADCL) employs procedure manuals as part of its Quality Assurance (QA) program. One of these manuals covers the QA procedures and results for all of the UW ADCL measurement equipment. The QA procedures are divided into two main areas: QA for laboratory equipment and QA for external chambers sent for calibration. All internal laboratory equipment is checked and recalibrated on an annual basis, after establishing its consistency on a 6-month basis. QA for external instruments involves checking past calibration history as well as comparing to a range of calibration values for specific instrument models. Generally, the authors find that a chamber will have a variation of less than 0.5 % from previous Co-60 calibration factors, and falls within two standard deviations of previous calibrations. If x-ray calibrations are also performed, the energy response of the chamber is plotted and compared to previous instruments of the same model. These procedures give the authors confidence in the transfer of calibration values from National Institute of Standards and Technology (NIST).

QA experience at the University of Wisconsin accredited dosimetry calibration laboratory

International Nuclear Information System (INIS)

DeWard, L.A.; Micka, J.A.

1993-01-01

The University of Wisconsin Accredited Dosimetry Calibration Laboratory (UW ADCL) employs procedure manuals as part of its Quality Assurance (QA) program. One of these manuals covers the QA procedures and results for all of the UW ADCL measurement equipment. The QA procedures are divided into two main areas: QA for laboratory equipment and QA for external chambers sent for calibration. All internal laboratory equipment is checked and recalibrated on an annual basis, after establishing its consistency on a 6-month basis. QA for external instruments involves checking past calibration history as well as comparing to a range of calibration values for specific instrument models. Generally, the authors find that a chamber will have a variation of less than 0.5 % from previous Co-60 calibration factors, and falls within two standard deviations of previous calibrations. If x-ray calibrations are also performed, the energy response of the chamber is plotted and compared to previous instruments of the same model. These procedures give the authors confidence in the transfer of calibration values from National Institute of Standards and Technology (NIST)

Buried Waste Program (BWP) data qualification manual

International Nuclear Information System (INIS)

Casey, C.; Larson, R.A.; Harris, G.A.

1989-06-01

The Data Qualification Manual (DQM) has been developed to discuss the process required to qualify data generated for the Buried Waste Program (BWP). The data from the BWP tasks conducted at the Radioactive Waste Management Complex (RWMC) and elsewhere will lead to remedial decisions being made which are governed by federal regulations administered by the Environmental Protection Agency (EPA). Data qualification is the process of insuring that only data of planned and known qualities are used to make a decision or answer a question. Although it is the Data Integrity Review Committee's (DIRC) responsibility to insure that the quality of all BWP data is ultimately verified and validated, all personnel who participate in the data gathering process will affect the quality of the data and must be responsible for knowing what is required to produce data of the planned quality. Therefore this manual is addressed to all participants in a data-gathering task. This manual discusses requirements to support data qualification in several areas, including: the sampling and analysis plan; data quality objectives and PARCC goals; sample custody documentation; quality assurance; assembly of the data qualification package; and existing data. 23 refs., 4 figs., 6 tabs

Topics in radiation dosimetry radiation dosimetry

CERN Document Server

1972-01-01

Radiation Dosimetry, Supplement 1: Topics in Radiation Dosimetry covers instruments and techniques in dealing with special dosimetry problems. The book discusses thermoluminescence dosimetry in archeological dating; dosimetric applications of track etching; vacuum chambers of radiation measurement. The text also describes wall-less detectors in microdosimetry; dosimetry of low-energy X-rays; and the theory and general applicability of the gamma-ray theory of track effects to various systems. Dose equivalent determinations in neutron fields by means of moderator techniques; as well as developm

UMTRA Project-Level Cost Reduction/Productivity Improvement Program manual

International Nuclear Information System (INIS)

1995-06-01

Mission of the Uranium Mill Tailings Remedial Action (UMTRA) Project Cost Reduction/Productivity Improvement Program (CR/PIP) is to contribute to the UMTRA Project's environmental restoration mission by providing the means to achieve and recognize continuous improvements and cost savings. This manual includes program definition, description of UMTRA project organizational responsibilities and interfaces with existing project functions, guidance to contractors, and definition of project-level functions

Dosimetry of a gammabeam 650 60Co irradiator

International Nuclear Information System (INIS)

Escobedo, J.F.; Nascimento Filho, V.F.; Barros Ferraz, E.S. de

1980-01-01

Fricke and glass dosimetries allowed the determination of some basic irradiation of the γ source Gamma-beam 650, 29,080 Ci of 60 Co on April 1st., 1974 made by Atomic Energy of Canada Limited, in operation at CENA - Piracicaba, Sa o Paulo, Brazil. The number of radioactive capsules in each of the 12 exposure tubes, the uniformity of the activity related to each tube and the mean position of the set of capsules during exposition were determined. The exposure rate at the central point of the internal cavity relatively to the diameter formed by 12 active tubes, were experimentally determined by Fricke dosimetry. The results agreed with those indicated in the operation manual of the irradiator source. (Author) [pt

Setting-Up Of A Film Dosimetry System For High Energy Electron Beams And Development Of Computer Programs For Data Processing

International Nuclear Information System (INIS)

Schwob, N.; Schwob, W.; Loewenthal, E.

1999-01-01

Film dosimetry has the advantage over other dosimetry methods, of having a high spatial resolution and a fast two dimensional data acquisition. We have set up a system using a film digitizer with its associated software, dedicated to radiosurgery and we have developed data processing programs in Visual Basic for Excel. Data acquisition is not limited to water equivalent media: correction factors can be provided in the data processing procedure

Current internal-dosimetry practices at US Department of Energy facilities

International Nuclear Information System (INIS)

Traub, R.J.; Murphy, B.L.; Selby, J.M.; Vallario, E.J.

1985-04-01

The internal dosimetry practice at DOE facilities were characterized. The purpose was to determine the size of the facilities' internal dosimetry programs, the uniformity of the programs among the facilities, and the areas of greatest concern to health physicists in providing and reporting accurate estimates of internal radiation dose and in meeting proposed changes in internal dosimetry. The differences among the internal-dosimetry programs are related to the radioelements in use at each facility and, to some extent, the number of workers at each facility. The differences include different frequencies in the use of quality control samples, different minimum detection levels, different methods of recording radionuclides, different amounts of data recorded in the permanent record, and apparent differences in modeling the metabolism of radionuclides within the body. Recommendations for improving internal-dosimetry practices include studying the relationship between air-monitoring/survey readings and bioassay data, establishing uniform methods for recording bioassay results, developing more sensitive direct-bioassay procedures, establishing a mechanism for sharing information on internal-dosimetry procedures among DOE facilities, and developing mathematical models and interactive computer codes that can help quantify the uptake of radioactive materials and predict their distribution in the body. 19 refs., 8 tabs

Results from 2010 Caliban Criticality Dosimetry Intercomparison

Energy Technology Data Exchange (ETDEWEB)

Veinot, K. G.

2011-10-12

The external dosimetry program participated in a criticality dosimetry intercomparison conducted at the Caliban facility in Valduc, France in 2010. Representatives from the dosimetry and instrumentation groups were present during testing which included irradiations of whole-body beta/gamma (HBGT) and neutron thermoluminescent dosimeters (TLDs), a fixed nuclear accident dosimeter (FNAD), electronic alarming dosimeters, and a humanoid phantom filled with reference man concentrations of sodium. This report reviews the testing procedures, preparations, irradiations, and presents results of the tests.

Manual of dosimetry in radiotherapy. A practical guide for testing and calibrating equipment used in external beam treatments

International Nuclear Information System (INIS)

Massey, J.B.

1971-01-01

In order to achieve safe and efficient radiotherapy, one should respect a number of technical criteria, meaning that the irradiation facility should be adapted every time to the specific patient and the dose received by the patient should be fixed. If the radio therapist should decide about the characteristics of the treatment, he might not have the technical education needed to ensure that the applied devices are appropriate for obtaining the wanted results. This is the responsibility of the medical radio physicist. Unfortunately many countries lack qualified medical doctors experienced in radiotherapy. Although these countries can supply numerous hospitals with radiotherapeutic devices and x-ray sources they cannon make good use of them. That is why the IAEA, WHO and Pan-American Health Organization organised an experts team to study the problems of dosimetry in the radiotherapeutic centres. The objective of the present manual is to supply specialists in radiotherapy with practical instructions which will enable them to apply precise physical data on the irradiation volume and applied doses

Handbook for Classroom Testing in Peace Corps Language Programs. Manual T0068.

Science.gov (United States)

Anderson, Neil J.

This manual provides instructors in Peace Corps language training programs with information about two kinds of classroom testing: formative, ongoing testing and summative testing that occurs at the end of an instructional period. The first of the manual's four chapters on the purposes of language testing, discusses language testing within a…

The quality control program for an Ontario Hydro operated thermoluminescence dosimetry service at nuclear generating stations

International Nuclear Information System (INIS)

Orr, B.H.; Walsh, M.L.

1975-11-01

An essential aspect of the Ontario Hydro TLD service is the operation of an acceptable quality control (QC) program. The QC program which has been generally accepted by the A.E.C.B. is presented in this document. The aims of the program are as follows: (1) to ensure that Ontario Hydro maintains an acceptable standard of dosimetry; (2) to be able to demonstrate to any interested party that the dose measurements for individual workers have a high degree of credibility. (author)

Argentine intercomparison programme for personal dosimetry

International Nuclear Information System (INIS)

Gregori, B.N.; Papadopulos, S.B.; Cruzate, J.; Kunst, J.J.; Saravi, M.

2005-01-01

Full text: In 1997 began in Argentine, sponsored by Nuclear Regulatory Authority (ARN) the intercomparison program for personal dosimetry laboratories, on a voluntary basis. Up to know 6 exercises have been done. The program began with a workshop to present the quantities, personal dose equivalent, Hp(10) and extremities dose equivalent, Hs(d). The first aim of this program was to know the true sate of personal dosimetry laboratories in the country, and then introduce the personal dose equivalent, Hp(10) into the dose measurements. The Regional Reference Center for Dosimetry (CCR), belonging to CNEA and the Physical Dosimetry Laboratory of ARN performed the irradiation. Those were done air free and on ICRU phantom, using x-ray, quality ISO: W60, W110 and W200; and 137 Cs and 60 Co gamma rays. The irradiation was made following ISO 4037 (2) recommendations. There are studied the dose, energy and angular response of the different measuring system. The range of the dose analyzed was from 0.2 mSv up to 80 mSv. The beam incidence was normal and also 20 o and 60 o . The dosimeters irradiation's were performed kerma in free in air and in phantom in order to study the availability of the service to evaluate the behavior as a function of kerma free in air or Hp(10). At the same time several items have been asked to each participant referring to the action range, the detectors characteristics, the laboratory procedures, the existence of an algorithm and its use for the dosimeter evaluation and the wish to participate in a quality assurance program. The program worked in writing a standard of personal dosimetry laboratories, that was published in 2001. In this work the results of each laboratory and its performance based on the ICRP-60 and ICRP-35 acceptance criteria are shown. Also the laboratory evolution and inquiry analyses have been included. (author)

Proceedings of the third conference on radiation protection and dosimetry

Energy Technology Data Exchange (ETDEWEB)

Swaja, R.E.; Sims, C.S.; Casson, W.H. [eds.

1991-10-01

The Third Conference on Radiation Protection and Dosimetry was held during October 21--24, 1991, at the Sheraton Plaza Hotel in Orlando, Florida. This meeting was designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection, and providing them with sufficient information to evaluate their programs. To meet these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection was prepared. General topics considered in the technical session included external dosimetry, internal dosimetry, instruments, accident dosimetry, regulations and standards, research advances, and applied program experience. In addition, special sessions were held to afford attendees the opportunity to make short presentations of recent work or to discuss topics of general interest. Individual reports are processed separately on the database.

Proceedings of the third conference on radiation protection and dosimetry

International Nuclear Information System (INIS)

Swaja, R.E.; Sims, C.S.; Casson, W.H.

1991-10-01

The Third Conference on Radiation Protection and Dosimetry was held during October 21--24, 1991, at the Sheraton Plaza Hotel in Orlando, Florida. This meeting was designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection, and providing them with sufficient information to evaluate their programs. To meet these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection was prepared. General topics considered in the technical session included external dosimetry, internal dosimetry, instruments, accident dosimetry, regulations and standards, research advances, and applied program experience. In addition, special sessions were held to afford attendees the opportunity to make short presentations of recent work or to discuss topics of general interest. Individual reports are processed separately on the database

Technical basis document for internal dosimetry

International Nuclear Information System (INIS)

Hickman, D.P.

1991-01-01

This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosimetry program in accordance with expected Department of Energy Laboratory Accreditation Program (DOELAP) requirements for the selected radionuclides provided in this document, including uranium mill tailing mixtures. Additions and modifications to this document and procedures derived FR-om this document are expected in the future according to changes in standards and changes in programmatic mission

Area Monitoring Dosimeter Program for the Pacific Northwest National Laboratory: Results for CY 2000

International Nuclear Information System (INIS)

Bivins, Steven R; Stoetzel, Gregory A

2001-01-01

Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the Department of Energy (DOE) Radiological Control Manual (RCM) in January 1993. This program is to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a) (1)-(4) and Article 511.1 of the DOE Standard Radiological Control, personnel dosimetry shall be provided to (1) radiological workers who are likely to receive at least 100 mrem annually, and (2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years 1993-2000 confirm that personnel dosimetry is not needed for individuals located in areas monitored by the program

In vivo dosimetry: measurement of entrance and exit dose using MOSFET dosimeter

International Nuclear Information System (INIS)

Gopiraj, A.; Billimagga, Ramesh S.; Rekha, M.; Ramasubramaniam, V.

2007-01-01

Patient dose verification is an essential part of a Quality Assurance (QA) program in a Radiotherapy Department. As the transition is made from the conventional two-dimensional (2D) to three-dimensional (3D) conformal and intensity modulated therapy, it is recommended that new treatment techniques be checked systematically to guarantee accurate dose delivery by means of a comprehensive in vivo dosimetry program (i.e. real-time dosimetry during patient treatment). The authors conducted a study to assess the clinical utility of in vivo dosimetry in the Dept. of Radiation Oncology using MOSFET dosimetry system

Mathematical operations in cytogenetic dosimetry: Dosgen

International Nuclear Information System (INIS)

Garcia L, O.; Zequera J, T.

1996-01-01

Handling of formulas and mathematical procedures for fitting and using of dose-response relationships in cytogenetic dosimetry is often difficulted by the absence of collaborators specialized in mathematics and computation. DOSGEN program contains the main mathematical operations which are used in cytogenetic dosimetry. It is able to run in IBM compatible Pc's by non-specialized personnel.The program possibilities are: Poisson distribution fitting test for the number of aberration per cell, dose assessment for whole body irradiation, dose assessment for partial irradiation and determination of irradiated fraction. The program allows on screen visualization and printing of results. DOSGEN has been developed in turbo pascal and is 33Kb of size. (authors). 4 refs

Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies

International Nuclear Information System (INIS)

2011-01-01

Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade.

Region 8 radiological assistance program team response manual

International Nuclear Information System (INIS)

Webb, D.E.

1997-01-01

The purpose of this manual is to provide guidance so that a request for radiological assistance is responded to in an effective and consistent manner. These procedures are specific to the trained and qualified members of the Region 8 Radiological Assistance Program (RAP) team. Procedures provide steps for responding to the request, notification and activation of the team members, position descriptions, and checklists

Dosimetry. Standard practice for dosimetry in gamma irradiation facilities for food and non-food processing

International Nuclear Information System (INIS)

2008-01-01

This Ghana Standard outlines the installation qualification program for an irradiator and the dosimetry procedures to be followed during operational qualification, performance qualification and routine processing in facilities that process food and non-food with gamma rays. This is to ensure that the product has been treated with predetermined range of absorbed dose. It is not intended for use in X-ray and electron beam facilities and therefore dosimetry systems in such facilities are not covered

ELESTRES.M11K program users'manual and description

International Nuclear Information System (INIS)

Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

1992-12-01

ELESTRES.M11K is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computers the one-dimensional temperature distribution and thermal expansion of the fuel pellets, and computes two-dimensional pellet deformation using FEM. The amount of fission gas released and sheath strain/stress are also computed. This document is intended as a users' manual and description for ELESTRES.M11K program. (Author)

In vivo dosimetry in radiation therapy in Sweden

International Nuclear Information System (INIS)

Eriksson, Jacob; Blomquist, Michael

2010-07-01

A prerequisite for achieving high radiation safety for patients receiving external beam radiation therapy is that the hospitals have a quality assurance program. The program should include include monitoring of the radiation dose given to the patient. Control measurements are performed both at the system level and at the individual level. Control measurement is normally performed using in vivo dosimetry, e.g. a method to measure the radiation dose at the individual level during the actual radiation treatment time. In vivo dosimetry has proven to be an important tool to detect and prevent serious errors in patient treatment. The purpose of this research project was to identify the extent to which vivo dosimetry is used and the methods available for this at Swedish radiation therapy clinics. The authority also wanted to get an overall picture of how hospitals manage results of in vivo dosimetry, and how clinics control radiation dose when using modern treatment techniques. The report reflects the situation in Swedish radiotherapy clinics 2007. The report shows that all hospitals use some form of in vivo dosimetry. The instruments used are mainly diodes and termoluminiscence dosimeters

Relationship between student selection criteria and learner success for medical dosimetry students

International Nuclear Information System (INIS)

Baker, Jamie; Tucker, Debra; Raynes, Edilberto; Aitken, Florence; Allen, Pamela

2016-01-01

Medical dosimetry education occupies a specialized branch of allied health higher education. Noted international shortages of health care workers, reduced university funding, limitations on faculty staffing, trends in learner attrition, and increased enrollment of nontraditional students force medical dosimetry educational leadership to reevaluate current admission practices. Program officials wish to select medical dosimetry students with the best chances of successful graduation. The purpose of the quantitative ex post facto correlation study was to investigate the relationship between applicant characteristics (cumulative undergraduate grade point average (GPA), science grade point average (SGPA), prior experience as a radiation therapist, and previous academic degrees) and the successful completion of a medical dosimetry program, as measured by graduation. A key finding from the quantitative study was the statistically significant positive correlation between a student's previous degree and his or her successful graduation from the medical dosimetry program. Future research investigations could include a larger research sample, representative of more medical dosimetry student populations, and additional studies concerning the relationship of previous work as a radiation therapist and the effect on success as a medical dosimetry student. Based on the quantitative correlation analysis, medical dosimetry leadership on admissions committees could revise student selection rubrics to place less emphasis on an applicant's undergraduate cumulative GPA and increase the weight assigned to previous degrees.

Relationship between student selection criteria and learner success for medical dosimetry students

Energy Technology Data Exchange (ETDEWEB)

Baker, Jamie, E-mail: jabaker@mdanderson.org [Medical Dosimetry Program, School of Health Professions, The University of Texas MD Anderson Cancer Center School of Health Professions, Houston, TX (United States); Tucker, Debra [Arizona State University, Phoenix, AZ (United States); Raynes, Edilberto [University of Phoenix, Phoenix, AZ (United States); Aitken, Florence [University of Nevada, Las Vegas, NV (United States); Allen, Pamela [Department of Radiation Oncology, The University of Texas MD Anderson Cancer Center, Houston, TX (United States)

2016-04-01

Medical dosimetry education occupies a specialized branch of allied health higher education. Noted international shortages of health care workers, reduced university funding, limitations on faculty staffing, trends in learner attrition, and increased enrollment of nontraditional students force medical dosimetry educational leadership to reevaluate current admission practices. Program officials wish to select medical dosimetry students with the best chances of successful graduation. The purpose of the quantitative ex post facto correlation study was to investigate the relationship between applicant characteristics (cumulative undergraduate grade point average (GPA), science grade point average (SGPA), prior experience as a radiation therapist, and previous academic degrees) and the successful completion of a medical dosimetry program, as measured by graduation. A key finding from the quantitative study was the statistically significant positive correlation between a student's previous degree and his or her successful graduation from the medical dosimetry program. Future research investigations could include a larger research sample, representative of more medical dosimetry student populations, and additional studies concerning the relationship of previous work as a radiation therapist and the effect on success as a medical dosimetry student. Based on the quantitative correlation analysis, medical dosimetry leadership on admissions committees could revise student selection rubrics to place less emphasis on an applicant's undergraduate cumulative GPA and increase the weight assigned to previous degrees.

Individual dosimetry and calibration

International Nuclear Information System (INIS)

Otto, T.

1997-01-01

In 1996, the Dosimetry and Calibration Section was, as in previous years, mainly engaged in routine tasks: the distribution of over 6000 dosimeters (with a total of more than 10,000 films) every two months and the calibration of about 900 fixed and mobile instruments used in the radiation survey sections of RP group. These tasks were, thanks to an experienced team, well mastered. Special efforts had to be made in a number of areas to modernize the service or to keep it in line with new prescriptions. The Individual Dosimetry Service had to assure that CERN's contracting firms comply with the prescriptions in the Radiation Safety Manual (1996) that had been inspired by the Swiss Ordinance of 1994: Companies must file for authorizations with the Swiss Federal Office for Public Health requiring that in every company an 'Expert in Radiation Protection' be nominated and subsequently trained. CERN's Individual Dosimetry Service is accredited by the Swiss Federal Authorities and works closely together with other, similar services on a rigorous quality assurance programme. Within this framework, CERN was mandated to organize this year the annual Swiss 'Intercomparison of Dosimeters'. All ten accredited dosimetry services - among others those of the Paul Scherrer Institute (PSI) in Villigen and of the four Swiss nuclear power stations - sent dosimeters to CERN, where they were irradiated in CERN's calibration facility with precise photon doses. After return to their origin they were processed and evaluated. The results were communicated to CERN and were compared with the originally given doses. A report on the results was subsequently prepared and submitted to the Swiss 'Group of Experts on Personal Dosimetry'. Reference monitors for photon and neutron radiation were brought to standard laboratories to assure the traceability of CERN's calibration service to the fundamental quantities. For photon radiation, a set of ionization chambers was calibrated in the reference field

Effective use of metrics in an ALARA program

International Nuclear Information System (INIS)

Bates, B.B. Jr.

1996-01-01

ALARA radiological protection programs require metrics to meet their objectives. Sources of metrics include; external dosimetry; internal dosimetry; radiological occurrences from the occurrence reporting and processing system (ORPS); and radiological incident reports (RIR). The sources themselves contain an abundance of specific ''indicators''. To choose the site-specific indicators that will be tracked and trended requires careful review. This required the end users to expend valuable time and effort to locate the data they needed. To address this problem, a central metrics database has been developed so that customers can have all their questions addressed quickly and correctly. The database was developed in the beginning to answer some of the customer's most frequently asked questions. It is now also a tool to communicate the status of the radiation protection program to facility managers. Finally it also addresses requirements contained in the Rad Con manual and the 10CFR835 implementation guides. The database uses currently available, ''user friendly'', software and contains information from RIR's, ORPS, and external dosimetry records specific to ALARA performance indicators. The database is expandable to allow new metrics input. Specific reports have been developed to assist customers in their tracking and trending of ALARA metrics

A Manual for the Anchorage School District Bilingual Education Program Revised Scope and Sequence, K-3.

Science.gov (United States)

Heinrich, Maria Nieves Bumanlag Lilagan

The manual offers a systematic set of procedures and relevant information to facilitate effective use of the Anchorage school district (ASD) bilingual education program (BEP). The historical background of the program's development is presented, available manuals for teaching English to limited English proficiency (LEP) students and related…

Report on high energy neutron dosimetry workshop

International Nuclear Information System (INIS)

Alvar, K.R.; Gavron, A.

1993-01-01

The workshop was called to assess the performance of neutron dosimetry per the responses from ten DOE accelerator facilities to an Office of Energy Research questionnaire regarding implementation of a personnel dosimetry requirement in DRAFT DOE 5480.ACC, ''Safety of Accelerator Facilities''. The goals of the workshop were to assess the state of dosimetry at high energy accelerators and if such dosimetry requires improvement, to reach consensus on how to proceed with such improvements. There were 22 attendees, from DOE Programs and contract facilities, DOE, Office of Energy Research (ER), Office of Environmental Safety and Health (EH), Office of Fusion Energy, and the DOE high energy accelerator facilities. A list of attendees and the meeting agenda are attached. Copies of the presentations are also attached

Reading Roundup: Rope a Good Book. Louisiana Summer Reading Program, 1995 Manual.

Science.gov (United States)

White, Dorothy, J., Ed.

A manual for the Louisiana Summer Reading Program is presented in 14 sections with a western theme and illustrations. An evaluation form, a 1995 calendar, and a list of audiovisual materials with addresses and prices are also provided. Section 1 discusses promotion, publicity, and programs; and includes sample news releases; program ideas, and…

Neutron dosimetry program at Mound - problems and solutions

International Nuclear Information System (INIS)

Winegardner, M.K.

1991-01-01

The Mound personnel neutron dosimetry program utilizes TLD albedo technology. The neutron dosimeter design incorporates a two-element spectrometer for site-specific neutron quality determination and empirical application of field neutron calibration factors. Design elements feature two Li(6)F (TLD- 600) chips for neutron detection and one Li(7)F (TLD-700) chip for gamma compensation of the TLD- 600 chips. One TLD-600 chip is Cadmium shielded on the front side of the dosimeter, the other is Cadmium shielded from the back side. Tin filters are placed opposite of the Cadmium shield on each of the TLD-600 chips and on both sides of the TLD-700 chip for symmetrically equivalent gamma absorption characteristics. Neutron quality determination is accomplished by the albedo neutron-to- incident thermal neutron response ratio above the Cadmium cutoff. This front Cadmium shielded-to-back Cadmium shielded response ratio, compensated for the presence of gamma radiation, provides the basis for neutron energy calibration via the albedo response curve

Relationship between student selection criteria and learner success for medical dosimetry students.

Science.gov (United States)

Baker, Jamie; Tucker, Debra; Raynes, Edilberto; Aitken, Florence; Allen, Pamela

2016-01-01

Medical dosimetry education occupies a specialized branch of allied health higher education. Noted international shortages of health care workers, reduced university funding, limitations on faculty staffing, trends in learner attrition, and increased enrollment of nontraditional students force medical dosimetry educational leadership to reevaluate current admission practices. Program officials wish to select medical dosimetry students with the best chances of successful graduation. The purpose of the quantitative ex post facto correlation study was to investigate the relationship between applicant characteristics (cumulative undergraduate grade point average (GPA), science grade point average (SGPA), prior experience as a radiation therapist, and previous academic degrees) and the successful completion of a medical dosimetry program, as measured by graduation. A key finding from the quantitative study was the statistically significant positive correlation between a student׳s previous degree and his or her successful graduation from the medical dosimetry program. Future research investigations could include a larger research sample, representative of more medical dosimetry student populations, and additional studies concerning the relationship of previous work as a radiation therapist and the effect on success as a medical dosimetry student. Based on the quantitative correlation analysis, medical dosimetry leadership on admissions committees could revise student selection rubrics to place less emphasis on an applicant׳s undergraduate cumulative GPA and increase the weight assigned to previous degrees. Copyright © 2016 American Association of Medical Dosimetrists. Published by Elsevier Inc. All rights reserved.

Cross sections required for FMIT dosimetry

International Nuclear Information System (INIS)

Gold, R.; McElroy, W.N.; Lippincott, E.P.; Mann, F.M.; Oberg, D.L.; Roberts, J.H.; Ruddy, F.H.

1980-01-01

The Fusion Materials Irradiation Test (FMIT) facility, currently under construction, is designed to produce a high flux of high energy neutrons for irradiation effects experiments on fusion reactor materials. Characterization of the flux-fluence-spectrum in this rapidly varying neutron field requires adaptation and extension of currently available dosimetry techniques. This characterization will be carried out by a combination of active, passive, and calculational dosimetry. The goal is to provide the experimenter with accurate neutron flux-fluence-spectra at all positions in the test cell. Plans have been completed for a number of experimental dosimetry stations and provision for these facilities has been incorporated into the FMIT design. Overall needs of the FMIT irradiation damage program delineate goal accuracies for dosimetry that, in turn, create new requirements for high energy neutron cross section data. Recommendations based on these needs have been derived for required cross section data and accuracies

KAFEPA-II program users' manual and description

International Nuclear Information System (INIS)

Suk, H. C.; Hwang, W.; Kim, B. G.; Sim, K. S.; Heo, Y. H.; Byun, T. S.; Park, G. S.

1992-04-01

KAFEPA-II is a computer program for simulating the behaviour of UO 2 fuel elements under normal operating conditions of a CANDU reactor. It computes the one-dimensional temperature distribution and thermal expansion of the fuel pellets. The amount of gas released during irradiation of the fuel is also computed. Thermal expansion and gas pressure inside the fuel element are then used to compute the strains and stresses in the sheath. This document is intended as a user's manual and description for KAFEPA-II. (Author)

Chemical dosimetry principles in high dose dosimetry

International Nuclear Information System (INIS)

Mhatre, Sachin G.V.

2016-01-01

In radiation processing, activities of principal concern are process validation and process control. The objective of such formalized procedures is to establish documentary evidence that the irradiation process has achieved the desired results. The key element of such activities is inevitably a well characterized reliable dosimetry system that is traceable to recognized national and international dosimetry standards. Only such dosimetry systems can help establish the required documentary evidence. In addition, industrial radiation processing such as irradiation of foodstuffs and sterilization of health careproducts are both highly regulated, in particular with regard to dose. Besides, dosimetry is necessary for scaling up processes from the research level to the industrial level. Thus, accurate dosimetry is indispensable

User's Manual for SPECTROM-41: a Finite-Element Heat Transfer Program

International Nuclear Information System (INIS)

Svalstad, D.K.

1983-06-01

This User's Manual addresses SPECTROM-41: A Finite Element Heat Transfer Computer Program. The user is introduced to the program's capabilities and operation, with required user input outlined in detail. Example problems are included to illustrate the use of the various program features, and included to illustrate the use of the various program features, and analytical solutions are presented for four of the examples to provide a measure of program accuracy. Past and ongoing comparative benchmark analyses are highlighted to provide the user with an indication of how SPECTROM-41 predictions compare with other available heat transfer programs

Viscous wing theory development. Volume 2: GRUMWING computer program user's manual

Science.gov (United States)

Chow, R. R.; Ogilvie, P. L.

1986-01-01

This report is a user's manual which describes the operation of the computer program, GRUMWING. The program computes the viscous transonic flow over three-dimensional wings using a boundary layer type viscid-inviscid interaction approach. The inviscid solution is obtained by an approximate factorization (AFZ)method for the full potential equation. The boundary layer solution is based on integral entrainment methods.

Manual of program operation for data analysis from radiometer system

International Nuclear Information System (INIS)

Silva Mello, L.A.R. da; Migliora, C.G.S.

1987-12-01

This manual describes how to use the software to retrieve and analyse data from radiometer systems and raingauges used in the 12 GHz PROPAGATION MEASUREMENTS/CANADA - TELEBRAS COOPERATION PROGRAM. The data retrieval and analisys is being carried out by CETUC, as part of the activities of the project Simulacao de Enlaces Satelite (SES). The software for these tasks has been supplied by the Canadian Research Centre (CRC), together with the measurement equipment. The two following sections describe the use of the data retrieval routines and the data analysis routines of program ATTEN. Also, a quick reference guide for commands that can be used when a microcomputer is local or remotely connected to a radiometer indoor unit is included as a last section. A more detailed description of these commands, their objectives and cautions that should de taken when using them can be found in the manual ''12 GHz Propagation Measurements System - Volume 1 - Dual Slope Radiometer and Data Aquisition System'', supplied by Diversitel Communications Inc. (author) [pt

100 years of solid state dosimetry and radiation protection dosimetry

International Nuclear Information System (INIS)

Bartlett, David T.

2008-01-01

The use of solid state detectors in radiation dosimetry has passed its 100th anniversary. The major applications of these detectors in radiation dosimetry have been in personal dosimetry, retrospective dosimetry, dating, medical dosimetry, the characterization of radiation fields, and also in microdosimetry and radiobiology research. In this introductory paper for the 15th International Conference, I shall speak of the history of solid state dosimetry and of the radiation measurement quantities that developed at the same time, mention some landmark developments in detectors and applications, speak a bit more about dosimetry and measurement quantities, and briefly look at the past and future

First intercomparison exercise in the frame of the coordinated investigation program of the IAEA on regional intercomparison of personal dosimetry

International Nuclear Information System (INIS)

Massera, G.; Papadopulos, S.B.; Gregori, B.N.; DaSilva, T.; Griffith, R.; )

1998-01-01

During the days 7 and 11 of October of 1996 took place in Buenos Aires, Argentina, the first Meeting of the Coordinated Investigation program of the IAEA on Regional Intercomparison of Personal Dosimetry for Latin American. In this meeting participated nine representatives of reference laboratories and of personal dosimetry of the region. Fundamental aspect of personal dosimetry relates with the quantity personal dose equivalent Hp application and the implementation of intercomparison exercise in order to improve the quality of the dose estimation have been discussed. Also lectures carried out by the specialist on Hp and practical aspects of it implementation; answer and calibration according to the ISO 4037; intercomparison methods: procedures and organizations. It was carried out the first intercomparison exercise where the participants collaborated in the preparations and irradiations of personal dosemeters they have brought. (author)

Survey Procedures Manual for the Environmental Survey and Site Assessment Program (ESSAP). Revision 10

International Nuclear Information System (INIS)

2000-01-01

The Environmental Survey and Site Assessment Program (ESSAP) of the Oak Ridge Institute for Science and Education (ORISE) conducts radiological survey activities under a contract with the U. S. Department of Energy (DOE) and for the U.S. Nuclear Regulatory Commission (NRC). ORISE and its programs are operated by Oak Ridge Associated Universities (ORAU) through a contract with DOE. The purpose of this Procedures Manual is to provide a standardized set of procedures that document activities of the program in an auditable manner. These procedures are applicable to both DOE and NRC operations. Procedures presented in this manual are limited to those associated with site survey activities

Advances on radiation protection dosimetry research, development and services at AEOI

International Nuclear Information System (INIS)

Sohrabi, M.

1993-01-01

Radiation dosimetry is the main counterpart of an effective national radiation protection program to protect radiation workers, public and the environment against harmful effects of radiation. Research and development on radiation dosimetry are of vital needs to support national dosimetry services. The National Radiation Protection Department (NRPD) of the Atomic Energy Organization of Iran (AEOI) being a National Authority on radiation protection is also responsible for radiation dosimetry research, development and services. Some highlights of such activities at NRPD are reviewed and discussed

Nuclear medicine. 1 part. Manual

International Nuclear Information System (INIS)

Shlygina, O.E.; Borisenko, A.R.

2006-01-01

Current manual is urged to give wide-scale readers a submission on a key principles and methods of nuclear medicine, and it opportunities and restrictions in diagnostics and treatment of different diseases. Nuclear medicine is differing first of all by combination of diverse knowledge fields: special knowledge of a doctor, knowledge of physical processes bases, related with radiation, grounds of radiopharmaceutics, dosimetry. In the base of the book the 5th edition of 'Nuclear medicine' manual in 2 parts of German authors - Schicha, G.; Schober, O. is applied. In the book publishing the stuff of the Institute of Nuclear Physics of the National Nuclear Center of Republic of Kazakhstan has been worked. Modifications undergo practically all chapters: especially the second one, forth and sixth was enlarged. The 1 part of the book was published due to support of IAEA within the Technical cooperation project 'Implementation of Nuclear Medicine and Biophysics Center' (KAZ/6/007). The manual second part - devoted to applications of nuclear medicine methods for diagnostics and treatment - will be published in 2007

Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (Spanish Edition)

International Nuclear Information System (INIS)

2014-01-01

Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual’s working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (Arabic Edition)

International Nuclear Information System (INIS)

2014-01-01

Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (Russian Edition)

International Nuclear Information System (INIS)

2014-01-01

Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (Chinese Edition)

International Nuclear Information System (INIS)

2015-01-01

Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

Cytogenetic Dosimetry: Applications in Preparedness for and Response to Radiation Emergencies (French Edition)

International Nuclear Information System (INIS)

2013-01-01

Cytogenetic dosimetry is recognized as a valuable dose assessment method which fills a gap in dosimetric technology, particularly when there are difficulties in interpreting the data, in cases where there is reason to believe that persons not wearing dosimeters have been exposed to radiation, in cases of claims for compensation for radiation injuries that are not supported by unequivocal dosimetric evidence, or in cases of exposure over an individual's working lifetime. The IAEA has maintained a long standing involvement in biological dosimetry commencing in 1978. This association has been through a sequence of coordinated research programmes (CRPs), the running of regional and national training courses, the sponsorship of individual training fellowships, and the provision of equipment to laboratories in Member States, establishing capabilities in biological dosimetry. From this has arisen the provision to Member States of advice regarding the best focus for research and suggestions for the most suitable techniques for future practice in biological dosimetry. One CRP resulted in the publication in 1986 of a manual, entitled Biological Dosimetry: Chromosomal Aberration Analysis for Dose Assessment (Technical Reports Series No. 260). This was superseded in 2001 by a revised second edition, Technical Reports Series No. 405. This present publication constitutes a third edition, with extensive updating to reflect the considerable advances that have been made in cytogenetic biological dosimetry during the past decade

Field manual for ground water reconnaissance. Savannah River Laboratory National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Ferguson, R.B.; Price, V.; Baucom, E.I.

1977-01-01

A manual is presented that is intended to direct and coordinate field operations, site selection, groundwater sample collection, and information codes for the Savannah River Laboratory (SRL) contribution to the National Uranium Resource Evaluation (NURE) program. The manual provides public relations information for field sampling teams as well as technical direction

Manualization of Occupational Therapy Interventions: Illustrations from the Pressure Ulcer Prevention Research Program

Science.gov (United States)

Blanche, Erna Imperatore; Fogelberg, Donald; Diaz, Jesus; Carlson, Mike; Clark, Florence

2011-01-01

The manualization of a complex occupational therapy intervention is a crucial step in ensuring treatment fidelity for both clinical application and research purposes. Towards this latter end, intervention manuals are essential for assuring trustworthiness and replicability of randomized controlled trials (RCT’s) that aim to provide evidence of the effectiveness of occupational therapy. In this paper, literature on the process of intervention manualization is reviewed. The prescribed steps are then illustrated through our experience in implementing the University of Southern California/Rancho Los Amigos National Rehabilitation Center’s collaborative Pressure Ulcer Prevention Project (PUPP). In this research program, qualitative research provided the initial foundation for manualization of a multifaceted occupational therapy intervention designed to reduce incidence of medically serious pressure ulcers in people with SCI. PMID:22214116

Highway Safety Program Manual: Volume 8: Alcohol in Relation to Highway Safety.

Science.gov (United States)

National Highway Traffic Safety Administration (DOT), Washington, DC.

Volume 8 of the 19-volume Highway Safety Program Manual (which provides guidance to State and local governments on preferred highway safety practices) concentrates on alcohol in relation to highway safety. The purpose and objectives of the alcohol program are outlined. Federal authority in the area of highway safety and general policies regarding…

DIMAC program user's manual

International Nuclear Information System (INIS)

Lee, Byoung Oon; Song, Tae Young

2003-11-01

DIMAC (A DIspersion Metallic fuel performance Analysis Code) is a computer program for simulating the behavior of dispersion fuel rods under normal operating conditions of HYPER. It computes the one-dimensional temperature distribution and the thermo-mechanical characteristics of fuel rod under the steady state operation condition, including the swelling and rod deformation. DIMAC was developed based on the experience of research reactor fuel. DIMAC consists of the temperature calculation module, the mechanical swelling calculation module, and the fuel deformation calculation module in order to predict the deformation of a dispersion fuel as a function of power history. Because there are a little of available U-TRU-Zr or TRU-Zr characteristics, the material data of U-Pu-Zr or Pu-Zr are used for those of U-TRU-Zr or TRU-Zr. This report is mainly intended as a user's manual for the DIMAC code. The general description on this code, the description on input parameter, the description on each subroutine, the sample problem and the sample input and partial output are written in this report

DIMAC program user's manual

Energy Technology Data Exchange (ETDEWEB)

Lee, Byoung Oon; Song, Tae Young

2003-11-01

DIMAC (A DIspersion Metallic fuel performance Analysis Code) is a computer program for simulating the behavior of dispersion fuel rods under normal operating conditions of HYPER. It computes the one-dimensional temperature distribution and the thermo-mechanical characteristics of fuel rod under the steady state operation condition, including the swelling and rod deformation. DIMAC was developed based on the experience of research reactor fuel. DIMAC consists of the temperature calculation module, the mechanical swelling calculation module, and the fuel deformation calculation module in order to predict the deformation of a dispersion fuel as a function of power history. Because there are a little of available U-TRU-Zr or TRU-Zr characteristics, the material data of U-Pu-Zr or Pu-Zr are used for those of U-TRU-Zr or TRU-Zr. This report is mainly intended as a user's manual for the DIMAC code. The general description on this code, the description on input parameter, the description on each subroutine, the sample problem and the sample input and partial output are written in this repo0008.

A quality assurance programme for radiation therapy dosimetry: Report of a consultants' meeting to review the status and to plant the development

International Nuclear Information System (INIS)

Izewska, J.; Andreo, P.

1996-01-01

Four national External Audit Groups (EAG) in charge of operating quality audits for radiotherapy dosimetry have been created through a Co-ordinated Research Programme ''Development of a Quality Assurance Programme for Radiation Therapy Dosimetry in Developing Countries'' (E2-40-07). The present status of the development of the measuring systems and measuring procedures for the EAGs has been compared to the methodology established by Quality Audit Networks operating at present in Europe. To harmonize different EAG procedures, a document entitled ''Guidelines to prepare a Quality Manual for External Audit Groups on Dosimetry in Radiotherapy '' has been outlined and a first draft prepared. The ''Guidelines...'' covers quality policy, quality systems and quality structures including process control following the recommendations of ISO 9000 series and ISO/IEC guide No. 25. When completed, this document can be used as a guide on how to prepare the quality manual for national EAGs in developing countries. Due to increased interest in the project three new participants have been admitted. (author)

Field manual for stream sediment reconnaissance. Savannah River Laboratory National Uranium Resource Evaluation Program

International Nuclear Information System (INIS)

Ferguson, R.B.; Price, V.; Baucom, E.I.

1976-07-01

A manual is presented that is intended to direct and coordinate field operations, site selection, stream sediment sample collection, water sample collection, and information codes for the Savannah River Laboratory (SRL) contribution to the National Uranium Resource Evaluation (NURE) program. The manual provides public relations information for field sampling teams as well as technical direction

Proceedings of the second conference on radiation protection and dosimetry

International Nuclear Information System (INIS)

Swaja, R.E.; Sims, C.S.

1988-11-01

The Second Conference on Radiation Protection and Dosimetry was held during October 31--November 3, 1988, at the Holiday Inn, Crowne Plaza Hotel in Orlando, Florida. This meeting was designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection and providing them with sufficient information to evaluate their programs. To facilitate meeting these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection was prepared. General topics considered in the technical sessions included external dosimetry, internal dosimetry, calibration, standards and regulations, instrumentation, accreditation and test programs, research advances, and applied program experience. In addition, special sessions were held to afford attendees the opportunity to make short presentations of recent work or to discuss topics of general interest. This document provides a summary of the conference technical program and a partial collection of full papers for the oral presentations in order of delivery. Individual papers were processed separately for the data base

Proceedings of the second conference on radiation protection and dosimetry

Energy Technology Data Exchange (ETDEWEB)

Swaja, R. E.; Sims, C. S. [eds.

1988-11-01

The Second Conference on Radiation Protection and Dosimetry was held during October 31--November 3, 1988, at the Holiday Inn, Crowne Plaza Hotel in Orlando, Florida. This meeting was designed with the objectives of promoting communication among applied, research, regulatory, and standards personnel involved in radiation protection and providing them with sufficient information to evaluate their programs. To facilitate meeting these objectives, a technical program consisting of more than 75 invited and contributed oral presentations encompassing all aspects of radiation protection was prepared. General topics considered in the technical sessions included external dosimetry, internal dosimetry, calibration, standards and regulations, instrumentation, accreditation and test programs, research advances, and applied program experience. In addition, special sessions were held to afford attendees the opportunity to make short presentations of recent work or to discuss topics of general interest. This document provides a summary of the conference technical program and a partial collection of full papers for the oral presentations in order of delivery. Individual papers were processed separately for the data base.

NV/YMP radiological control manual, Revision 2

International Nuclear Information System (INIS)

Gile, A.L.

1996-11-01

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations

NV/YMP radiological control manual, Revision 2

Energy Technology Data Exchange (ETDEWEB)

Gile, A.L. [comp.

1996-11-01

The Nevada Test Site (NTS) and the adjacent Yucca Mountain Project (YMP) are located in Nye County, Nevada. The NTS has been the primary location for testing nuclear explosives in the continental US since 1951. Current activities include operating low-level radioactive and mixed waste disposal facilities for US defense-generated waste, assembly/disassembly of special experiments, surface cleanup and site characterization of contaminated land areas, and non-nuclear test operations such as controlled spills of hazardous materials at the hazardous Materials (HAZMAT) Spill Center (HSC). Currently, the major potential for occupational radiation exposure is associated with the burial of low-level nuclear waste and the handling of radioactive sources. Planned future remediation of contaminated land areas may also result in radiological exposures. The NV/YMP Radiological Control Manual, Revision 2, represents DOE-accepted guidelines and best practices for implementing Nevada Test Site and Yucca Mountain Project Radiation Protection Programs in accordance with the requirements of Title 10 Code of Federal Regulations Part 835, Occupational Radiation Protection. These programs provide protection for approximately 3,000 employees and visitors annually and include coverage for the on-site activities for both personnel and the environment. The personnel protection effort includes a DOE Laboratory Accreditation Program accredited dosimetry and personnel bioassay programs including in-vivo counting, routine workplace air sampling, personnel monitoring, and programmatic and job-specific As Low as Reasonably Achievable considerations.

Dosimetry

International Nuclear Information System (INIS)

Anon.

1990-01-01

The purpose of ionizing radiation dosimetry is the measurement of the physical and biological consequences of exposure to radiation. As these consequences are proportional to the local absorption of energy, the dosimetry of ionizing radiation is based on the measurement of this quantity. Owing to the size of the effects of ionizing radiation on materials in all of these area, dosimetry plays an essential role in the prevention and the control of radiation exposure. Its use is of great importance in two areas in particular where the employment of ionizing radiation relates to human health: radiation protection, and medical applications. Dosimetry is different for various reasons: owing to the diversity of the physical characteristics produced by different kinds of radiation according to their nature (X- and γ-photons, electrons, neutrons,...), their energy (from several keV to several MeV), the orders of magnitude of the doses being estimated (a factor of about 10 5 between diagnostic and therapeutic applications); and the temporal and spatial variation of the biological parameters entering into the calculations. On the practical level, dosimetry poses two distinct yet closely related problems: the determination of the absorbed dose received by a subject exposed to radiation from a source external to his body (external dosimetry); and the determination of the absorbed dose received by a subject owing to the presence within his body of some radioactive substance (internal dosimetry)

Technical basis document for internal dosimetry

CERN Document Server

Hickman, D P

1991-01-01

This document provides the technical basis for the Chem-Nuclear Geotech (Geotech) internal dosimetry program. Geotech policy describes the intentions of the company in complying with radiation protection standards and the as low as reasonably achievable (ALARA) program. It uses this policy and applicable protection standards to derive acceptable methods and levels of bioassay to assure compliance. The models and computational methods used are described in detail within this document. FR-om these models, dose- conversion factors and derived limits are computed. These computations are then verified using existing documentation and verification information or by demonstration of the calculations used to obtain the dose-conversion factors and derived limits. Recommendations for methods of optimizing the internal dosimetry program to provide effective monitoring and dose assessment for workers are provided in the last section of this document. This document is intended to be used in establishing an accredited dosi...

An evaluation of the Panasonic model UD513AC-1 Thermoluminescence Dosimetry system

International Nuclear Information System (INIS)

Durrer, R.E. Jr.

1991-12-01

An evaluation of the Panasonic UD513AC-1 Thermoluminescence Dosimetry system was performed to determine the system's capabilities as a general purpose thermoluminescence dosimeter measuring device. The tests that were performed included a critique of the user's manual, delimitation of the operating parameters, the quality of construction, and an evaluation of the features that were unique to this system. The UD513AC-1 was found to be an adequate measuring device for most dosimetric applications. It was not well suited for experimental work with thermoluminescence materials due to a low sensitivity displayed by the photomultiplier tube to commonly used materials. The system was well constructed and did not suffer hardware failure during this research. Major attributes of the UD513AC-1 were automatic data storage, highly reproducible heating ramps, an excellent infrared light filter and a unique feature to a single phosphor unit, a dose determination function. Negative aspects of the system included a limited data manipulation capability within the controlling program, a poorly written user's manual, inadequate sensitivity on the part of the photomultiplier tube, and insufficient capability to adjust the hot N 2 gas flow to desired levels

Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

Energy Technology Data Exchange (ETDEWEB)

Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva, E-mail: suelip@ird.gov.br, E-mail: sarah.barreto1@gmail.com [Instituto de Radioproteção e Dosimetria (IRD/CNEN-RJ), Rio de Janeiro, RJ (Brazil). Div. de Radioproteção

2017-07-01

As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

Overview of environmental radiological monitoring program of Institute of Radiation Protection And Dosimetry - IRD

International Nuclear Information System (INIS)

Gomes, Sarah Barreto Oliveira de Christo; Peres, Sueli da Silva

2017-01-01

As a branch of the Brazilian Nuclear Energy Commission (CNEN), the Institute of Radiation Protection and Dosimetry (IRD) performs extensive activities in the fields of radiation protection, metrology, and dosimetry, as well as specific education, onto a wide operational scope that includes the technical support to national regulatory authorities in the licensing process for nationwide nuclear and radioactive facilities. IRD has several laboratories where are performed radiometric and radiochemical analyses and others radioactivity evaluation procedures in different types of samples obtained in the inspection activities, production of radioactivity metrological standards and reference material by National Laboratory of Metrology of Ionizing Radiation (LMNRI), besides others research activities. In this laboratories can be used sealed or unsealed radioactive sources and radiation-producing devices and are classified with radioactive installations in accordance to national regulations. This way, radioactive liquid effluents can be eventually produced and released into the environment in the course of such activities and an effluent monitoring program to control and reduce the releases to environment is carried out. Additionally, IRD maintains the Radioactive Waste Management Program and Environmental Radiological Monitoring Program (ERMP) in accordance to national regulations requirements. The primary focus of ERMP comprises the validation of the dose prognostics for the public members due to effluents discharge and the provision of consistent projections of the radiation levels at the monitoring sites. In this study, a long term ERMP data survey is discussed, spanning the last thirteen years of activities. On the basis of such discussions and prognostics, it could be observed that the radiological environmental radiological impact due to operation of IRD installations is negligible. (author)

California Publicly-Owned Utilities (POUs) – LBNL ‘Beyond Widgets’ Project. Task: ambient lighting and occupancy-based plug load control. System Program Manual

Energy Technology Data Exchange (ETDEWEB)

Robinson, Alastair; Mathew, Paul A.; Regnier, Cynthia; Schwartz, Peter; Schakelford, Jordan; Walter, Travis

2017-09-01

This program manual contains detailed technical information for implementing an incentive program for task-ambient lighting and occupancy-based plug load control. This manual was developed by Lawrence Berkeley National Laboratory, in collaboration with the California Publicly-Owned Utilities (CA POUs) as a partner in the ‘Beyond Widgets’ program funded by the U.S. Department of Energy Building Technologies Office. The primary audience for this manual is the program staff of the various CA POUs. It may also be used by other utility incentive programs to help develop similar programs. It is anticipated that the content of this manual be utilized by the CA POU staff for developing related documents such as the Technical Resource Manual and other filings pertaining to the rollout of an energy systems-based rebate incentive program.

Dosimetry Service

CERN Multimedia

2006-01-01

Cern Staff and Users can now consult their dose records for an individual or an organizational unit with HRT. Please see more information on our web page: http://cern.ch/rp-dosimetry Dosimetry Service is open every morning from 8.30 - 12.00. Closed in the afternoons. We would like to remind you that dosimeters cannot be sent to customers by internal mail. Short-term dosimeters (VCT's) must always be returned to the Service after the use and must not be left on the racks in the experimental areas or in the secretariats. Dosimetry Service Tel. 7 2155 Dosimetry.service@cern.ch http://cern.ch/rp-dosimetry

Determining the lower limit of detection for personnel dosimetry systems

International Nuclear Information System (INIS)

Roberson, P.L.; Carlson, R.D.

1992-01-01

A simple method for determining the lower limit of detection (LLD) for personnel dosimetry systems is described. The method relies on the definition of a critical level and a detection level. The critical level is the signal level above which a result has a small probability of being due to a fluctuation of the background. All results below the critical level should not be reported as an indication of a positive result. The detection level is the net signal level (i.e., dose received) above which there is a high confidence that a true reading will be detected and reported as a qualitatively positive result. The detection level may be identified as the LLD. A simple formula is derived to allow the calculation of the LLD under various conditions. This type of formula is being used by the Department of Energy Laboratory Accreditation Program (DOELAP) for personnel dosimetry. Participants in either the National Voluntary Laboratory Accreditation Program (NVLAP) for personnel dosimetry or DOELAP can use performance test results along with a measurement of background levels to estimate the LLDs for their dosimetry system. As long as they maintain their dosimetry system such that the LLDs are less than half the lower limit of the NVLAP or DOELAP test exposure ranges, dosimetry laboratories can avoid testing failures due to poor performance at very low exposures

Radiation protection dosimetry in medicine - Report of the working group n.9 of the European radiation dosimetry group (EURADOS) - coordinated network for radiation dosimetry (CONRAD - contract EC N) fp6-12684; Dosimetrie pour la radioprotection en milieu medical - rapport du groupe de travail n. 9 du European radiation dosimetry group (EURADOS) - coordinated netword for radiation dosimetry (CONRAD - contrat CE fp6-12684)

Energy Technology Data Exchange (ETDEWEB)

NONE

2009-07-01

This report present the results achieved within the frame of the work the WP 7 (Radiation Protection Dosimetry of Medical Staff) of the coordination action CONRAD (Coordinated Network for Radiation Dosimetry) funded through the 6. EU Framework Program. This action was coordinated by EURADOS (European Radiation Dosimetry Group). EURADOS is an organization founded in 1981 to advance the scientific understanding and the technical development of the dosimetry of ionising radiation in the fields of radiation protection, radiobiology, radiation therapy and medical diagnosis by promoting collaboration between European laboratories. WP7 coordinates and promotes European research for the assessment of occupational exposures to staff in therapeutic and diagnostic radiology workplaces. Research is coordinated through sub-groups covering three specific areas: 1. Extremity dosimetry in nuclear medicine and interventional radiology: this sub-group coordinates investigations in the specific fields of the hospitals and studies of doses to different parts of the hands, arms, legs and feet; 2. Practice of double dosimetry: this sub-group reviews and evaluates the different methods and algorithms for the use of dosemeters placed above and below lead aprons in large exposure during interventional radiology procedures, especially to determine effective doses to cardiologists during cardiac catheterization; and 3. Use of electronic personal dosemeters in interventional radiology: this sub-group coordinates investigations in laboratories and hospitals, and intercomparisons with passive dosemeters with the aim to enable the formulation of standards. (authors)

Neutron personnel dosimetry considerations for fusion reactors

International Nuclear Information System (INIS)

Barton, T.P.; Easterly, C.E.

1979-07-01

The increasing development of fusion reactor technology warrants an evaluation of personnel neutron dosimetry systems to aid in the concurrent development of a radiation protection program. For this reason, current state of knowledge neutron dosimeters have been reviewed with emphasis placed on practical utilization and the problems inherent in each type of dosimetry system. Evaluations of salient parameters such as energy response, latent image instability, and minimum detectable dose equivalent are presented for nuclear emulsion films, track etch techniques, albedo and other thermoluminescent dosimetry techniques, electrical conductivity damage effects, lyoluminescence, thermocurrent, and thermally stimulated exoelectron emission. Brief summaries of dosimetry regulatory requirements and intercomparison study results help to establish compliance and recent trends, respectively. Spectrum modeling data generated by the Neutron Physics Division of Oak Ridge National Laboratory for the Princeton Tokamak Fusion Test Reactor (TFTR) Facility have been analyzed by both International Commission on Radiological Protection fluence to dose conversion factors and an adjoint technique of radiation dosimetry, in an attempt to determine the applicability of current neutron dosimetry systems to deuterium and tritium fusion reactor leakage spectra. Based on the modeling data, a wide range of neutron energies will probably be present in the leakage spectra of the TFTR facility, and no appreciable risk of somatic injury to occupationally exposed workers is expected. The relative dose contributions due to high energy and thermal neutrons indicate that neutron dosimetry will probably not be a serious limitation in the development of fusion power

Practical neutron dosimetry at high energies

International Nuclear Information System (INIS)

McCaslin, J.B.; Thomas, R.H.

1980-10-01

Dosimetry at high energy particle accelerators is discussed with emphasis on physical measurements which define the radiation environment and provide an immutable basis for the derivation of any quantities subsequently required for risk evaluation. Results of inter-laboratory dosimetric comparisons are reviewed and it is concluded that a well-supported systematic program is needed which would make possible detailed evaluations and inter-comparisons of instruments and techniques in well characterized high energy radiation fields. High-energy dosimetry is so coupled with radiation transport that it is clear their study should proceed concurrently

GERTS GQ User's Manual.

Science.gov (United States)

Akiba, Y.; And Others

This user's manual for the simulation program Graphical Evaluation and Review Technique (GERT) GQ contains sections on nodes, branches, program input description and format, and program output, as well as examples. Also included is a programmer's manual which contains information on scheduling, subroutine descriptions, COMMON Variables, and…

Dosimetry system 1986

International Nuclear Information System (INIS)

Woolson, William A.; Egbert, Stephen D.; Gritzner, Michael L.

1987-01-01

In May 1983, the authors proposed a dosimetry system for use by the Radiation Effects Research Foundation (RERF) that would incorporate the new findings and calculations of the joint United States - Japan working groups on the reassessment of A-bomb dosimetry. The proposed dosimetry system evolved from extensive discussions with RERF personnel, numerous meetings of the scientists from Japan and the United States involved in the dosimetry reassessment research, and requirements expressed by epidemiologists and radiobiologists on the various review panels. The dosimetry system proposed was based on considerations of the dosimetry requirements for the normal work of RERF and for future research in radiobiology, the computerized input data on A-bomb survivors available in the RERF data base, the level of detail, precision, and accuracy of various components of the dosimetric estimates, and the computer resources available at RERF in Hiroshima. These discussions and our own experience indicated that, in light of the expansion of computer and radiation technologies and the desire for more detail in the dosimetry, an entirely new approach to the dosimetry system was appropriate. This resulted in a complete replacement of the T65D system as distinguished from a simpler approach involving a renormalization of T65D parameters to reflect the new dosimetry. The proposed dosimetry system for RERF and the plan for implementation was accepted by the Department of Energy (DOE) Working Group on A-bomb Dosimetry chaired by Dr. R.F. Christy. The dosimetry system plan was also presented to the binational A-bomb dosimetry review groups for critical comment and was discussed at joint US-Japan workshop. A prototype dosimetry system incorporating preliminary dosimetry estimates and applicable to only a limited set of A-bomb survivors was installed on the RERF computer system in the fall of 1984. This system was successfully operated at RERF and provided an initial look at the impact of

C-program LINOP for the evaluation of film dosemeters by linear optimization. User manual

International Nuclear Information System (INIS)

Kragh, P.

1995-11-01

Linear programming results in an optimal measuring value for film dosemeters. The Linop program was developed to be used for linear programming. The program permits the evaluation and control of film dosemeters and of all other multi-component dosemeters. This user manual for the Linop program contains the source program, a description of the program and installation and use instructions. The data sets with programs and examples are available upon request. (orig.) [de

Development of manual procedures for care of pregnant patients in radiotherapy service; Desarrollo de manual de procedimentos para atencion de pacientes embarazadas en servicio de radioterapia

Energy Technology Data Exchange (ETDEWEB)

Scarabino, M.L., E-mail: maliscarabino@gmail.com [Hospital Italiano de Buenos Aires (HIBA), Buenos Aires (Argentina); Ruggeri, R.M.; Colombo, S.; Mairal, L.; Sardi, M.E., E-mail: ricardoruggeri@gmail.com [Mevaterapia Centro Medico, Buenos Aires (Argentina)

2013-11-01

The work involves the creation of a manual of procedures for the care of pregnant patients in a radiotherapy center in which each instance of treatment is included, from the obstetrician-oncology comprehensive assessment during admission to establishing controls newborn and its subsequent development in multidisciplinary team. For the preparation of the manual had to design an anthropomorphic phantom that resembles a pregnant woman, which was used to carry out internal and external dosimetry. In turn imparted calculations fetal doses using TPS, imaging tests with MRI, avoiding the use of the tomograph and adapted to the resonator involved were carried immobilizer. All experiences and progress made during the treated cases are introduced in the procedures manual, making it a dynamic tool for continuous improvement for the institution.

Personal dosimetry performance testing in the United States

International Nuclear Information System (INIS)

Soares, Christopher G.

2008-01-01

The basis for personal dosimetry performance testing in the United States is ANSI/HPS N13.11. Now in it's fourth edition, this standard has been in place since 1983. Testing under this standard is administered by the National Voluntary Laboratory Accreditation Program (NVLAP), and accreditation of dosimetry processors under this program is required by U.S. Nuclear Regulatory Commission (NRC) regulations. The U.S. Department of Energy (DOE) also maintains a testing program for its laboratories and contractors, administered by the Department of Energy Laboratory Accreditation Program (DOELAP). One of the goals of this current revision was the modification of ANSI/HPS N13.11 to allow acceptance by both testing programs in order to bring harmonization to U.S. personal dosemeter performance testing. The testing philosophy of ANSI/HPS N13.11 has always combined elements of type testing and routine performance testing and is thus different from the testing philosophy used in the rest of the world. In this paper, the history of performance testing in the U.S. is briefly reviewed. Also described is the revision that produced the fourth edition of this standard, which has taken place over the last three years (2005-2008) by a working group representing national standards laboratories, government laboratories, the military, dosimetry vendors, universities and the nuclear power industry. (author)

In vivo dosimetry with silicon diodes in total body irradiation

International Nuclear Information System (INIS)

Oliveira, F.F.; Amaral, L.L.; Costa, A.M.; Netto, T.G.

2014-01-01

The aim of this work is the characterization and application of silicon diode detectors for in vivo dosimetry in total body irradiation (TBI) treatments. It was evaluated the diode response with temperature, dose rate, gantry angulations and field size. A maximum response variation of 2.2% was obtained for temperature dependence. The response variation for dose rate and angular was within 1.2%. For field size dependence, the detector response increased with field until reach a saturation region, where no more primary radiation beam contributes for dose. The calibration was performed in a TBI setup. Different lateral thicknesses from one patient were simulated and then the calibration factors were determined by means of maximum depth dose readings. Subsequent to calibration, in vivo dosimetry measurements were performed. The response difference between diode readings and the prescribed dose for all treatments was below 4%. This difference is in agreement as recommended by the International Commission on Radiation Units and Measurements (ICRU), which is ±5%. The present work to test the applicability of a silicon diode dosimetry system for performing in vivo dose measurements in TBI techniques presented good results. These measurements demonstrated the value of diode dosimetry as a treatment verification method and its applicability as a part of a quality assurance program in TBI treatments. - Highlights: ► Characterization of a silicon diode dosimetry system. ► Application of the diodes for in vivo dosimetry in total body irradiation treatments. ► Implementation of in vivo dosimetry as a part of a quality assurance program in radiotherapy

EPR Dosimetry - Present and Future

Energy Technology Data Exchange (ETDEWEB)

Regulla, D.F. [GSF - National Research Centre for Environment and Health, Institute of Radiation Protection, 85764 Neuherberg (Germany)

1999-07-01

In the past, IAEA has played a central role in stipulating research and development in EPR high-dose standardisation as well as in coordinating and organising international dose intercomparison programs, within the Member States of the United Nations from the mid-seventies till today. The future tasks of EPR dosimetry seem to tend towards different subjects such as bio markers, biological radiation effects, post-accident dose reconstruction in the environment, and retrospective human dosimetry. The latter may be considered a promising tool for epidemiology on the way to re-define radiation risk of man for chronicle radiation exposures, based on e.g. South Ural civil population and radiation workers. There are on-going international activities in the field of standardising high-level dosimetry by the American Standards on Testing and Materials (Astm), and by the International Organisation of Standards (ISO). The International Commission on Radiation Units and Measurements (ICRU) is considering the establishment of relevant recommendations concerning industrial radiation processing, but also human dose reconstruction. (Author)

EPR Dosimetry - Present and Future

International Nuclear Information System (INIS)

Regulla, D.F.

1999-01-01

In the past, IAEA has played a central role in stipulating research and development in EPR high-dose standardisation as well as in coordinating and organising international dose intercomparison programs, within the Member States of the United Nations from the mid-seventies till today. The future tasks of EPR dosimetry seem to tend towards different subjects such as bio markers, biological radiation effects, post-accident dose reconstruction in the environment, and retrospective human dosimetry. The latter may be considered a promising tool for epidemiology on the way to re-define radiation risk of man for chronicle radiation exposures, based on e.g. South Ural civil population and radiation workers. There are on-going international activities in the field of standardising high-level dosimetry by the American Standards on Testing and Materials (Astm), and by the International Organisation of Standards (ISO). The International Commission on Radiation Units and Measurements (ICRU) is considering the establishment of relevant recommendations concerning industrial radiation processing, but also human dose reconstruction. (Author)

Decomposition of spectra in EPR dosimetry using the matrix method

International Nuclear Information System (INIS)

Sholom, S.V.; Chumak, V.V.

2003-01-01

The matrix method of EPR spectra decomposition is developed and adapted for routine application in retrospective EPR dosimetry with teeth. According to this method, the initial EPR spectra are decomposed (using methods of matrix algebra) into several reference components (reference matrices) that are specific for each material. Proposed procedure has been tested on the example of tooth enamel. Reference spectra were a spectrum of an empty sample tube and three standard signals of enamel (two at g=2.0045, both for the native signal and one at g perpendicular =2.0018, g parallel =1.9973 for the dosimetric signal). Values of dosimetric signals obtained using the given method have been compared with data obtained by manual manipulation of spectra, and good coincidence was observed. This allows considering the proposed method as potent for application in routine EPR dosimetry

Characterization of internal dosimetry practices

International Nuclear Information System (INIS)

Traub, R.J.; Heid, K.R.; Mann, J.C.

1983-01-01

Current practices in internal dosimetry at DOE facilities were evaluated with respect to consistency among DOE Contractors. All aspects of an internal dosimetry program were addressed. Items considered include, but are not necessarily limited to, record systems and ease of information retrieval; ease of integrating internal dose and external dose; modeling systems employed, including ability to modify models depending on excretion data, and verification of computer codes utilized; bioassay procedures, including quality control; and ability to relate air concentration data to individual workers and bioassay data. Feasibility of uranium analysis in solution by laser fluorescence excitation at uranium concentrations of one part per billion was demonstrated

Financial Reporting and Cost Analysis Manual for Day Care Centers, Head Start, and Other Programs.

Science.gov (United States)

Bedger, Jean E.; And Others

This manual is designed to provide fundamental directions for systematic financial reporting and cost analysis for the administrators, accountants, bookkeepers, and staff of day care, Project Head Start, and other programs. The major aims of the manual are to induce day care directors to adopt uniform bookkeeping procedures and to analyze costs…

Vocational Education Program/Course Inventory Form PCI. Explanation and Instructional Manual.

Science.gov (United States)

California Occupational Information Coordinating Committee, Sacramento.

This manual for teachers, administrators, and counselors both explains the Program/Course Inventory (PCI), a data collection instrument, and provides instructions for completing the PCI form. The first section describes the PCI developed by the Ventura County Superintendent of Schools staff to collect data that define vocational education…

CABAS: A freely available PC program for fitting calibration curves in chromosome aberration dosimetry

International Nuclear Information System (INIS)

Deperas, J.; Szluiska, M.; Deperas-Kaminska, M.; Edwards, A.; Lloyd, D.; Lindholm, C.; Romm, H.; Roy, L.; Moss, R.; Morand, J.; Wojcik, A.

2007-01-01

The aim of biological dosimetry is to estimate the dose and the associated uncertainty to which an accident victim was exposed. This process requires the use of the maximum-likelihood method for fitting a calibration curve, a procedure that is not implemented in most statistical computer programs. Several laboratories have produced their own programs, but these are frequently not user-friendly and not available to outside users. We developed a software for fitting a linear-quadratic dose-response relationship by the method of maximum-likelihood and for estimating a dose from the number of aberrations observed. The program called as CABAS consists of the main curve-fitting and dose estimating module and modules for calculating the dose in cases of partial body exposure, for estimating the minimum number of cells necessary to detect a given dose of radiation and for calculating the dose in the case of a protracted exposure. (authors)

FDA (Food and Drug Administration) Compliance Program Guidance Manual (FY 88). Section 4. Medical and radiological devices

International Nuclear Information System (INIS)

1988-01-01

The FDA Compliance Program Guidance Manual provides a system for issuing and filing program plans and instructions directed to Food and Drug Administration Field operations for project implementation. Section IV provides those chapters of the Compliance Program Guidance Manual which pertain to the areas of medical and radiological devices. Some of the areas of coverage include laser and sunlamp standards inspections, compliance testing of various radiation-emitting products such as television receivers and microwave ovens, emergency response planning and policy, premarket approval and device manufacturers inspections, device problem reporting, sterilization of devices, and consumer education programs on medical and radiological devices

AutoBayes Program Synthesis System Users Manual

Science.gov (United States)

Schumann, Johann; Jafari, Hamed; Pressburger, Tom; Denney, Ewen; Buntine, Wray; Fischer, Bernd

2008-01-01

Program synthesis is the systematic, automatic construction of efficient executable code from high-level declarative specifications. AutoBayes is a fully automatic program synthesis system for the statistical data analysis domain; in particular, it solves parameter estimation problems. It has seen many successful applications at NASA and is currently being used, for example, to analyze simulation results for Orion. The input to AutoBayes is a concise description of a data analysis problem composed of a parameterized statistical model and a goal that is a probability term involving parameters and input data. The output is optimized and fully documented C/C++ code computing the values for those parameters that maximize the probability term. AutoBayes can solve many subproblems symbolically rather than having to rely on numeric approximation algorithms, thus yielding effective, efficient, and compact code. Statistical analysis is faster and more reliable, because effort can be focused on model development and validation rather than manual development of solution algorithms and code.

ACT Plan: Technical Manual. 2013/2014

Science.gov (United States)

ACT, Inc., 2013

2013-01-01

This manual contains information about the American College Test (ACT) Plan® program. The principal focus of this manual is to document the Plan program's technical adequacy in light of its intended purposes. This manual supersedes the 2011 edition. The content of this manual responds to requirements of the testing industry as established in the…

Annual course of retraining for the occupational exposure personnel of the laboratory of internal dosimetry; Curso anual de reentrenamiento para el POE del laboratorio de dosimetria interna

Energy Technology Data Exchange (ETDEWEB)

Alfaro L, M.M. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

2002-09-15

The general objective of this report is to instruct the personnel in the basic concepts of radiological protection and in the Manual of Procedures of Radiological Safety of the Laboratory of Internal Dosimetry. Also, to exchange experiences during the activities that are carried out in the laboratory and in the knowledge of abnormal situations. The referred Manual consists of 14 procedures and 5 instructions which are listed in annex of this document. The content of this course consists of three topics: 1. Basic principles of radiological protection to reduce the received dose equivalent. 2. Use of radiation measurer equipment. 3. Emergency procedures of the laboratory of internal dosimetry. (Author)

Calibration of dosimeters used in radiotherapy. A manual

International Nuclear Information System (INIS)

1994-01-01

The present manual is a revision of IAEA Technical Reports Series No.185, published in 1979. This manual is intended for use by the network of Secondary Standard Dosimetry Laboratories (SSDLs) which was set up by the IAEA and the World Health Organization (WHO). The objectives of the SSDL network are to: calibrate radiation dosimeters and ancillary instruments; serve as a link between primary standard laboratories and radiation users; and provide advice and assistance in all aspects of radiation metrology. The various calibration procedures are described, their relative advantages and disadvantages are discussed, and criteria are put forward to help an SSDL decide which procedure is the best to use in order to meet a particular requirement. The information in this manual should also be of value to other similar laboratories, usually associated with hospitals, which are not formally part of the IAEA/WHO network of SSDLs. 26 refs, 6 figs, 6 tabs

Operating manual for the Health Physics Research Reactor

International Nuclear Information System (INIS)

1985-11-01

This manual is intended to serve as a guide in the operation and maintenance of the Health Physics Researh Reactor (HPRR) of the Health Physics Dosimetry Applications Research (DOSAR) Facility. It includes descriptions of the HPRR and of associated equipment such as the reactor positioning devises and the derrick. Procedures for routine operation of the HPRR are given in detail, and checklists for the various steps are provided where applicable. Emergency procedures are similarly covered, and maintenance schedules are outlined. Also, a bibliography of references giving more detailed information on the DOSAR Facility is included. Changes to this manual will be approved by at least two of the following senior staff members: (1) the Operations Division Director, (2) the Reactor Operations Department Head, (3) the Supervisor of Reactor Operations TSF-HPRR Areas. The master copy and the copy of the manual issued to the HPRR Operations Supervisor will always reflect the latest revision. 22 figs

Personnel radiation dosimetry

International Nuclear Information System (INIS)

1987-01-01

The book contains the 21 technical papers presented at the Technical Committee Meeting to Elaborate Procedures and Data for the Intercomparison of Personnel Dosimeters organizaed by the IAEA on 22-26 April 1985. A separate abstract was prepared for each of these papers. A list of areas in which additional research and development work is needed and recommendations for an IAEA-sponsored intercomparison program on personnel dosimetry is also included

Application of EGS and ETRAN to Problems in Medical Physics and Dosimetry

CERN Document Server

Nelson, W R

1980-01-01

The author looks at a few applications of Monte Carlo programs to problems of interest in medical physics and dosimetry. In particular, two areas are considered: 1) bremsstrahlung production from medical accelerators; 2) photon dosimetry at medium to low energies. (16 refs) .

Management of individual and collective dosimetry at Fessenheim nuclear plant. Evaluation after refueling shutdown

International Nuclear Information System (INIS)

Lamarre, D.; Waller, A.

1980-01-01

The principle of dosimetry management chosen by Fessenheim nuclear power station was originally consisted of two phases: - an automatic acquisition of individual doses realized by stylodosimeter readers; - a deferred data processing by computer. The whole system has not been used during the shutdown for the first refuelling of unit number one in view of encountered difficulties with perfecting of automatic readers prototype, this last phase has been replaced by a manual acquisition of doses. The dosimetry data processing has two main objects: - supervision of individual dosimetry for people who work in the nuclear power station; - knowledge of doses assigned for each working and equipment. Moreover, a first dosimetric result of the shutdown for refuelling of unit number one, enables to notice the workings which doses are the most important and written in percentage of total doses: regulatory controls: about 19%; - steam generators working: 16%; - working decontamination and making health physics screen (lock chamber) 10% [fr

Neutron personnel dosimetry

International Nuclear Information System (INIS)

Griffith, R.V.

1981-01-01

The current state-of-the-art in neutron personnel dosimetry is reviewed. Topics covered include dosimetry needs and alternatives, current dosimetry approaches, personnel monitoring devices, calibration strategies, and future developments

Review of radiation dosimetry research at the University of Wisconsin during 1961-1982

International Nuclear Information System (INIS)

Cameron, J.R.; Moran, P.R.; Attix, F.H.

1982-01-01

The report provides a comprehensive review of the overall activities in this program since 1961. Research areas have included the development and use of lithium fluoride for thermoluminescent dosimetry, solid state neutron dosimetry, and ionization chamber research

Report of the results of the second phase of Research Coordinated Program of IAEA ''Regional Intercomparison of Personnel Dosimetry''

International Nuclear Information System (INIS)

Morales, J.; Diaz, E.; Hernandez, E.; Capote, E.

1998-01-01

In this report the results of an intercomparison program within a research coordinated program are presented. This is a second phase of the study that consisted in to evaluate the implementation of the new ICRU quantities for individual monitoring by the dosimetry laboratories. In this report the organization aspects, quality control of the irradiations performed by the reference laboratory (SSDL of the Centro de Proteccion e Higiene de las radiaciones) as well the results of the participant laboratories are included

Implementation of high-dose chemical dosimetry for industrial facilities

International Nuclear Information System (INIS)

Conceicao, Cirilo Cezar Sant'Anna da

2006-01-01

The purpose of this work is the implementation of methodology for high dose measurements using chemical dosimeters in liquid phase, traceable to the international metrology system, and make available in the country, the standard of high-dose to industrial irradiation facilities and research irradiators, trough the quality program with comparative measurements and direct use of the standard dosimeters in routine. The use of these low cost dosimetry systems in industrial irradiation facilities, assists to the certification requirements and it can reduce the costs with dosimetry for approximately 20% of the total dosimetry costs, using these systems in routine measurements and validation process, largely substituting the imported PMMA dosimeters, among others. (author)

Development of manual procedures for care of pregnant patients in radiotherapy service

International Nuclear Information System (INIS)

Scarabino, M.L.; Ruggeri, R.M.; Colombo, S.; Mairal, L.; Sardi, M.E.

2013-01-01

The work involves the creation of a manual of procedures for the care of pregnant patients in a radiotherapy center in which each instance of treatment is included, from the obstetrician-oncology comprehensive assessment during admission to establishing controls newborn and its subsequent development in multidisciplinary team. For the preparation of the manual had to design an anthropomorphic phantom that resembles a pregnant woman, which was used to carry out internal and external dosimetry. In turn imparted calculations fetal doses using TPS, imaging tests with MRI, avoiding the use of the tomograph and adapted to the resonator involved were carried immobilizer. All experiences and progress made during the treated cases are introduced in the procedures manual, making it a dynamic tool for continuous improvement for the institution

Economic Development through Youth. A Program for Schools and Communities. Manual.

Science.gov (United States)

Nolen, Lori

This manual is designed to help teachers, businesses, Chambers of Commerce, and students start their own economic development activities and youth ventures. It describes a two-step plan to economic development through youth: development of an in-school student chamber of commerce program and development of a youth-owned venture. The first part of…

Dosimetry services for internal and external radiation sources

International Nuclear Information System (INIS)

1988-01-01

The Canadian Atomic Energy Control Board (AECB) sets radiation dose limits for the operation of nuclear facilities and the possession of prescribed substances within Canada. To administer these regulations the AECB must be satisfied that the dosimetry services used by a licensee meet adequate standards. Licensees are required to use the Occupational Dosimetry Service operated by the Bureau of Radiation and Medical Devices, Department of National Health and Welfare (BRMD) to determine doses from external sources of radiation, except where a detailed rationale is given for using another service. No national dosimetry service exists for internal sources of radiation. Licensees who operate or use a dosimetry service other than the BRMD must provide the AECB with evidence of the competence of the staff and adequacy of the equipment, techniques and procedures; provide the AECB with evidence that a quality assurance program has been implemented; and send individual dose or exposure data to the National Dose Registry. (L.L.)

EPR dosimetry - present and future

International Nuclear Information System (INIS)

Regulla, D.F.

1999-01-01

In the past, IAEA has played a central role in stipulating research and development in EPR high-dose standardisation as well as co-ordinating and organising international dose intercomparison programs, within the Member States of the United Nations from the mid-seventies till today. The future tasks of EPR dosimetry seem to tend towards different subjects such as biomarkers, biological radiation effects, post-accident dose reconstruction in the environment, and retrospective human dosimetry. The latter may be considered a promising tool for epidemiology on the way to re-define radiation risk of man for chronicle radiation exposures, based on e.g. South Ural civil population and radiation workers. There are on-going international activities in the field of standardising high-level dosimetry by the American Standards on Testing and Materials (ASTM), and the International Organisation of Standards (ISO) as well as those of the International Commission on Radiation Units and Measurements (ICRU) considering the establishment of relevant recommendations concerning industrial radiation processing, but also human dose reconstruction. (author)

Dosimetry

International Nuclear Information System (INIS)

Rezende, D.A.O. de

1976-01-01

The fundamental units of dosimetry are defined, such as exposure rate, absorbed dose and equivalent dose. A table is given of relative biological effectiveness values for the different types of radiation. The relation between the roentgen and rad units is calculated and the concepts of physical half-life, biological half-life and effective half-life are discussed. Referring to internal dosimetry, a mathematical treatment is given to β particle-and γ radiation dosimetry. The absorbed dose is calculated and a practical example is given of the calculation of the exposure and of the dose rate for a gama source [pt

Dosimetry tools and techniques for IMRT

International Nuclear Information System (INIS)

Low, Daniel A.; Moran, Jean M.; Dempsey, James F.; Dong Lei; Oldham, Mark

2011-01-01

Intensity modulated radiation therapy (IMRT) poses a number of challenges for properly measuring commissioning data and quality assurance (QA) radiation dose distributions. This report provides a comprehensive overview of how dosimeters, phantoms, and dose distribution analysis techniques should be used to support the commissioning and quality assurance requirements of an IMRT program. The proper applications of each dosimeter are described along with the limitations of each system. Point detectors, arrays, film, and electronic portal imagers are discussed with respect to their proper use, along with potential applications of 3D dosimetry. Regardless of the IMRT technique utilized, some situations require the use of multiple detectors for the acquisition of accurate commissioning data. The overall goal of this task group report is to provide a document that aids the physicist in the proper selection and use of the dosimetry tools available for IMRT QA and to provide a resource for physicists that describes dosimetry measurement techniques for purposes of IMRT commissioning and measurement-based characterization or verification of IMRT treatment plans. This report is not intended to provide a comprehensive review of commissioning and QA procedures for IMRT. Instead, this report focuses on the aspects of metrology, particularly the practical aspects of measurements that are unique to IMRT. The metrology of IMRT concerns the application of measurement instruments and their suitability, calibration, and quality control of measurements. Each of the dosimetry measurement tools has limitations that need to be considered when incorporating them into a commissioning process or a comprehensive QA program. For example, routine quality assurance procedures require the use of robust field dosimetry systems. These often exhibit limitations with respect to spatial resolution or energy response and need to themselves be commissioned against more established dosimeters. A chain of

Radiation protection dosimetry in medicine - Report of the working group n.9 of the European radiation dosimetry group (EURADOS) - coordinated network for radiation dosimetry (CONRAD - contract EC N) fp6-12684

International Nuclear Information System (INIS)

2009-01-01

This report present the results achieved within the frame of the work the WP 7 (Radiation Protection Dosimetry of Medical Staff) of the coordination action CONRAD (Coordinated Network for Radiation Dosimetry) funded through the 6. EU Framework Program. This action was coordinated by EURADOS (European Radiation Dosimetry Group). EURADOS is an organization founded in 1981 to advance the scientific understanding and the technical development of the dosimetry of ionising radiation in the fields of radiation protection, radiobiology, radiation therapy and medical diagnosis by promoting collaboration between European laboratories. WP7 coordinates and promotes European research for the assessment of occupational exposures to staff in therapeutic and diagnostic radiology workplaces. Research is coordinated through sub-groups covering three specific areas: 1. Extremity dosimetry in nuclear medicine and interventional radiology: this sub-group coordinates investigations in the specific fields of the hospitals and studies of doses to different parts of the hands, arms, legs and feet; 2. Practice of double dosimetry: this sub-group reviews and evaluates the different methods and algorithms for the use of dosemeters placed above and below lead aprons in large exposure during interventional radiology procedures, especially to determine effective doses to cardiologists during cardiac catheterization; and 3. Use of electronic personal dosemeters in interventional radiology: this sub-group coordinates investigations in laboratories and hospitals, and intercomparisons with passive dosemeters with the aim to enable the formulation of standards. (authors)

Reassessment of the atomic bomb radiation dosimetry for Hiroshima and Nagasaki. Dosimetry system 2002. DS02. Volume 1

International Nuclear Information System (INIS)

Young, Robert W.; Kerr, George D.

2005-01-01

The extensive efforts to review the dosimetry of the atomic-bomb survivors and formulate the new dosimetry system DS02 have been greatly welcomed by the Radiation Effects Research Foundation (RERF). This accomplishment is a fine tribute to the importance of the epidemiological studies being conducted at RERF. No other study is so informative of the effects of radiation on human health. The gracious participation in the RERF program by the atomic-bomb survivors allows us to contribute to the well being of these individuals, and the high quality of the data obtained allows the RERF results to feature so prominently in the formulation of international guidelines for radiation protection. Such a great effort to improve and substantiate the dosimetry would not otherwise have been justified. RERF greatly appreciates the independent work of the U.S. and Japanese Working Groups on the atomic-bomb dosimetry and the review by the Joint Senior Review Group of this overall effort. We are assured that unbiased development of the new dosimetry system will reflect well in its application in the RERF epidemiology study. The documentation included in this report will serve as reference for the many deliberations concluded. The title publications are divided into 2 volumes. This is the first volume. The 8 of the reports in each chapter are indexed individually. (J.P.N.)

Reassessment of the atomic bomb radiation dosimetry for Hiroshima and Nagasaki. Dosimetry system 2002. DS02. Volume 2

International Nuclear Information System (INIS)

Young, Robert W.; Kerr, George D.

2005-01-01

The extensive efforts to review the dosimetry of the atomic-bomb survivors and formulate the new dosimetry system DS02 have been greatly welcomed by the Radiation Effects Research Foundation (RERF). This accomplishment is a fine tribute to the importance of the epidemiological studies being conducted at RERF. No other study is so informative of the effects of radiation on human health. The gracious participation in the RERF program by the atomic-bomb survivors allows us to contribute to the well being of these individuals, and the high quality of the data obtained allows the RERF results to feature so prominently in the formulation of international guidelines for radiation protection. Such a great effort to improve and substantiate the dosimetry would not otherwise have been justified. RERF greatly appreciates the independent work of the U.S. and Japanese Working Groups on the atomic-bomb dosimetry and the review by the Joint Senior Review Group of this overall effort. We are assured that unbiased development of the new dosimetry system will reflect well in its application in the RERF epidemiology study. The documentation included in this report will serve as reference for the many deliberations concluded. The title publications are divided into 2 volumes. This is the second volume. The 29 of the reports in each chapter are indexed individually. (J.P.N.)

Development of object oriented program `SONSHO` for strength evaluation. Manual of Version 4.0 program

Energy Technology Data Exchange (ETDEWEB)

Hosogai, Hiromi [Joyo Industries Co. Ltd., Tokai, Ibaraki (Japan); Kasahara, Naoto

1998-07-01

Object Oriented Program `SONSHO` predicts creep fatigue damage factors based on Elevated Temperature Structural Design Guide for `Monju` and other various procedures from stress classification data obtained from structural analysis results. From view point of program implementation, it is required that external programs interface and frequent revise from update of material and creep fatigue evaluation methods. Object oriented approach was continuously introduced to improve these aspects of the program. Version 4.0 has the following new functions. (1) Material strength library was implemented as an independent program module based on Microsoft Active X control and 32bitDLL technologies, which can be accessed by general Windows programs. (2) Self instruction system `Wizard` enables manual less operation. (3) Microsoft common object model (COM) was adopted for program interface, and this program can communicate with Excel sheet data on memory. Sonsho Ver.4.0 can work on Windows 95 or Windows NT4.0. Microsoft Visual Basic 5.0 (Enterprose Edition) and Microsoft FORTRAN Power Station 4.0 were adopted for program. (author)

DOSAR/CalLab Operations Manual

International Nuclear Information System (INIS)

Bogard, J.S.

2000-01-01

The Life Sciences Division (LSD) of Oak Ridge National Laboratory (ORNL) has a long record of radiation dosimetry research, primarily using the Health Physics Research Reactor (HPRR) and the Dosimetry Applications Research (DOSAR) Program Calibration Laboratory (CalLab), referred to formerly as the Radiation Calibration Laboratory. These facilities have been used by a broad segment of the research community to perform a variety of experiments in areas including, but not limited to, radiobiology, radiation dosimeter and instrumentation development and calibration, and the testing of materials in a variety of radiation environments

Roadmap Through Title XX. Financing Services for Children Through Title XX and Other Programs: Manual 5.

Science.gov (United States)

Copeland, William C.; Iversen, Iver A.

This manual, part of a Hecht Institute four-manual series entitled Financing Children's Services Through Title XX and Related Programs, teaches what Title XX regulations are, what they mean, and what actions and procedures are commanded by them. The first section covers the necessity of rule systems, the characteristics of a good rule system and…

Internal dosimetry and control

International Nuclear Information System (INIS)

Rich, B.L.

1990-05-01

This internal dosimetry and control report provides guidance for EG ampersand G Idaho, Inc., field programs in detecting, evaluating, and controlling personnel exposure resulting from uptake of radionuclides by the body. Procedures specific to each program or facility are required to define the details of guidance from this report. Fundamental principles related to philosophy, policies, monitoring guidelines, and dose evaluation are discussed. Specific numerical guides and action levels are developed to guide the programs in evaluating the significance of specific analytical results. The requirement to thoroughly document the results and provide a formal technical base for each policy and/or practice is outlined and explained. 8 refs., 3 figs., 7 tabs

Photon dosimetry intercomparisons at Tygerberg and Groote Schuur hospitals

International Nuclear Information System (INIS)

Jones, D.T.L.; Symons, J.E.; Schreuder, A.N.; Van der Merwe, E.J.; Rossouw, A.; Hough, J.K.; Lazarus, G.L.

1994-08-01

A national photon dosimetry intercomparison was undertaken at 8 hospitals at the beginning of 1989 prior to the commencement of randomised clinical trials involving neutron therapy at the National Accelerator Centre. The results obtained were in agreement at all but two hospitals. Following these studies it was agreed that a uniform photon dosimetry protocol, the AAPM TG2 protocol, be adopted countrywide. The clinical program at the National Accelerator Centre is now far advanced and it was deemed appropriate to undertake a new photon dosimetry intercomparison at two local hospitals, through which all patients are referred. The procedure involved was to compare the doses measured at each hospital under specified conditions by National Accelerator staff with the doses measured by the hospital physicists using their own equipment and protocols. The results obtained were in good agreement, confirming the validity of the dosimetry techniques used. 8 refs., 8 tabs

Management Information System Project. Data Processors Manual to the Program Oriented Accounting System: The Budgetary Process.

Science.gov (United States)

Foley, Walter; Harr, Gordon

The purpose of this manual is to serve the needs of a data processing facility in the operation of a management information system (MIS). Included in the manual are system flowcharts, job control language, and system documentation. The system has been field tested and operates under IBM System 360/Model 65-05-MVT-HASP. The programing language is…

Dosimetry of 64Cu-DOTA-AE105, a PET tracer for uPAR imaging

DEFF Research Database (Denmark)

Persson, Morten; El Ali, Henrik H.; Binderup, Tina

2014-01-01

64Cu-DOTA-AE105 is a novel positron emission tomography (PET) tracer specific to the human urokinase-type plasminogen activator receptor (uPAR). In preparation of using this tracer in humans, as a new promising method to distinguish between indolent and aggressive cancers, we have performed PET...... studies in mice to evaluate the in vivo biodistribution and estimate human dosimetry of 64Cu-DOTA-AE105. MethodsFive mice received iv tail injection of 64Cu-DOTA-AE105 and were PET/CT scanned 1, 4.5 and 22h post injection. Volume-of-interest (VOI) were manually drawn on the following organs: heart, lung......Favorable dosimetry estimates together with previously reported uPAR PET data fully support human testing of 64Cu-DOTA-AE105....

Polymer gel dosimetry

Energy Technology Data Exchange (ETDEWEB)

Baldock, C [Institute of Medical Physics, School of Physics, University of Sydney (Australia); De Deene, Y [Radiotherapy and Nuclear Medicine, Ghent University Hospital (Belgium); Doran, S [CRUK Clinical Magnetic Resonance Research Group, Institute of Cancer Research, Surrey (United Kingdom); Ibbott, G [Radiation Physics, UT M D Anderson Cancer Center, Houston, TX (United States); Jirasek, A [Department of Physics and Astronomy, University of Victoria, Victoria, BC (Canada); Lepage, M [Centre d' imagerie moleculaire de Sherbrooke, Departement de medecine nucleaire et de radiobiologie, Universite de Sherbrooke, Sherbrooke, QC (Canada); McAuley, K B [Department of Chemical Engineering, Queen' s University, Kingston, ON (Canada); Oldham, M [Department of Radiation Oncology, Duke University Medical Center, Durham, NC (United States); Schreiner, L J [Cancer Centre of South Eastern Ontario, Kingston, ON (Canada)], E-mail: c.baldock@physics.usyd.edu.au, E-mail: yves.dedeene@ugent.be

2010-03-07

Polymer gel dosimeters are fabricated from radiation sensitive chemicals which, upon irradiation, polymerize as a function of the absorbed radiation dose. These gel dosimeters, with the capacity to uniquely record the radiation dose distribution in three-dimensions (3D), have specific advantages when compared to one-dimensional dosimeters, such as ion chambers, and two-dimensional dosimeters, such as film. These advantages are particularly significant in dosimetry situations where steep dose gradients exist such as in intensity-modulated radiation therapy (IMRT) and stereotactic radiosurgery. Polymer gel dosimeters also have specific advantages for brachytherapy dosimetry. Potential dosimetry applications include those for low-energy x-rays, high-linear energy transfer (LET) and proton therapy, radionuclide and boron capture neutron therapy dosimetries. These 3D dosimeters are radiologically soft-tissue equivalent with properties that may be modified depending on the application. The 3D radiation dose distribution in polymer gel dosimeters may be imaged using magnetic resonance imaging (MRI), optical-computerized tomography (optical-CT), x-ray CT or ultrasound. The fundamental science underpinning polymer gel dosimetry is reviewed along with the various evaluation techniques. Clinical dosimetry applications of polymer gel dosimetry are also presented. (topical review)

Cytogenetic analysis for radiation dose assessment. A manual

International Nuclear Information System (INIS)

2001-01-01

the methods and their modifications used for biological dose assessment worldwide, as well as the need and the possible ways of standardization of the available and promising cytogenetic techniques to evaluate the dose of accidental acute or cumulative chronic exposure to ionizing radiation. The contribution of the chief scientific investigators of the IAEA CRP on 'Radiation Dosimetry through Biological Indicators' is sincerely acknowledged (the list of the participating biodosimetry laboratories is given at the end of the Manual). Four Consultancy Services Meetings were held in 1999-2000 to prepare this Manual on standardized conventional methods and amend them with newly available, proven techniques such as fluorescence in situ hybridization (FISH), premature chromosomal condensation (PCC) and study of micronuclei (MN) frequency

CT dosimetry and quality control of its operation

International Nuclear Information System (INIS)

Mechi, Saida

2011-01-01

This thesis focuses on the dosimetry of a scanner, quality control of its operations and the development of a protocol. It allowed us the mastery of the art scanner and participation in all quality controls with appropriate ghosts. CT is a radiographic examination sophisticated and accurate, widely used to screen for various diseases, among other cancer. We worked on the dosimetry of a scanner and we have made simulations with a program called Impact that calculates the CT CTDI and the PDL and compared with values displayed on the console. Similarly, the software calculates the absorbed dose and compared with that calculated by Caldose X. This work is complemented by the development of a protocol with the quality control procedures of the image and dosimetry in chronological order.

Dosimetry in Interventional Radiology - Effective Dose Estimation

International Nuclear Information System (INIS)

Miljanic, S.; Buls, N.; Clerinx, P.; Jarvinen, H.; Nikodemova, D.; Ranogajec-Komor, M; D'Errico, F.

2008-01-01

Interventional radiological procedures can lead to significant radiation doses to patients and to staff members. In order to evaluate the personal doses with respect to the regulatory dose limits, doses measured by dosimeters have to be converted to effective doses (E). Measurement of personal dose equivalent Hp(10) using a single unshielded dosimeter above the lead apron can lead to significant overestimation of the effective dose, while the measurement with dosimeter under the apron can lead to underestimation. To improve the accuracy, measurements with two dosimeters, one above and the other under the apron have been suggested ( d ouble dosimetry ) . The ICRP has recommended that interventional radiology departments develop a policy that staff should wear two dosimeters. The aim of this study was to review the double dosimetry algorithms for the calculation of effective dose in high dose interventional radiology procedures. The results will be used to develop general guidelines for personal dosimetry in interventional radiology procedures. This work has been carried out by Working Group 9 (Radiation protection dosimetry of medical staff) of the CONRAD project, which is a Coordination Action supported by the European Commission within its 6th Framework Program.(author)

9th International Conference on 3D Radiation Dosimetry

International Nuclear Information System (INIS)

2017-01-01

IC3DDose 2016 - 9th International Conference on 3D Radiation Dosimetry Preface It was a great pleasure to welcome participants to IC3DDose 2016, the 9th International Conference on 3D Radiation Dosimetry, held from 7–10 November 2016 in Galveston, Texas. The series of conferences has evolved considerably during its history. At the first conference, DOSGEL’99, the discussion centered around gel dosimetry. Held in Lexington, Kentucky in 1999, it was timed to coincide with the American Association of Physicists in Medicine (AAPM) Annual Meeting in Nashville, Tennessee. It was my honour to organize that first conference, and it was once again my honour to organize the 9th conference in the series now known as IC3DDose which was held in Galveston, Texas. As was the case with recent IC3DDose conferences, the topic has broadened considerably beyond gel dosimetry. Not only have newer 3D volumetric dosimeters appeared on the scene, but novel electronic dosimetry systems and software that generate quasi-3D dose information have also. These changes have tracked advances in radiation oncology as techniques such as IMRT, VMAT, and IGRT have become almost ubiquitous. At the same time, dynamic treatments including gating and tracking now enjoy widespread use. Novel treatment technologies have appeared with perhaps the most disruptive being combined MR imaging-treatment units such as the ViewRay MR-cobalt unit and the Elekta/Philips MR-Linac. The potential benefits offered by 3D dosimetry were explored, compared and evaluated during IC3DDose 2016. Novel and improved readout techniques, some of which take advantage of the contemporary treatment environment and new QA systems and procedures, as well as other aspects of clinical dosimetry were well represented in the program. Over the past several years, the importance of safety in radiation therapy has been highlighted. The benefits of 3D dosimetry in contributing to safe and accurate treatments cannot be overstated. The

Internal sources dosimetry

International Nuclear Information System (INIS)

Savio, Eduardo

1994-01-01

The absorbed dose, need of estimation in risk evaluation in the application of radiopharmaceuticals in Nuclear Medicine practice,internal dosimetry,internal and external sources. Calculation methodology,Marinelli model,MIRD system for absorbed dose calculation based on biological parameters of radiopharmaceutical in human body or individual,energy of emitted radiations by administered radionuclide, fraction of emitted energy that is absorbed by target body.Limitation of the MIRD calculation model. A explanation of Marinelli method of dosimetry calculation,β dosimetry. Y dosimetry, effective dose, calculation in organs and tissues, examples. Bibliography .

Nuclear accident dosimetry. Revision of emergency data sheets

International Nuclear Information System (INIS)

Delafield, H.J.

1976-09-01

The Emergency Data Sheets on Nuclear Accident Dosimetry have been revealed following the publication of a three part manual on this subject (Delafield, Dennis and Gibson, AERE-R 7485/6/7, 1973). This memo provides an explanation of the action levels adopted for the initial segregation of irradiated persons following a criticality accident, by monitoring the activity of indium foils contained in personnel dosimeters and the induced body sodium activity. The data sheets are given as an Appendix. They provide basic information on; the segregation of irradiated persons, the estimation of radiation exposure, and the assessment of personnel γ-ray and neutron doses. (author)

Summary remarks and recommended reactions for an international data file for dosimetry applications for LWR, FBR, and MFR reactor research, development and testing programs

International Nuclear Information System (INIS)

McElroy, W.N.; Lippincott, E.P.; Grundl, J.A.; Fabry, A.; Dierckx, R.; Farinelli, U.

1979-01-01

The need for the use of an internationally accepted data file for dosimetry applications for light water reactor (LWR), fast breeder reactor (FBR), and magnetic fusion reactor (MFR) research, development, and testing programs continues to exist for the Nuclear Industry. The work of this IAEA meeting, therefore, will be another important step in achieving consensus agreement on an internationally recommended file and its purpose, content, structure, selected reactions, and associated uncertainy files. Summary remarks and a listing of recommended reactions for consideration in the formulation of an ''International Data File for Dosimetry Applications'' are presented in subsequent sections of this report

Techniques for radiation measurements: Micro-dosimetry and dosimetry

International Nuclear Information System (INIS)

Waker, A. J.

2006-01-01

Experimental Micro-dosimetry is concerned with the determination of radiation quality and how this can be specified in terms of the distribution of energy deposition arising from the interaction of a radiation field with a particular target site. This paper discusses various techniques that have been developed to measure radiation energy deposition over the three orders of magnitude of site-size; nano-meter, micrometer and millimetre, which radiation biology suggests is required to fully account for radiation quality. Inevitably, much of the discussion will concern the use of tissue-equivalent proportional counters and variants of this device, but other technologies that have been studied, or are under development, for their potential in experimental Micro-dosimetry are also covered. Through an examination of some of the quantities used in radiation metrology and dosimetry the natural link with Micro-dosimetric techniques will be shown and the particular benefits of using Micro-dosimetric methods for dosimetry illustrated. (authors)

Thermoluminescence albedo-neutron dosimetry

International Nuclear Information System (INIS)

Strand, T.; Storruste, A.

1986-10-01

The report discusses neutron detection with respect to dosimetry and compares different thermoluminescent dosimetry materials for neutron dosimetry. Construction and calibration of a thermoluminescence albedo neutron dosemeter, developed by the authors, is described

Applications of gel dosimetry

International Nuclear Information System (INIS)

Ibbott, Geoffrey S

2004-01-01

Gel dosimetry has been examined as a clinical dosimeter since the 1950s. During the last two decades, however, a rapid increase in the number of investigators has been seen, and the body of knowledge regarding gel dosimetry has expanded considerably. Gel dosimetry is still considered a research project, and the introduction of this tool into clinical use is proceeding slowly. This paper will review the characteristics of gel dosimetry that make it desirable for clinical use, the postulated and demonstrated applications of gel dosimetry, and some complications, set-backs, and failures that have contributed to the slow introduction into routine clinical use

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ({sup 58}Co, {sup 60}Co, {sup 54}Mn, and {sup 59}Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs.

Technical basis for internal dosimetry at Hanford

Energy Technology Data Exchange (ETDEWEB)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products (/sup 58/Co, /sup 60/Co, /sup 54/Mn, and /sup 59/Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs.

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1991-07-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium,. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation and bioassay follow-up treatment. 78 refs., 35 figs., 115 tabs

Technical basis for internal dosimetry at Hanford

International Nuclear Information System (INIS)

Sula, M.J.; Carbaugh, E.H.; Bihl, D.E.

1989-04-01

The Hanford Internal Dosimetry Program, administered by Pacific Northwest Laboratory for the US Department of Energy, provides routine bioassay monitoring for employees who are potentially exposed to radionuclides in the workplace. This report presents the technical basis for routine bioassay monitoring and the assessment of internal dose at Hanford. The radionuclides of concern include tritium, corrosion products ( 58 Co, 60 Co, 54 Mn, and 59 Fe), strontium, cesium, iodine, europium, uranium, plutonium, and americium. Sections on each of these radionuclides discuss the sources and characteristics; dosimetry; bioassay measurements and monitoring; dose measurement, assessment, and mitigation; and bioassay follow-up treatment. 64 refs., 42 figs., 118 tabs

Programmers's manual for the SYVAC geosphere program GEO2

International Nuclear Information System (INIS)

Oldfield, S.G.; Broyd, T.W.

1983-11-01

A Programmers' Manual for the computer model GEO2, of radionuclide migration through an unsaturated multi-layered rock strata GEO2 uses a numerical solution to equations of one dimensional flow and transport of radionuclides in the groundwater, including the effects of linear equilibrium sorption (for porous or fractured media), linear dispersion and chain decay for arbitrary chain lengths, The model is designed to be incorporated into the SYVAC (SYstems Variability Analysis Code) computer program the function of which is to perform generic uncertainty assessments on hypothetical vault-geosphere-biosphere combinations, taking into account parameter variability and uncertainty. (author)

GANDALF: users' manual

International Nuclear Information System (INIS)

Strout, R.E. II; Beach, J.L.

1977-01-01

The GANDALF computer code was written to calculate neutron dose equivalent given the pulse-height data obtained by using a Linear Energy Transfer (LET) proportional counter. The code also uses pre- and/or post-calibration spectra, from an alpha source, to determine a calibration factor in keV/μ/channel. Output from the code consists of the effective radius of the detection chamber in microns, a calibration factor in keV/μ/channel, and the total dose and dose equivalent in rad or rem between any two LET energies by using the equations by Attix and Roesch [Radiation Dosimetry, 1, 71 (1968)]. This report is a user's manual and is not intended as anything else, and assumes that the user has a basic knowledge of the LLL Octopus timesharing system. However, a very brief description of how the code operates is included

MO-B-BRB-04: 3D Dosimetry in End-To-End Dosimetry QA

Energy Technology Data Exchange (ETDEWEB)

Ibbott, G. [UT MD Anderson Cancer Center (United States)

2016-06-15

Full three-dimensional (3D) dosimetry using volumetric chemical dosimeters probed by 3D imaging systems has long been a promising technique for the radiation therapy clinic, since it provides a unique methodology for dose measurements in the volume irradiated using complex conformal delivery techniques such as IMRT and VMAT. To date true 3D dosimetry is still not widely practiced in the community; it has been confined to centres of specialized expertise especially for quality assurance or commissioning roles where other dosimetry techniques are difficult to implement. The potential for improved clinical applicability has been advanced considerably in the last decade by the development of improved 3D dosimeters (e.g., radiochromic plastics, radiochromic gel dosimeters and normoxic polymer gel systems) and by improved readout protocols using optical computed tomography or magnetic resonance imaging. In this session, established users of some current 3D chemical dosimeters will briefly review the current status of 3D dosimetry, describe several dosimeters and their appropriate imaging for dose readout, present workflow procedures required for good dosimetry, and analyze some limitations for applications in select settings. We will review the application of 3D dosimetry to various clinical situations describing how 3D approaches can complement other dose delivery validation approaches already available in the clinic. The applications presented will be selected to inform attendees of the unique features provided by full 3D techniques. Learning Objectives: L. John Schreiner: Background and Motivation Understand recent developments enabling clinically practical 3D dosimetry, Appreciate 3D dosimetry workflow and dosimetry procedures, and Observe select examples from the clinic. Sofie Ceberg: Application to dynamic radiotherapy Observe full dosimetry under dynamic radiotherapy during respiratory motion, and Understand how the measurement of high resolution dose data in an

Effect of processor temperature on film dosimetry

International Nuclear Information System (INIS)

Srivastava, Shiv P.; Das, Indra J.

2012-01-01

Optical density (OD) of a radiographic film plays an important role in radiation dosimetry, which depends on various parameters, including beam energy, depth, field size, film batch, dose, dose rate, air film interface, postexposure processing time, and temperature of the processor. Most of these parameters have been studied for Kodak XV and extended dose range (EDR) films used in radiation oncology. There is very limited information on processor temperature, which is investigated in this study. Multiple XV and EDR films were exposed in the reference condition (d max. , 10 × 10 cm 2 , 100 cm) to a given dose. An automatic film processor (X-Omat 5000) was used for processing films. The temperature of the processor was adjusted manually with increasing temperature. At each temperature, a set of films was processed to evaluate OD at a given dose. For both films, OD is a linear function of processor temperature in the range of 29.4–40.6°C (85–105°F) for various dose ranges. The changes in processor temperature are directly related to the dose by a quadratic function. A simple linear equation is provided for the changes in OD vs. processor temperature, which could be used for correcting dose in radiation dosimetry when film is used.

The Radiological Safety Analysis Computer Program (RSAC-5) user's manual

International Nuclear Information System (INIS)

Wenzel, D.R.

1994-02-01

The Radiological Safety Analysis Computer Program (RSAC-5) calculates the consequences of the release of radionuclides to the atmosphere. Using a personal computer, a user can generate a fission product inventory from either reactor operating history or nuclear criticalities. RSAC-5 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated through the inhalation, immersion, ground surface, and ingestion pathways. RSAC+, a menu-driven companion program to RSAC-5, assists users in creating and running RSAC-5 input files. This user's manual contains the mathematical models and operating instructions for RSAC-5 and RSAC+. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-5 and RSAC+. These programs are designed for users who are familiar with radiological dose assessment methods

Aircraft operations management manual

Science.gov (United States)

1992-01-01

The NASA aircraft operations program is a multifaceted, highly diverse entity that directly supports the agency mission in aeronautical research and development, space science and applications, space flight, astronaut readiness training, and related activities through research and development, program support, and mission management aircraft operations flights. Users of the program are interagency, inter-government, international, and the business community. This manual provides guidelines to establish policy for the management of NASA aircraft resources, aircraft operations, and related matters. This policy is an integral part of and must be followed when establishing field installation policy and procedures covering the management of NASA aircraft operations. Each operating location will develop appropriate local procedures that conform with the requirements of this handbook. This manual should be used in conjunction with other governing instructions, handbooks, and manuals.

The Montana Rivers Information System: Edit/entry program user`s manual

Energy Technology Data Exchange (ETDEWEB)

1992-07-01

The Montana Rivers Information System (MRIS) was initiated to assess the state`s fish, wildlife, and recreation value; and natural cultural and geologic features. The MRIS is now a set of data bases containing part of the information in the Natural Heritage Program natural features and threatened and endangered species data bases. The purpose of this User`s Manual is to: (1) describe to the user how to maintain the MRIS database of their choice by updating, changing, deleting, and adding records using the edit/entry programs; and (2) provide to the user all information and instructions necessary to complete data entry into the MRIS databases.

BASACF, Integral Neutron Spectra Adjustment and Dosimetry

International Nuclear Information System (INIS)

Tichy, Milos

1996-01-01

1 - Description of program or function: Adjustment of a neutron spectrum based on integral detector measurements and calculation of an integral dosimetric quantity (integral flux, d.p.a., dose equivalent) and its variance. The program requires measured data (activities and their covariance matrix) and a priori information (spectrum, dosimetry cross sections, integral quantity conversion factor and their covariance matrices). All a priori covariance matrices can be read in from a file prepared by some other code or can be generated by means of three different methods (by subroutines included in the program). A subroutine which can normalize the a priori flux to measured data is also included. The program provides also adjusted dosimetry cross sections (with covariance matrix) so that it can be used for an adjustment of cross sections (or response functions of e.g. Bonner balls) by measurements in well-known neutron spectra. 2 - Method of solution: Bayesian theorem on conditional probability applied to linearized relation between activities, dosimetry cross sections and flux. All probability distributions are supposed to be normal and this supposition leads to minimizing of the same functional as least squares method (STAY'SL). This task is solved by a covariance filter method which avoids any matrix inversion and is numerically robust and stable. 3 - Restrictions on the complexity of the problem: This version can use 45 energy groups and 5 detectors and occupies 310 kB of main memory. This restriction can be modified according to available memory. The covariance matrix of activities is supposed diagonal. A solution is produced for any set of input data but in the case of non-consistent data, when measured activities do not match the a priori flux, the solution is not very meaningful

Dosimetry quality assurance in Martin Marietta Energy Systems' centralized external dosimetry system

International Nuclear Information System (INIS)

Souleyrette, M.L.

1992-01-01

External dosimetry needs at the four Martin Marietta Energy Systems facilities are served by Energy Systems Centralized External Dosimetry System (CEDS). The CEDS is a four plant program with four dosimeter distribution centers and two dosimeter processing centers. Each plant has its own distribution center, while processing centers are located at ORNL and the Y-12 Plant. The program has been granted accreditation by the Department of Energy Laboratory Accreditation Program (DOELAP). The CEDS is a TLD based system which is responsible for whole-body beta-gamma, neutron, and extremity monitoring. Beta-gamma monitoring is performed using the Harshaw/Solon Technologies model 8805 dosimeter. Effective October 1, 1992 the standard silver mylar has been replaced with an Avery mylar foil blackened on the underside with ink. This was done in an effort to reduce the number of light induced suspect readings. At this time we have little operational experience with the new blackened mylars-The CEDS neutron dosimeter is the Harshaw model 8806B. This card/holder configuration contains two TLD-600/TLD-700 chip pairs; one pair is located beneath a cadmium filter and one pair is located beneath a plastic filter. In routine personnel monitoring the CEDS neutron dosimeter is always paired with a CEDS beta-gamma dosimeter.The CEDS extremity dosimeter is composed of a Harshaw thin TLD-700 dosiclip placed inside a Teledyne RB-4 finger sachet. The finger sachet provides approximately 7 mg/cm 2 filtration over the chip. A teflon ring surrounds the dosiclip to help prevent tearing of the vinyl sachet

Analytical methods manual for the Mineral Resource Surveys Program, U.S. Geological Survey

Science.gov (United States)

Arbogast, Belinda F.

1996-01-01

The analytical methods validated by the Mineral Resource Surveys Program, Geologic Division, is the subject of this manual. This edition replaces the methods portion of Open-File Report 90-668 published in 1990. Newer methods may be used which have been approved by the quality assurance (QA) project and are on file with the QA coordinator.This manual is intended primarily for use by laboratory scientists; this manual can also assist laboratory users to evaluate the data they receive. The analytical methods are written in a step by step approach so that they may be used as a training tool and provide detailed documentation of the procedures for quality assurance. A "Catalog of Services" is available for customer (submitter) use with brief listings of:the element(s)/species determined,method of determination,reference to cite,contact person,summary of the technique,and analyte concentration range.For a copy please contact the Branch office at (303) 236-1800 or fax (303) 236-3200.

Reactor Dosimetry State of the Art 2008

Science.gov (United States)

Voorbraak, Wim; Debarberis, Luigi; D'Hondt, Pierre; Wagemans, Jan

2009-08-01

from the first-generation nuclear-powered submarines by gamma scanning / A. F. Usatyi. L. A. Serdyukova and B. S. Stepennov -- Oral session 3: Power plant surveillance. Upgraded neutron dosimetry procedure for VVER-440 surveillance specimens / V. Kochkin ... [et al.]. Neutron dosimetry on the full-core first generation VVER-440 aimed to reactor support structure load evaluation / P. Borodkin ... [et al.]. Ex-vessel neutron dosimetry programs for PWRs in Korea / C. S. Yoo. B. C. Kim and C. C. Kim. Comparison of irradiation conditions of VVER-1000 reactor pressure vessel and surveillance specimens for various core loadings / V. N. Bukanov ... [et al.]. Re-evaluation of dosimetry in the new surveillance program for the Loviisa 1 VVER-440 reactor / T. Serén -- Oral session 4: Benchmarks, intercomparisons and adjustment methods. Determination of the neutron parameter's uncertainties using the stochastic methods of uncertainty propagation and analysis / G. Grégoire ... [et al.].Covariance matrices for calculated neutron spectra and measured dosimeter responses / J. G. Williams ... [et al.]. The role of dosimetry at the high flux reactor / S. C. van der Marek ... [et al.]. Calibration of a manganese bath relative to Cf-252 nu-bar / D. M. Gilliam, A. T. Yue and M. Scott Dewey. Major upgrade of the reactor dosimetry interpretation methodology used at the CEA: general principle / C. Destouches ... [et al.] -- Oral session 5: power plant surveillance. The role of ex-vessel neutron dosimetry in reactor vessel surveillance in South Korea / B.-C. Kim ... [et al.]. Spanish RPV surveillance programmes: lessons learned and current activities / A. Ballesteros and X. Jardí. Atucha I nuclear power plant extended dosimetry and assessment / H. Blaumann ... [et al.]. Monitoring of radiation load of pressure vessels of Russian VVER in compliance with license amendments / G. Borodkin ... [et al.] -- Poster session 2: Test reactors, accelerators and advanced systems; cross sections, nuclear

Using a profiling process to insure program quality: Volume I - a self-instructional manual

Energy Technology Data Exchange (ETDEWEB)

Kaser, J.S.; Roody, D.S.; Raizen, S.A.

1996-11-01

Between 1990 and 1995 the U.S. Department of Energy (DOE) and the National Center for Improving Science Education (National Center) developed a system for ongoing evaluation of K-12 educational programs in the DOE-supported national energy Laboratories. As part of the formative evaluation component of this collaborative endeavor, field staff in the Laboratories began creating profiles of their programs. However, many individuals within DOE Headquarters were not familiar with this profiling process and were unprepared to use the valuable information that the profiles generated. This manual was produced to orient Headquarters staff to profiling. It focuses on how Headquarters staff can use the profiling process to help their funded programs establish and/or maintain high quality. Its purpose, then, is not to train Headquarters staff to become proficient in profiling, but to show them how to draw on the Laboratories` use of profiling to bring about program improvement. Profiling is the process of systematically examining and describing a program`s elements against a set of components that define Effective Practice. The instrument used to capture the data for analysis is called a template, and most of this manual focuses on the templates and how to read and interpret them. However, since it is important to understand these data in context, the authors also describe what should accompany each template in a complete profiling packet and offer guidelines for reviewing complete packets and providing feedback to program managers.

A parameterization method and application in breast tomosynthesis dosimetry

Energy Technology Data Exchange (ETDEWEB)

Li, Xinhua; Zhang, Da; Liu, Bob [Division of Diagnostic Imaging Physics and Webster Center for Advanced Research and Education in Radiation, Department of Radiology, Massachusetts General Hospital, Boston, Massachusetts 02114 (United States)

2013-09-15

Purpose: To present a parameterization method based on singular value decomposition (SVD), and to provide analytical parameterization of the mean glandular dose (MGD) conversion factors from eight references for evaluating breast tomosynthesis dose in the Mammography Quality Standards Act (MQSA) protocol and in the UK, European, and IAEA dosimetry protocols.Methods: MGD conversion factor is usually listed in lookup tables for the factors such as beam quality, breast thickness, breast glandularity, and projection angle. The authors analyzed multiple sets of MGD conversion factors from the Hologic Selenia Dimensions quality control manual and seven previous papers. Each data set was parameterized using a one- to three-dimensional polynomial function of 2–16 terms. Variable substitution was used to improve accuracy. A least-squares fit was conducted using the SVD.Results: The differences between the originally tabulated MGD conversion factors and the results computed using the parameterization algorithms were (a) 0.08%–0.18% on average and 1.31% maximum for the Selenia Dimensions quality control manual, (b) 0.09%–0.66% on average and 2.97% maximum for the published data by Dance et al. [Phys. Med. Biol. 35, 1211–1219 (1990); ibid. 45, 3225–3240 (2000); ibid. 54, 4361–4372 (2009); ibid. 56, 453–471 (2011)], (c) 0.74%–0.99% on average and 3.94% maximum for the published data by Sechopoulos et al. [Med. Phys. 34, 221–232 (2007); J. Appl. Clin. Med. Phys. 9, 161–171 (2008)], and (d) 0.66%–1.33% on average and 2.72% maximum for the published data by Feng and Sechopoulos [Radiology 263, 35–42 (2012)], excluding one sample in (d) that does not follow the trends in the published data table.Conclusions: A flexible parameterization method is presented in this paper, and was applied to breast tomosynthesis dosimetry. The resultant data offer easy and accurate computations of MGD conversion factors for evaluating mean glandular breast dose in the MQSA

Dosimetry Service

CERN Multimedia

2005-01-01

Please remember to read your dosimeter at least once a month. Regular read-outs are vital to ensure that your personal dose is periodically monitored. Dosimeters should be read even if you have not visited the controlled areas. Dosimetry Service - Tel. 72155 http://cern.ch/rp-dosimetry

National Household Education Surveys Program of 2012: Data File User's Manual. Parent and Family Involvement in Education Survey. Early Childhood Program Participation Survey. NCES 2015-030

Science.gov (United States)

McPhee, C.; Bielick, S.; Masterton, M.; Flores, L.; Parmer, R.; Amchin, S.; Stern, S.; McGowan, H.

2015-01-01

The 2012 National Household Education Surveys Program (NHES:2012) Data File User's Manual provides documentation and guidance for users of the NHES:2012 data files. The manual provides information about the purpose of the study, the sample design, data collection procedures, data processing procedures, response rates, imputation, weighting and…

Thermoluminescence in medical dosimetry

International Nuclear Information System (INIS)

Rivera, T.

2011-10-01

The dosimetry by thermoluminescence (Tl) is applied in the entire world for the dosimetry of ionizing radiations specially to personal and medical dosimetry. This dosimetry method has been very interesting for measures in vivo because the Tl dosimeters have the advantage of being very sensitive in a very small volume and they are also equivalent to tissue and they do not need additional accessories (for example, cable, electrometer, etc.) The main characteristics of the diverse Tl materials to be used in the radiation measures and practical applications are: the Tl curve, the share homogeneity, the signal stability after the irradiation, precision and exactitude, the response in function with the dose and the energy influence. In this work a brief summary of the advances of the radiations dosimetry is presented by means of the thermally stimulated luminescence and its application to the dosimetry in radiotherapy. (Author)

Radiation dosimetry for the space shuttle program

International Nuclear Information System (INIS)

Jones, K.L.; Richmond, R.G.; Cash, B.L.

1985-01-01

Radiation measurements aboard the Space Shuttle are made to record crew doses for medical records, to verify analytical shielding calculations used in dose predictions and to provide dosimetry support for radiation sensitive payloads and experiments. Low cost systems utilizing thermoluminescent dosimeters, nuclear track detectors and activation foils have been developed to fulfill these requirements. Emphasis has been placed on mission planning and dose prediction. As a result, crew doses both inside the orbiter and during extra-vehicular activities have been reasonable low. Brief descriptions of the space radiation environment, dose prediction models, and radiation measurement systems are provided, along with a summary of the results for the first fourteen Shuttle flights

Neutron dosimetry - A review

Energy Technology Data Exchange (ETDEWEB)

Baum, J W

1955-03-29

This review summarizes information on the following subjects: (1) physical processes of importance in neutron dosimetry; (2) biological effects of neutrons; (3) neutron sources; and (4) instruments and methods used in neutron dosimetry. Also, possible improvements in dosimetry instrumentation are outlined and discussed. (author)

JENDL Dosimetry File

International Nuclear Information System (INIS)

Nakazawa, Masaharu; Iguchi, Tetsuo; Kobayashi, Katsuhei; Iwasaki, Shin; Sakurai, Kiyoshi; Ikeda, Yujiro; Nakagawa, Tsuneo.

1992-03-01

The JENDL Dosimetry File based on JENDL-3 was compiled and integral tests of cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Data stored in the JENDL Dosimetry File are the cross sections and their covariance data for 61 reactions. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. For some reactions, data were adopted from other evaluated data files. The data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-5 format. In order to confirm reliability of the data, several integral tests were carried out; comparison with the data in IRDF-85 and average cross sections measured in fission neutron fields, fast reactor spectra, DT neutron fields and Li(d, n) neutron fields. As a result, it has been found that the JENDL Dosimetry File gives better results than IRDF-85 but there are some problems to be improved in future. The contents of the JENDL Dosimetry File and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form. (author) 76 refs

JENDL Dosimetry File

Energy Technology Data Exchange (ETDEWEB)

Nakazawa, Masaharu; Iguchi, Tetsuo [Tokyo Univ. (Japan). Faculty of Engineering; Kobayashi, Katsuhei [Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst.; Iwasaki, Shin [Tohoku Univ., Sendai (Japan). Faculty of Engineering; Sakurai, Kiyoshi; Ikeda, Yujior; Nakagawa, Tsuneo [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

1992-03-15

The JENDL Dosimetry File based on JENDL-3 was compiled and integral tests of cross section data were performed by the Dosimetry Integral Test Working Group of the Japanese Nuclear Data Committee. Data stored in the JENDL Dosimetry File are the cross sections and their covariance data for 61 reactions. The cross sections were mainly taken from JENDL-3 and the covariances from IRDF-85. For some reactions, data were adopted from other evaluated data files. The data are given in the neutron energy region below 20 MeV in both of point-wise and group-wise files in the ENDF-5 format. In order to confirm reliability of the data, several integral tests were carried out; comparison with the data in IRDF-85 and average cross sections measured in fission neutron fields, fast reactor spectra, DT neutron fields and Li(d,n) neutron fields. As a result, it has been found that the JENDL Dosimetry File gives better results than IRDF-85 but there are some problems to be improved in future. The contents of the JENDL Dosimetry File and the results of the integral tests are described in this report. All of the dosimetry cross sections are shown in a graphical form.

Dosimetry Service

CERN Multimedia

2005-01-01

Please remember to read your dosimeter at least once a month. Regular read-outs are vital to ensure that your personal dose is periodically monitored. Dosimeters should be read even if you have not visited the controlled areas. Dosimetry Service - Tel. 7 2155 http://cern.ch/rp-dosimetry

Dosimetry Service

CERN Multimedia

Dosimetry Service

2005-01-01

Please remember to read your dosimeter at least once a month. Regular read-outs are vital to ensure that your personal dose is periodically monitored. Dosimeters should be read even if you have not visited the controlled areas. Dosimetry Service Tel. 7 2155 http://cern.ch/rp-dosimetry

Dosimetry for radiation processing

DEFF Research Database (Denmark)

Miller, Arne

1986-01-01

During the past few years significant advances have taken place in the different areas of dosimetry for radiation processing, mainly stimulated by the increased interest in radiation for food preservation, plastic processing and sterilization of medical products. Reference services both...... and sterilization dosimetry, optichromic dosimeters in the shape of small tubes for food processing, and ESR spectroscopy of alanine for reference dosimetry. In this paper the special features of radiation processing dosimetry are discussed, several commonly used dosimeters are reviewed, and factors leading...

Development of A-bomb survivor dosimetry

International Nuclear Information System (INIS)

Kerr, G.D.

1995-01-01

An all important datum in risk assessment is the radiation dose to individual survivors of the bombings in Hiroshima and Nagasaki. The first set of dose estimates for survivors was based on a dosimetry system developed in 1957 by the Oak Ridge National Laboratory (ORNL). These Tentative 1957 Doses (T57D) were later replaced by a more extensive and refined set of Tentative 1965 Doses (T65D). The T65D system of dose estimation for survivors was also developed at ORNL and served as a basis for risk assessment throughout the 1970s. In the late 1970s, it was suggested that there were serious inadequacies with the T65D system, and these inadequacies were the topic of discussion at two symposia held in 1981. In early 1983, joint US- Japan research programs were established to conduct a thorough review of all aspects of the radiation dosimetry for the Hiroshima and Nagasaki A-bomb survivors. A number of important contributions to this review were made by ORNL staff members. The review was completed in 1986 and a new Dosimetry System 1986 (DS86) was adopted for use. This paper discusses the development of the various systems of A-bomb survivor dosimetry, and the status of the current DS86 system as it is being applied in the medical follow-up studies of the A-bomb survivors and their offspring

Development of A-bomb survivor dosimetry

Energy Technology Data Exchange (ETDEWEB)

Kerr, G.D.

1995-12-31

An all important datum in risk assessment is the radiation dose to individual survivors of the bombings in Hiroshima and Nagasaki. The first set of dose estimates for survivors was based on a dosimetry system developed in 1957 by the Oak Ridge National Laboratory (ORNL). These Tentative 1957 Doses (T57D) were later replaced by a more extensive and refined set of Tentative 1965 Doses (T65D). The T65D system of dose estimation for survivors was also developed at ORNL and served as a basis for risk assessment throughout the 1970s. In the late 1970s, it was suggested that there were serious inadequacies with the T65D system, and these inadequacies were the topic of discussion at two symposia held in 1981. In early 1983, joint US- Japan research programs were established to conduct a thorough review of all aspects of the radiation dosimetry for the Hiroshima and Nagasaki A-bomb survivors. A number of important contributions to this review were made by ORNL staff members. The review was completed in 1986 and a new Dosimetry System 1986 (DS86) was adopted for use. This paper discusses the development of the various systems of A-bomb survivor dosimetry, and the status of the current DS86 system as it is being applied in the medical follow-up studies of the A-bomb survivors and their offspring.

EDISTR: a computer program to obtain a nuclear decay data base for radiation dosimetry

International Nuclear Information System (INIS)

Dillman, L.T.

1980-01-01

This report provides documentation for the computer program EDISTR. EDISTR uses basic radioactive decay data from the Evaluated Nuclear Structure Data File developed and maintained by the Nuclear Data Project at the Oak Ridge National Laboratory as input, and calculates the mean energies and absolute intensities of all principal radiations associated with the radioactive decay of a nuclide. The program is intended to provide a physical data base for internal dosimetry calculations. The principal calculations performed by EDISTR are the determination of (1) the average energy of beta particles in a beta transition, (2) the beta spectrum as function of energy, (3) the energies and intensities of x-rays and Auger electrons generated by radioactive decay processes, (4) the bremsstrahlung spectra accompanying beta decay and monoenergetic Auger and internal conversion electrons, and (5) the radiations accompanying spontaneous fission. This report discusses the theoretical and empirical methods used in EDISTR and also practical aspects of the computer implementation of the theory. Detailed instructions for preparing input data for the computer program are included, along with examples and discussion of the output data generated by EDISTR

Experiences in the continuous improvement of quality assurance of the dosimetry services of SLDC-MD-ININ

International Nuclear Information System (INIS)

Tovar M, V. M.; Vergara M, F.; Perez M, V.; Anaya M, R.; Cejudo A, J.; Alvarez R, J. T.; Arenas O, A.; Cruz F, C.

2010-09-01

From 2003 the Secondary Laboratory of Dosimetric Calibration (SLDC) of Metrology Department of Ionizing Radiations (MD), has complemented the Quality Manual of National Institute of Nuclear Research (ININ) according to the standard ISO 9001: 2000. However, due to that the National Center of Metrology of Mexico delegates its functions in the dosimetry and activity area for the field of the ionizing radiations to the ININ: one of the requirements so that the ININ has been designated as -Declared Institute- before the International Office of Weights and Measurements, it is to demonstrate before the Inter-American System of Metrology that the quality system of the SLDC fulfills the standard ISO/IEC 17025: 2005, satisfied this requirement the Inter-American System of Metrology in their meeting of evaluation of quality systems, Ottawa (2007) grants a certification document to the SLDC that guarantees their capacities of calibration measurements for dosimetry services. Concretely, inside the standard activities ISO 9000 with respect to the point 8 on measurement, analysis and improvement the Management of Quality Assurance of ININ carries out at year two interns auditing and every month is given continuation to the non conformities detected in the procedures that support the services of the SLDC for dosimetry with purposes of radiological protection and clinical dosimetry. (Author)

Perofrmance testing of personnel dosimetry services. Final report of a two-year pilot study, October 1977-September 1979

International Nuclear Information System (INIS)

Plato, P.; Hudson, G.

1980-01-01

A two-year pilot study was conducted of the Health Physics Society Standards Committee (HPSSC) Standard titled, Criteria for Testing Personnel Dosimetry Performance. The objectives of the pilot study were: to give processors an opportunity to correct any problems that are uncovered; to develop operational and administrative prodedures to be used later by a permanent testing laboratory; and to determine whether the proposed HPSSC Standard provides an adequate and practical test of dosimetry performance. Fifty-nine dosimetry processors volunteered to submit dosimeters for test irradiations according to the requirements of the HPSSC Standard. The feasibility of using the HPSSC Standard for a future mandatory testing program for personnel dosimetry processors is discussed. This report shows the results of the pilot study and contains recommendations for revisions in the Standard that will make a mandatory testing program useful to regulatory agencies, dosimetry processors, and radiation workers that use personnel dosimeters

Cuban experience in dosimetry quality audit program in radiotherapy

International Nuclear Information System (INIS)

Alonso-Samper, J.L.; Dominguez, L.; Yip, F.G.; Laguardia, R.A.; Morales, J.L.; Larrinaga, E.

2002-01-01

Full text: Five years ago we started a National Program of Quality Assurance in Radiotherapy. This program was possible thanks to the cooperation between the Cuban Ministry of Health and the International Atomic Energy Agency (IAEA) in the Projects ARCAL XXX and CUB/6/011. In the framework of these projects a total of ten complete dosimetry set were acquired and a large number of medical physicists were trained. At the same time, the Cuban side signed a contract for nine cobalt units, which have been gradually installed and all of them are running at the moment. During more than 20 years Cuba has taken part in the IAEA/WHO TLD postal dose audit programs and our results have been inside the (+/-)5 % acceptance limit. Cuba also joined the IAEA Coordinated Research Program E2 40 07, to extend at a national level the experience of the TLD based audits, using the capability of our SSDL to measure TLD. At the same time the work of the already existing External Audit Group was consolidated. The National Program of Quality Assurance in Radiotherapy works on base of external on-site visits. The main objective is to avoid any accident and to improve the quality of the RT treatments. Every year each Radiotherapy service is visited by a qualified team of physicists with the objective to check the physical aspects of the quality of the RT treatment, it includes: Documents and Records, safety, mechanical and dosimetric aspects, treatment planning, also we use the fixed depth phantom to simulate and verify several techniques. Although the TLD postal audit results are acceptable, in our QA audits we have detected some problems that may deviate the dose delivery to patients in more than 5%, examples of which are: Not all the clinical plans are redundantly checked by an independent person; Not all the controls (daily, monthly and annual) are performed according to the protocols approved by the National QA Committee. In some cases the controls are not well recorded; Clinical

Alanine dosimetry for clinical applications. Proceedings

International Nuclear Information System (INIS)

Anton, M.

2006-05-01

The following topics are dealt with: Therapy level alanine dosimetry at the UK Nationational Physical Laboratory, alanine as a precision validation tool for reference dosimetry, composition of alanine pellet dosimeters, the angular dependence of the alanine ESR spectrum, the CIAE alanine dosimeter for radiotherapy level, a correction for temporal evolution effects in alanine dosimetry, next-generation services foe e-traceability to ionization radiation national standards, establishing e-traceability to HIST high-dose measurement standards, alanine dosimetry of dose delivery from clinical accelerators, the e-scan alanine dosimeter reader, alanine dosimetry at ISS, verification of the integral delivered dose for IMRT treatment in the head and neck region with ESR/alanine dosimetry, alanine dosimetry in helical tomotherapy beams, ESR dosimetry research and development at the University of Palermo, lithium formate as a low-dose EPR radiation dosimeter, sensitivity enhancement of alanine/EPR dosimetry. (HSI)

Commissioning dosimetry and in situ dose mapping of a semi-industrial Cobalt-60 gamma-irradiation facility using Fricke and Ceric-cerous dosimetry system and comparison with Monte Carlo simulation data

Science.gov (United States)

Mortuza, Md Firoz; Lepore, Luigi; Khedkar, Kalpana; Thangam, Saravanan; Nahar, Arifatun; Jamil, Hossen Mohammad; Bandi, Laxminarayan; Alam, Md Khorshed

2018-03-01

Characterization of a 90 kCi (3330 TBq), semi-industrial, cobalt-60 gamma irradiator was performed by commissioning dosimetry and in-situ dose mapping experiments with Ceric-cerous and Fricke dosimetry systems. Commissioning dosimetry was carried out to determine dose distribution pattern of absorbed dose in the irradiation cell and products. To determine maximum and minimum absorbed dose, overdose ratio and dwell time of the tote boxes, homogeneous dummy product (rice husk) with a bulk density of 0.13 g/cm3 were used in the box positions of irradiation chamber. The regions of minimum absorbed dose of the tote boxes were observed in the lower zones of middle plane and maximum absorbed doses were found in the middle position of front plane. Moreover, as a part of dose mapping, dose rates in the wall positions and some selective strategic positions were also measured to carry out multiple irradiation program simultaneously, especially for low dose research irradiation program. In most of the cases, Monte Carlo simulation data, using Monte Carlo N-Particle eXtended code version MCNPX 2.7., were found to be in congruence with experimental values obtained from Ceric-cerous and Fricke dosimetry; however, in close proximity positions from the source, the dose rate variation between chemical dosimetry and MCNP was higher than distant positions.

Developments in physical dosimetry and radiation protection; Entwicklungen in der physikalischen Dosimetrie im Strahlenschutz

Energy Technology Data Exchange (ETDEWEB)

Fiebich, Martin [Technische Hochschule Mittelhessen, Giessen (Germany). Inst. fuer Medizinische Physik und Strahlenschutz

2017-07-01

In the frame of physical dosimetry new dose units have been defined: the depth personal dose (equivalent dose in 10 mm depth) and the surface personal dose (equivalent dose in 0.07 mm depth). Physical dosimetry is applied for the determination of occupational radiation exposure, the radiation protected area control, the estimation of radiation exposure of patients during radiotherapy, for quality assurance and in research projects and optimization challenges. Developments have appeared with respect to punctual measuring chambers, eye lens dosimetry, OSL (optically stimulated luminescence) dosimetry, real-time dosimetry and Monte Carlo methods. New detection limits of about 1 micro Gy were reached.

Radiographic angles in hallux valgus: differences between measurements made manually and with a computerized program.

Science.gov (United States)

Piqué-Vidal, Carlos; Maled-García, Ignaci; Arabi-Moreno, Juanjo; Vila, Joan

2006-03-01

The objective of this study was to compare angular measurements in the evaluation of hallux valgus deformities using a goniometer and a computerized program to assess degree of concordance between the two methods and determine the reliability of manual measurements. Angles measured included the hallux valgus angle (HVA), the intermetatarsal angle (IMA), the distal metatarsal articular angle (DMAA), and the proximal phalangeal articular angle (PPAA), also called the hallux valgus interphalangeus angle or interphalangeal angle. Measurements were made on preoperative weightbearing radiographs in 176 patients with symptomatic hallux valgus. Manual measurements were made with a goniometer by an orthopaedic surgeon. An independent experienced technician used digitized images to perform angular measurements with the Autocad software program (Autodesk Inc., San Rafael, CA). HVA values obtained with the two techniques were similar. However, significantly higher mean values were obtained with the Autocad for the IMA and PPAA measurements, and higher mean values were obtained for the DMAA measurement with the manual technique. Whereas differences were more or less randomly distributed for the HVA, in the remaining patients, measurements were clearly related to the measurement technique, i.e., for the DMAA, the manual technique had a tendency to show higher values, and for the IMA and PPAA the manual technique showed lower values than the computer. Correlations between both techniques for the different angular measurements were as follows: HVA, -0.179 (p = 0.018); DMMA, -0.294 (p Autocad angular measurements was excellent for the HVA (ICC = 0.89) and DMAA (ICC = 0.80) and very poor for the PPAA (ICC = 0.11) and IMA (ICC = 0.42). Angular measurements made on weightbearing radiographs with the Autocad in patients with hallux valgus deformities were more reliable than those made with a goniometer. Although for large angles, such as HVA and DMAA, results obtained with both

Personnel neutron dosimetry

International Nuclear Information System (INIS)

Hankins, D.

1982-04-01

This edited transcript of a presentation on personnel neutron discusses the accuracy of present dosimetry practices, requirements, calibration, dosemeter types, quality factors, operational problems, and dosimetry for a criticality accident. 32 figs

Personal dosimetry performance testing in the United States

International Nuclear Information System (INIS)

Soares, C.G.

2005-01-01

Full text: The basis for personal dosimetry performance testing in the United States is ANSI/HPS N13.11 (2002). Now in its third edition, this standard has been in place since 1983. Testing under this standard is administered by the National Voluntary Accreditation Program (NVLAP), and accreditation of dosimetry processors under this program is required by US Nuclear Regulatory Commission (NRC) regulations. The US Department of Energy (DOE) also maintains a testing program for its laboratories and contractors, administered by the Department of Energy Laboratory Accreditation Program (DOELAP). A focus in recent years has been the modification of ANSI/HPS N13.11 to allow acceptance by both testing programs in order to bring harmonization to US personal dosimeter processing testing. The testing philosophy of ANSI N13.11 has always combined elements of type testing and routine performance testing and is thus different from the testing philosophy used in the rest of the world. This unique philosophy is explored in detail in this presentation, along with trends in the development of the document to its present state. In addition, a look will be taken at what the future holds for the next revision of the document, scheduled to begin in 2005. (author)

Quality assurance program in the External dosimetry laboratory of the CPHR; Programa de aseguramiento de la calidad en el laboratorio de dosimetria externa del CPHR

Energy Technology Data Exchange (ETDEWEB)

Molina P, D.; Pernas S, R.; Martinez H, E.; Cardenas H, J. [Centro de Proteccion e Higiene de las Radiaciones, Calle 20 No. 4113 e/41 y 47. Playa, C.P. 11300, A.P. 6195, C.P. 10600 La Habana (Cuba)

2006-07-01

From 1999 the Laboratory of External Dosimetry of the Radiation Protection and Hygiene Center comes applying in its service of personal dosimetry a Program of Quality Assurance. This program was designed according to the recommendations of national and international organizations as the National Assuring Office of the Republic of Cuba (ONARC), the International Standards Organization (ISO), the International Electro technique Commission (IEC) and the International Atomic Energy Agency (IAEA). In this work it is presented in a summarized way the operation of this Program of Quality Assurance which includes the administration and conservation of the results and the documentation of the service, the controls that are carried out to the equipment, the acceptance tests that are applied to the equipment and new dosemeters, the shipment and prosecution of the dosemeters, the evaluation, storage and conservation of the doses, the report of the results, the traceability and reproducibility of the measurements, the attention to the reclamations and the clients complaints and the internal and external audits to those that it undergoes periodically the laboratory. (Author)

Partners Plus: Families and Caregivers in Partnerships. A Family-Centered Guide to Respite Care. Trainer's Workshop Manual [and] Community Planning Manual [and] A Family Manual [and] Caregiver Manual.

Science.gov (United States)

Ownby, Lisa L.; Hooke, Amanda C.; Moore, Dee Wylie; Garland, Corinne W.; Frank, Adrienne

Four manuals on implementing the Partners Respite Model, which provides respite care for children with disabilities or chronic illnesses, comprise this document. The Community Planning Manual offers a step-by-step guide to replication of the Partners Respite Model and is divided into sections on developing the Partners program, implementing the…

ETAP user's manual

International Nuclear Information System (INIS)

Watanabe, Norio; Higuchi, Suminori.

1990-11-01

The event tree analysis technique has been used in Probabilistic Safety Assessment for LWRs to delineate various accident scenarios leading to core melt or containment failure and to evaluate their frequencies. This technique often requires manual preparation of event trees with iterative process and time-consuming work in data handling. For the purpose of reducing manual efforts in event tree analysis, we developed a new software package named ETAP (Event Tree Analysis Supporting Program) for event tree analysis. ETAP is an interactive PC-based program which has the ability to construct, update, document, and quantify event trees. Because of its fast running capability to quantify event trees, use of the EATP program can make it easy to perform the sensitivity studies on a variety of system/containment performance issues. This report provides a user's manual for ETAP, which describes the structure, installation, and use of EATP. This software runs on NEC/PC-9800 or compatible PCs that have a 640 KB memory and MS-DOS 2.11 or higher. (author)

Skin dosimetry - radiological protection aspects of skin dosimetry

International Nuclear Information System (INIS)

Dennis, J.A.

1991-01-01

Following a Workshop in Skin Dosimetry, a summary of the radiological protection aspects is given. Aspects discussed include routine skin monitoring and dose limits, the need for careful skin dosimetry in high accidental exposures, techniques for assessing skin dose at all relevant depths and the specification of dose quantities to be measured by personal dosemeters and the appropriate methods to be used in their calibration. (UK)

Area monitoring dosimeter program for the Pacific Northwest National Laboratory: Results for CY 1997

International Nuclear Information System (INIS)

Bivins, S.R.; Stoetzel, G.A.

1998-07-01

In January 1993, Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the US Department of Energy (DOE) Radiological Control Manual (RCM). The purpose of the program was to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a) (1)--(3) and Article 511.1 of the RCM, personnel dosimetry shall be provided to (1) radiological workers who are likely to receive at least 100 mrem annually, and (2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years (CY) 1993--1996 confirmed that personnel dosimetry was not needed for individuals located in areas monitored by the program. A total of 93 area thermoluminescent dosimeters (TLDs) were placed in PNNL facilities during CY 1997. The TLDs were exchanged and analyzed quarterly. All routine area monitoring TLD results were less than 50 mrem annually after correcting for worker occupancy. The results support the conclusions that personnel dosimeters are not necessary for staff, declared pregnant workers, minors, or members of the public in these monitored areas

Area Monitoring Dosimeter Program for the Pacific Northwest National Laboratory: Results for CY 1998

International Nuclear Information System (INIS)

GA Stoetzel; SR Bivins

1999-01-01

In January 1993, Pacific Northwest National Laboratory (PNNL) established an area monitoring dosimeter program in accordance with Article 514 of the Department of Energy (DOE) Radiological Control Manual (RCM). The purpose of the program was to minimize the number of areas requiring issuance of personnel dosimeters and to demonstrate that doses outside Radiological Buffer Areas are negligible. In accordance with 10 CFR Part 835.402 (a)(1)-(4) and Article 511.1 of the RCM, personnel dosimetry shall be provided to (1) radiological workers who are likely to receive at least 100 mrem annually and (2) declared pregnant workers, minors, and members of the public who are likely to receive at least 50 mrem annually. Program results for calendar years 1993-1997 confirmed that personnel dosimetry was not needed for individuals located in areas monitored by the program. A total of 97 area thermoluminescent dosimeters (TLDs) were placed in PNNL facilities during calendar year 1998. The TLDs were exchanged and analyzed quarterly. All routine area monitoring TLD results were less than 50 mrem annually after correcting for worker occupancy. The results support the conclusion that personnel dosimeters are not necessary for staff, declared pregnant workers, minors, or members of the public in these monitored areas

Manual for a Volunteer Services System.

Science.gov (United States)

Helgerson, Linda; And Others

This manual presents guidelines for planning, monitoring, and controlling the development and operation of volunteer assistance programs. The materials included address questions related to both the process of establishing a volunteer program and the administration of a volunteer management system. The manual is not intended to provide a blueprint…

Personal radon daughter dosimetry

International Nuclear Information System (INIS)

Stocker, H.

1979-12-01

The conventional means of radon daughter exposure estimatikn for uranium miners in Canada is by grab sampling and time weighting. Personal dosimetry is a possible alternative method with its own advantages and limitations. The author poses basic questions with regard to two methods of radon daughter detection, thermoluminescent chips and track-etch film. An historical review of previous and current research and development programs in Canada and in other countries is presented, as are brief results and conclusions of each dosimeter evaluation

Examinations on Applications of Manual Calculation Programs on Lung Cancer Radiation Therapy Using Analytical Anisotropic Algorithm

Energy Technology Data Exchange (ETDEWEB)

Kim, Jung Min; Kim, Dae Sup; Hong, Dong Ki; Back, Geum Mun; Kwak, Jung Won [Dept. of Radiation Oncology, , Seoul (Korea, Republic of)

2012-03-15

There was a problem with using MU verification programs for the reasons that there were errors of MU when using MU verification programs based on Pencil Beam Convolution (PBC) Algorithm with radiation treatment plans around lung using Analytical Anisotropic Algorithm (AAA). On this study, we studied the methods that can verify the calculated treatment plans using AAA. Using Eclipse treatment planning system (Version 8.9, Varian, USA), for each 57 fields of 7 cases of Lung Stereotactic Body Radiation Therapy (SBRT), we have calculated using PBC and AAA with dose calculation algorithm. By developing MU of established plans, we compared and analyzed with MU of manual calculation programs. We have analyzed relationship between errors and 4 variables such as field size, lung path distance of radiation, Tumor path distance of radiation, effective depth that can affect on errors created from PBC algorithm and AAA using commonly used programs. Errors of PBC algorithm have showned 0.2{+-}1.0% and errors of AAA have showned 3.5{+-}2.8%. Moreover, as a result of analyzing 4 variables that can affect on errors, relationship in errors between lung path distance and MU, connection coefficient 0.648 (P=0.000) has been increased and we could calculate MU correction factor that is A.E=L.P 0.00903+0.02048 and as a result of replying for manual calculation program, errors of 3.5{+-}2.8% before the application has been decreased within 0.4{+-}2.0%. On this study, we have learned that errors from manual calculation program have been increased as lung path distance of radiation increases and we could verified MU of AAA with a simple method that is called MU correction factor.

Examinations on Applications of Manual Calculation Programs on Lung Cancer Radiation Therapy Using Analytical Anisotropic Algorithm

International Nuclear Information System (INIS)

Kim, Jung Min; Kim, Dae Sup; Hong, Dong Ki; Back, Geum Mun; Kwak, Jung Won

2012-01-01

There was a problem with using MU verification programs for the reasons that there were errors of MU when using MU verification programs based on Pencil Beam Convolution (PBC) Algorithm with radiation treatment plans around lung using Analytical Anisotropic Algorithm (AAA). On this study, we studied the methods that can verify the calculated treatment plans using AAA. Using Eclipse treatment planning system (Version 8.9, Varian, USA), for each 57 fields of 7 cases of Lung Stereotactic Body Radiation Therapy (SBRT), we have calculated using PBC and AAA with dose calculation algorithm. By developing MU of established plans, we compared and analyzed with MU of manual calculation programs. We have analyzed relationship between errors and 4 variables such as field size, lung path distance of radiation, Tumor path distance of radiation, effective depth that can affect on errors created from PBC algorithm and AAA using commonly used programs. Errors of PBC algorithm have showned 0.2±1.0% and errors of AAA have showned 3.5±2.8%. Moreover, as a result of analyzing 4 variables that can affect on errors, relationship in errors between lung path distance and MU, connection coefficient 0.648 (P=0.000) has been increased and we could calculate MU correction factor that is A.E=L.P 0.00903+0.02048 and as a result of replying for manual calculation program, errors of 3.5±2.8% before the application has been decreased within 0.4±2.0%. On this study, we have learned that errors from manual calculation program have been increased as lung path distance of radiation increases and we could verified MU of AAA with a simple method that is called MU correction factor.

FDA (Food and Drug Administration) compliance program guidance manual and updates (FY 86). Section 4. Medical and radiological devices. Irregular report

International Nuclear Information System (INIS)

1986-01-01

The FDA Compliance Program Guidance Manual provides a system for issuing and filing program plans and instructions directed to Food and Drug Administration Field operations for project implementation. Section IV provides those chapters of the Compliance Program Guidance Manual which pertain to the areas of medical and radiological devices. Some of the areas of coverage include laser and sunlamp standards inspections, compliance testing of various radiation-emitting products such as television receivers and microwave ovens, emergency response planning and policy, premarket approval and device manufacturers inspections, device problem reporting, sterilization of devices, and consumer education programs on medical and radiological devices

ESR Dosimetry

International Nuclear Information System (INIS)

Baffa, Oswaldo; Rossi, Bruno; Graeff, Carlos; Kinoshita, Angela; Chen Abrego, Felipe; Santos, Adevailton Bernardo dos

2004-01-01

ESR dosimetry is widely used for several applications such as dose assessment in accidents, medical applications and sterilization of food and other materials. In this work the dosimetric properties of natural and synthetic Hydroxyapatite, Alanine, and 2-Methylalanine are presented. Recent results on the use of a K-Band (24 GHz) ESR spectrometer in dosimetry are also presented

Finding Federal Money for Children's Services: Financing Services for Children through Title XX and Other Programs. Manual 1.

Science.gov (United States)

Copeland, William C.

This is the first manual of a 4-part series on how to find, obtain, contract for and manage Federal money for children's services. The first manual concentrates on ways to locate funds for new and existing programs. Emphasis is on Title XX of the Social Security Act, but attention is given also to alternative sources where Title XX funds are not…

Implementation of a post graduated course in radiation protection and dosimetry

International Nuclear Information System (INIS)

Papa, A.R.R.; Rodrigues, L.N.; Godoy, J.M.O.; Fonseca, E.S. da; Pereira, W.W.; Dantas, B.M.; Goncalves, M. G.

2001-01-01

The main motivations and followed lines in the implementation of a postgraduate course in Radiation Protection and Dosimetry are exposed. The principal research areas as well as the academic program are described. A prevision on the future and perspectives of the program is done. (author)

Historical review of personnel dosimetry development and its use in radiation protection programs at Hanford 1944 to the 1980s

Energy Technology Data Exchange (ETDEWEB)

Wilson, R.H.

1987-02-01

This document is an account of the personnel dosimetry programs as they were developed and practiced at Hanford from their inception in 1943 to 1944 to the 1980s. This history is divided into sections covering the general categories of external and internal measurement methods, in vivo counting, radiation exposure recordkeeping, and calibration of personnel dosimeters. The reasons and circumstances surrounding the inception of these programs at Hanford are discussed. Information about these programs was obtained from documents, letters, and memos that are available in our historical records; the personnel files of many people who participated in these programs; and from the recollections of many long-time, current, and past Hanford employees. For the most part, the history of these programs is presented chronologically to relate their development and use in routine Hanford operations. 131 refs., 38 figs., 23 tabs.

Dosimetry of ionizing radiation

International Nuclear Information System (INIS)

Musilek, L.; Seda, J.; Trousil, J.

1992-01-01

The publication deals with a major field of ionizing radiation dosimetry, viz., integrating dosimetric methods, which are the basic means of operative dose determination. It is divided into the following sections: physical and chemical effects of ionizing radiation; integrating dosimetric methods for low radiation doses (film dosimetry, nuclear emulsions, thermoluminescence, radiophotoluminescence, solid-state track detectors, integrating ionization dosemeters); dosimetry of high ionizing radiation doses (chemical dosimetric methods, dosemeters based on the coloring effect, activation detectors); additional methods applicable to integrating dosimetry (exoelectron emission, electron spin resonance, lyoluminescence, etc.); and calibration techniques for dosimetric instrumentation. (Z.S.). 422 refs

Dosimetry for audit and clinical trials: challenges and requirements

International Nuclear Information System (INIS)

Kron, T; Haworth, A; Williams, I

2013-01-01

Many important dosimetry audit networks for radiotherapy have their roots in clinical trial quality assurance (QA). In both scenarios it is essential to test two issues: does the treatment plan conform with the clinical requirements and is the plan a reasonable representation of what is actually delivered to a patient throughout their course of treatment. Part of a sound quality program would be an external audit of these issues with verification of the equivalence of plan and treatment typically referred to as a dosimetry audit. The increasing complexity of radiotherapy planning and delivery makes audits challenging. While verification of absolute dose delivered at a reference point was the standard of external dosimetry audits two decades ago this is often deemed inadequate for verification of treatment approaches such as Intensity Modulated Radiation Therapy (IMRT) and Volumetric Modulated Arc Therapy (VMAT). As such, most dosimetry audit networks have successfully introduced more complex tests of dose delivery using anthropomorphic phantoms that can be imaged, planned and treated as a patient would. The new challenge is to adapt this approach to ever more diversified radiotherapy procedures with image guided/adaptive radiotherapy, motion management and brachytherapy being the focus of current research.

LWR pressure vessel irradiation surveillance dosimetry. Quarterly progress report, July--September 1978

Energy Technology Data Exchange (ETDEWEB)

Guthrie, G L; McElroy, W N; Lippincott, E P; Gold, R

1978-12-01

Program objectives and progress to date by the national laboratories in LWR pressure vessel irradiation surveillance dosimetry are summarized. Participants in the program include: Rockwell International, Hanford Engineering Development Laboratory, National Bureau of Standards, and Oak Ridge National Laboratory.

History of personal dosimetry performance testing in the United States

International Nuclear Information System (INIS)

Soares, C. G.

2007-01-01

The basis for personal dosimetry performance testing in the United States is ANSI/HPS N13.11 (2001). Now in its third edition, this standard has been in place since 1983. Testing under this standard is administered by the National Voluntary Accreditation Program (NVLAP), and accreditation of dosimetry processors under this program is required by US Nuclear Regulatory Commission (NRC) regulations. The US Dept. of Energy (DOE) also maintains a testing program for its laboratories and contractors, administered by the Dept. of Energy Laboratory Accreditation Program (DOELAP). A focus in recent years has been the modification of ANSI/HPS N13.11 to allow acceptance by both testing programs in order to bring harmonisation to US personal dosemeter processing testing. Since there is no type testing program in the US for personal dosemeters, the testing philosophy of ANSI N13.11 has always combined elements of type testing and routine performance testing. This philosophy is explored in detail in this presentation, along with trends in the development of the document to its present state. In addition, a look will be taken at what the future holds for the next revision of the document, scheduled to begin in 2005. (authors)

Programmers' manual for the SYVAC geosphere program GEO3

International Nuclear Information System (INIS)

Oldfield, S.G.; Broyd, T.W.

1983-11-01

A Programmers' Manual for the computer model GEO3, of radionuclide migration through a saturated or unsaturated, multi-layered rock strata. GEO3 uses either a numerical (unsaturated) or an analytical (saturated) solution to equations of the one dimensional flow and three dimensional transport of radionuclides in the groundwater, including the effects of linear equilibrium sorption (for porous or fractured media), longitudinal and transverse dispersion, and chain decay for arbitrary chain lengths. The model is designed to be incorporated into the SYVAC (SYstems Variability Analysis Code) computer program, the function of which is to perform generic uncertainty assessments on hypothetical vault-geosphere-biosphere combinations, taking into account parameter variability and uncertainty. (author)

Clinical dosimetry

International Nuclear Information System (INIS)

Rassow, J.

1973-01-01

The main point of this paper on clinical dosimetry which is to be understood here as application of physical dosimetry on accelerators in medical practice, is based on dosimetric methodics. Following an explanation of the dose parameters and description of the dose distribution important for clinical practice as well as geometric irradiation parameters, the significance of a series of physical parameters such as accelerator energy, surface energy of average stopping power etc. is dealt with in detail. Following a section on field homogenization with bremsstrahlung and electron radiation, details on dosimetry in clinical practice are given. Finally, a few problems of dosemeter or monitor calibration on accelerators are described. The explanations are supplemented by a series of diagrams and tables. (ORU/LH) [de

Fast neutron spectrometry and dosimetry; Spectrometrie et dosimetrie des neutrons rapides

Energy Technology Data Exchange (ETDEWEB)

Blaize, S; Ailloud, J; Mariani, J; Millot, J P [Commissariat a l' Energie Atomique, Saclay (France). Centre d' Etudes Nucleaires

1958-07-01

We have studied fast neutron spectrometry and dosimetry through the recoil protons they produce in hydrogenated samples. In spectrometric, we used nuclear emulsions, in dosimetric, we used polyethylene coated with zinc sulphide and placed before a photomultiplier. (author)Fren. [French] Nous avons etudie la spectrometrie et la dosimetrie des neutrons rapides en utilisant les protons de recul qu'ils produisent dans une matiere hydrogenee. En spectrometrie, nous avons employe des emulsions nucleaires, en dosimetrie, du polyethylene recouvert de sulfure de zinc place devant un photomultiplicateur. (auteur)

Sandia National Laboratories, California Environmental Management System Program Manual.

Energy Technology Data Exchange (ETDEWEB)

2009-04-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004 and Department of Energy (DOE) Order 450.1. Sandia National Laboratories, California (SNL/CA) has maintained functional environmental programs to assist with regulatory compliance for more than 30 years. During 2005, these existing programs were rolled into a formal environmental management system (EMS) that expands beyond the traditional compliance focus to managing and improving environmental performance and stewardship practices for all site activities. An EMS is a set of inter-related elements that represent a continuing cycle of planning, implementing, evaluating, and improving processes and actions undertaken to achieve environmental policy and goals. The SNL/CA EMS Program conforms to the International Standard for Environmental Management Systems, ISO 14001:2004 (ISO 2004). The site received ISO 14001 certification in September 2006. SNL/CA's EMS Program is applicable to the Sandia, Livermore site only. Although SNL/CA operates as one organizational division of the overall Sandia National Laboratories, the EMS Program is site-specific, with site-specific objectives and targets. SNL/CA (Division 8000) benefits from the organizational structure as it provides corporate level policies, procedures, and standards, and established processes that connect to and support elements of the SNL/CA EMS Program. Additionally, SNL/CA's EMS Program benefits from two corporate functional programs (Facilities Energy Management and Fleet Services Environmental programs) that maintain responsibility for energy management and fleet services for all Sandia locations. Each EMS element is further enhanced with site-specific processes and standards. Division 8000 has several groups operating at Sandia

Sandia National Laboratories, California Environmental Management System program manual.

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2012-03-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004and Department of Energy (DOE) Order 436.1. Sandia National Laboratories, California (SNL/CA) has maintained functional environmental programs to assist with regulatory compliance for more than 30 years. During 2005, these existing programs were rolled into a formal environmental management system (EMS) that expands beyond the traditional compliance focus to managing and improving environmental performance and stewardship practices for all site activities. An EMS is a set of inter-related elements that represent a continuing cycle of planning, implementing, evaluating, and improving processes and actions undertaken to achieve environmental policy and goals. The SNL/CA EMS Program conforms to the International Standard for Environmental Management Systems, ISO 14001:2004 (ISO 2004). The site first received ISO 14001 certification in September 2006 and recertification in 2009. SNL/CA's EMS Program is applicable to the Sandia, Livermore site only. Although SNL/CA operates as one organizational division of the overall Sandia National Laboratories, the EMS Program is site-specific, with site-specific objectives and targets. SNL/CA (Division 8000) benefits from the organizational structure as it provides corporate level policies, procedures, and standards, and established processes that connect to and support elements of the SNL/CA EMS Program. Additionally, SNL/CA's EMS Program benefits from two corporate functional programs (Facilities Energy and Water Resource Management and Fleet Services programs) that maintain responsibility for energy management and fleet services for all Sandia locations. Each EMS element is further enhanced with site-specific processes and standards. Division 8000 has

Sandia National Laboratories, California Environmental Management System Program Manual.

Energy Technology Data Exchange (ETDEWEB)

Larsen, Barbara L.

2011-04-01

The Sandia National Laboratories, California (SNL/CA) Environmental Management System (EMS) Program Manual documents the elements of the site EMS Program. The SNL/CA EMS Program conforms to the International Standard on Environmental Management Systems, ISO 14001:2004and Department of Energy (DOE) Order 450.1. Sandia National Laboratories, California (SNL/CA) has maintained functional environmental programs to assist with regulatory compliance for more than 30 years. During 2005, these existing programs were rolled into a formal environmental management system (EMS) that expands beyond the traditional compliance focus to managing and improving environmental performance and stewardship practices for all site activities. An EMS is a set of inter-related elements that represent a continuing cycle of planning, implementing, evaluating, and improving processes and actions undertaken to achieve environmental policy and goals. The SNL/CA EMS Program conforms to the International Standard for Environmental Management Systems, ISO 14001:2004 (ISO 2004). The site received ISO 14001 certification in September 2006. SNL/CA's EMS Program is applicable to the Sandia, Livermore site only. Although SNL/CA operates as one organizational division of the overall Sandia National Laboratories, the EMS Program is site-specific, with site-specific objectives and targets. SNL/CA (Division 8000) benefits from the organizational structure as it provides corporate level policies, procedures, and standards, and established processes that connect to and support elements of the SNL/CA EMS Program. Additionally, SNL/CA's EMS Program benefits from two corporate functional programs (Facilities Energy Management and Fleet Services programs) that maintain responsibility for energy management and fleet services for all Sandia locations. Each EMS element is further enhanced with site-specific processes and standards. Division 8000 has several groups operating at Sandia National Laboratories

Dosimetry Control: Technic and methods. Proceedings of the international workshop 'Actual problems of dosimetry'

International Nuclear Information System (INIS)

Lyutsko, A.M.; Nesterenko, V.B.; Chudakov, V.A.; Konoplya, E.F.; Milyutin, A.A.

1997-10-01

There is a number of unsolved problems of both dosimetric and radiometric control, questions of the biological dosimetry, reconstruction of dozes of irradiation of the population at radiation incidents, which require coordination of efforts of scientists in various areas of a science. The submitted materials are grouped on five units: dosimetry engineering, biological dosimetry and markers of radiation impact, dosimetry of a medical irradiation, normative and measurement assurance of the dosimetric control, monitoring and reconstruction of dozes at radiation incidents

FURNACE; a toroidal geometry neutronic program system method description and users manual

International Nuclear Information System (INIS)

Verschuur, K.A.

1984-12-01

The FURNACE program system performs neutronic and photonic calculations in 3D toroidal geometry for application to fusion reactors. The geometry description is quite general, allowing any torus cross section and any neutron source density distribution for the plasma, as well as simple parametric representations of circular, elliptic and D-shaped tori and plasmas. The numerical method is based on an approximate transport model that produces results with sufficient accuracy for reactor-design purposes, at acceptable calculational costs. A short description is given of the numerical method, and a user manual for the programs of the system: FURNACE, ANISN-PT, LIBRA, TAPEMA and DRAWER is presented

Montana Rivers Information System : Edit/Entry Program User's Manual.

Energy Technology Data Exchange (ETDEWEB)

United States. Bonneville Power Administration; Montana Department of Fish, Wildlife and Parks

1992-07-01

The Montana Rivers Information System (MRIS) was initiated to assess the state`s fish, wildlife, and recreation value; and natural cultural, and geologic features. The MRIS is now a set of data bases containing part of the information in the Natural Heritage Program natural features and threatened and endangered species data bases and comprises of the Montana Interagency Stream Fisheries Database; the MDFWP Recreation Database; and the MDFWP Wildlife Geographic Information System. The purpose of this User`s Manual is to describe to the user how to maintain the MRIS database of their choice by updating, changing, deleting, and adding records using the edit/entry programs; and to provide to the user all information and instructions necessary to complete data entry into the MRIS databases.

Non-conventional personal dosimetry techniques

International Nuclear Information System (INIS)

Regulla, D.F.

1984-01-01

Established dosimetry has achieved a high standard in personnel monitoring. This applies particularly to photon dosimetry. Nevertheless, even in photon dosimetry, improvements and changes are being made. The reason may be technological progress, or the introduction of new tasks on the basis of the recommendations of international bodies (e.g. the new ICRU measurement unit) of national legislation. Since we are restricting ourselves here to technical trends the author would like to draw attention to various activities of current interest, e.g. the computation of receptor-related conversion coefficients from personal dose to organ or body doses, taking into account the conditions of exposure with respect to differential energy and angular distribution of the radiation field. Realistic data on exposure geometry are taken from work place analyses. Furthermore, the data banks of central personal dosimetry services are subject to statistical evaluation and radiation protection trend analysis. Technological progress and developments are considered from the point of view of personal dosimetry, partial body or extremity dosimetry and accidental dosimetry

Dosimetry for radiation processing

International Nuclear Information System (INIS)

McLaughlin, W.L.; Boyd, A.W.; Chadwick, K.H.; McDonald, J.C.; Miller, A.

1989-01-01

Radiation processing is a relatively young industry with broad applications and considerable commercial success. Dosimetry provides an independent and effective way of developing and controlling many industrial processes. In the sterilization of medical devices and in food irradiation, where the radiation treatment impacts directly on public health, the measurements of dose provide the official means of regulating and approving its use. In this respect, dosimetry provides the operator with a means of characterizing the facility, of proving that products are treated within acceptable dose limits and of controlling the routine operation. This book presents an up-to-date review of the theory, data and measurement techniques for radiation processing dosimetry in a practical and useful way. It is hoped that this book will lead to improved measurement procedures, more accurate and precise dosimetry and a greater appreciation of the necessity of dosimetry for radiation processing. (author)

High energy neutron dosimetry for the fusion program

International Nuclear Information System (INIS)

Barr, D.W.; Norris, A.E.

1977-01-01

Neutron dosimetry by the foil activation method offers a flexible technique for characterizing neutron spectra ranging from thermal energies to 30 MeV with the potential for extension to higher neutron energies as investigated by the Los Alamos Radiochemistry Group at the Los Alamos Meson Physics Facility and in the Apollo-Soyuz Test Project. The use of this method for the neutron flux description in thermal, resonance, and fission spectrum assemblies has been demonstrated. An extension of the method to environments involving thermonuclear processes was developed at Los Alamos in the early 1950's to characterize mixed fission-thermonuclear systems

An Administrator's Manual for Planning, Developing, and Implementing Mainstream, Self-Contained, or Co-op Programs for the Disadvantaged.

Science.gov (United States)

Pennsylvania State Univ., University Park. Div. of Occupational and Vocational Studies.

This administrator's manual contains guidelines for planning, developing, and implementing mainstream, self-contained, or cooperative work experience programs for the disadvantaged. Outlined in the introductory section are the philosophy underlying programs for the disadvantaged, procedures to determine student eligibility, signals indicating the…

Developing a Pupil Transportation Manual.

Science.gov (United States)

Douglas, Dave

1987-01-01

District-level pupil transportation manuals that contain clear, concise information about objectives, policies, and regulations are a must. These manuals should also specify procedures concerning evaluation processes, personnel recruitment and selection, and the driver training program. (MLH)

Operations manual for the plasma source ion implantation economics program

International Nuclear Information System (INIS)

Bibeault, M.L.; Thayer, G.R.

1995-10-01

Plasma Source Ion Implantation (PSII) is a surface modification technique for metal. PSIICOSTMODEL95 is an EXCEL-based program that estimates the cost for implementing a PSII system in a manufacturing setting where the number of parts to be processed is over 5,000 parts per day and the shape of each part does not change from day to day. Overall, the manufacturing process must be very well defined and should not change. This document is a self-contained manual for PSIICOSTMODEL95. It assumes the reader has some general knowledge of the technical requirements for PSII. Configuration of the PSII process versus design is used as the methodology in PSIICOSTMODEL95. The reason behind this is twofold. First, the design process cannot be programmed into a computer when the relationships between design variables are not understood. Second, the configuration methodology reduces the number of assumptions that must be programmed into our software. Misuse of results are less likely to occur if the user has fewer assumptions to understand

Thin film tritium dosimetry

Science.gov (United States)

Moran, Paul R.

1976-01-01

The present invention provides a method for tritium dosimetry. A dosimeter comprising a thin film of a material having relatively sensitive RITAC-RITAP dosimetry properties is exposed to radiation from tritium, and after the dosimeter has been removed from the source of the radiation, the low energy electron dose deposited in the thin film is determined by radiation-induced, thermally-activated polarization dosimetry techniques.

Proton-beam radiation therapy dosimetry standardization

International Nuclear Information System (INIS)

Gall, K.P.

1995-01-01

Beams of protons have been used for radiation therapy applications for over 40 years. In the last decade the number of facilities treating patients and the total number of patients being treated has begun go grow rapidly. Due to the limited and experimental nature of the early programs, dosimetry protocols tended to be locally defined. With the publication of the AAPM Task Group 20 report open-quotes Protocol for Dosimetry of Heavy Charged Particlesclose quotes and the open-quotes European Code of Practice for Proton-Beam Dosimetryclose quotes the practice of determining dose in proton-beam therapy was somewhat unified. The ICRU has also recently commissioned a report on recommendations for proton-beam dosimetry. There have been three main methods of determining proton dose; the Faraday cup technique, the ionization chamber technique, and the calorimeter technique. For practical reasons the ionization chamber technique has become the most widely used. However, due to large errors in basic parameters (e.g., W-value) is also has a large uncertainty for absolute dose. It has been proposed that the development of water calorimeter absorbed dose standards would reduce the uncertainty in absolute proton dose as well as the relative dose between megavoltage X-ray beams and proton beams. The advantages and disadvantages are discussed

The DOE Laboratory Accreditation Program 8 years later

International Nuclear Information System (INIS)

Cummings, R.; Kershisnik, R.; Taylor, T.; Grothaus, G.; Loesch, R.M.

1994-01-01

The DOE Laboratory Accreditation Program was implemented in 1986. Currently, the program is conducting its seventeenth performance testing session for whole body personnel dosimeters. All but two DOE laboratories have gained accreditation for their whole body personnel dosimetry systems. Several test situations which were anticipated in the early stages of DOELAP have not materialized. In addition, the testing standard for whole body personnel dosimetry systems is under review and revision. In the near future, the accreditation programs for extremity dosimetry and bioassay will be implemented. This presentation summarizes the status and anticipated direction of the DOE whole body and extremity dosimetry and bioassay laboratory accreditation program

Salinas : theory manual.

Energy Technology Data Exchange (ETDEWEB)

Walsh, Timothy Francis; Reese, Garth M.; Bhardwaj, Manoj Kumar

2004-08-01

This manual describes the theory behind many of the constructs in Salinas. For a more detailed description of how to use Salinas , we refer the reader to Salinas, User's Notes. Many of the constructs in Salinas are pulled directly from published material. Where possible, these materials are referenced herein. However, certain functions in Salinas are specific to our implementation. We try to be far more complete in those areas. The theory manual was developed from several sources including general notes, a programer-notes manual, the user's notes and of course the material in the open literature.

Chemical Dependency and Violence: Working with Dually Affected Families. A Cross-Training Program Manual for Counselors and Advocates.

Science.gov (United States)

Wright, Janet M.

This manual is designed as a cross-training program guide for counselors working in the fields of woman abuse and chemical dependency. (A cross-training program is a system for one (or more) agency personnel to train each other in their respective areas of expertise.) Chapter 1 discusses the rationale and goals of a cross-training program; issues…

Waste Management Technical Manual

Energy Technology Data Exchange (ETDEWEB)

Buckingham, J.S. [ed.

1967-08-31

This Manual has been prepared to provide a documented compendium of the technical bases and general physical features of Isochem Incorporated`s Waste Management Program. The manual is intended to be used as a means of training and as a reference handbook for use by personnel responsible for executing the Waste Management Program. The material in this manual was assembled by members of Isochem`s Chemical Processing Division, Battelle Northwest Laboratory, and Hanford Engineering Services between September 1965 and March 1967. The manual is divided into the following parts: Introduction, contains a summary of the overall Waste Management Program. It is written to provide the reader with a synoptic view and as an aid in understanding the subsequent parts; Feed Material, contains detailed discussion of the type and sources of feed material used in the Waste Management Program, including a chapter on nuclear reactions and the formation of fission products; Waste Fractionization Plant Processing, contains detailed discussions of the processes used in the Waste Fractionization Plant with supporting data and documentation of the technology employed; Waste Fractionization Plant Product and Waste Effluent Handling, contains detailed discussions of the methods of handling the product and waste material generated by the Waste Fractionization Plant; Plant and Equipment, describes the layout of the Waste Management facilities, arrangement of equipment, and individual equipment pieces; Process Control, describes the instruments and analytical methods used for process control; and Safety describes process hazards and the methods used to safeguard against them.

Technical Manual. The ACT®

Science.gov (United States)

ACT, Inc., 2014

2014-01-01

This manual contains technical information about the ACT® college readiness assessment. The principal purpose of this manual is to document the technical characteristics of the ACT in light of its intended purposes. ACT regularly conducts research as part of the ongoing formative evaluation of its programs. The research is intended to ensure that…

Fundamentals of x-ray dosimetry

International Nuclear Information System (INIS)

Roesch, W.C.

1976-01-01

Fundamental information about x-ray dosimetry is presented. Definitions are given and expanded on for dose, absorbed dose including microdosimetry, radiation physics (properties of the radiation that are important to dosimetry), and dosimetry (how the properties are dealt with in determining dose). 5 figs, 12 refs

Default Management Manual.

Science.gov (United States)

Dent, Richard A.

This manual is designed to instruct administrators of the Guaranteed Student Loan (GSL) Program in how to take every step possible to administer the program effectively and to minimize the program costs of serving the high risk student. It shows schools how to work with students throughout their time in school, create ownership of the loan(s) by…

MANUAL LOGIC CONTROLLER (MLC)

OpenAIRE

Claude Ziad Bayeh

2015-01-01

The “Manual Logic Controller” also called MLC, is an electronic circuit invented and designed by the author in 2008, in order to replace the well known PLC (Programmable Logic Controller) in many applications for its advantages and its low cost of fabrication. The function of the MLC is somewhat similar to the well known PLC, but instead of doing it by inserting a written program into the PLC using a computer or specific software inside the PLC, it will be manually programmed in a manner to h...

Thermoluminescent dosimetry in veterinary diagnostic radiology

International Nuclear Information System (INIS)

Hernández-Ruiz, L.; Jimenez-Flores, Y.; Rivera-Montalvo, T.; Arias-Cisneros, L.; Méndez-Aguilar, R.E.; Uribe-Izquierdo, P.

2012-01-01

This paper presents the results of Environmental and Personnel Dosimetry made in a radiology area of a veterinary hospital. Dosimetry was realized using thermoluminescent (TL) materials. Environmental Dosimetry results show that areas closer to the X-ray equipment are safe. Personnel Dosimetry shows important measurements of daily workday in some persons near to the limit established by ICRP. TL results of radiation measurement suggest TLDs are good candidates as a dosimeter to radiation dosimetry in veterinary radiology. - Highlights: ► Personnel dosimetry in laboratory veterinary diagnostic was determined. ► Student workplaces are safe against radiation. ► Efficiency value of apron lead was determined. ► X-ray beams distribution into veterinarian laboratory was measured.

Marketing Research. Instructor's Manual.

Science.gov (United States)

Small Business Administration, Washington, DC.

Prepared for the Administrative Management Course Program, this instructor's manual was developed to serve small-business management needs. The sections of the manual are as follows: (1) Lesson Plan--an outline of material covered, which may be used as a teaching guide, presented in two columns: the presentation, and a step-by-step indication of…

Sixth symposium on neutron dosimetry

International Nuclear Information System (INIS)

1987-01-01

This booklet contains all abstracts of papers presented in 13 sessions. Main topics: Cross sections and Kerma factors; analytical radiobiology; detectors for personnel monitoring; secondary charged particles and microdosimetric basis of q-value for neutrons; personnel dosimetry; concepts for radiation protection; ambient monitoring; TEPC and ion chambers in radiation protection; beam dosimetry; track detectors (CR-39); dosimetry at biomedical irradiation facilities; health physics at therapy facilities; calibration for radiation protection; devices for beam dosimetry (TLD and miscellaneous); therapy and biomedical irradiation facilities; treatment planning. (HP)

Environmental dosimetry

International Nuclear Information System (INIS)

Gold, R.

1977-01-01

For more than 60 years, natural radiation has offered broad opportunities for basic research as evidenced by many fundamental discoveries. Within the last decade, however, dramatic changes have occurred in the motivation and direction of this research. The urgent need for economical energy sources entailing acceptably low levels of environmental impact has compelled the applied aspects of our radiation environment to become overriding considerations. It is within this general framework that state-of-the-art environmental dosimetry techniques are reviewed. Although applied motivation and relevance underscores the current milieu for both reactor and environmental dosimetry, a perhaps even more unifying force is the broad similarity of reactor and environmental radiation fields. In this review, a comparison of these two mixed radiation fields is presented stressing the underlying similarities that exist. On this basis, the evolution of a strong inner bond between dosimetry methods for both reactor and environmental radiation fields is described. The existence of this bond will be illustrated using representative examples of observed spectra. Dosimetry methods of particularly high applicability for both of these fields are described. Special emphasis is placed on techniques of high sensitivity and absolute accuracy which are capable of resolving the components of these mixed radiation fields

Nuclear accident dosimetry

International Nuclear Information System (INIS)

1982-01-01

The film presents statistical data on criticality accidents. It outlines past IAEA activities on criticality accident dosimetry and the technical documents that resulted from this work. The film furthermore illustrates an international comparison study on nuclear accident dosimetry conducted at the Atomic Energy Research Establishment, Harwell, United Kingdom

Nuclear accident dosimetry

Energy Technology Data Exchange (ETDEWEB)

NONE

1983-12-31

The film presents statistical data on criticality accidents. It outlines past IAEA activities on criticality accident dosimetry and the technical documents that resulted from this work. The film furthermore illustrates an international comparison study on nuclear accident dosimetry conducted at the Atomic Energy Research Establishment, Harwell, United Kingdom

NV/YMP RADIOLOGICAL CONTROL MANUAL

Energy Technology Data Exchange (ETDEWEB)

U.S. DEPARTMENT OF ENERGY, NATIONAL NUCLEAR SECURITY ADMINISTRATION NEVADA SITE OFFICE; BECHTEL NEVADA

2004-11-01

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual.

NV/YMP RADIOLOGICAL CONTROL MANUAL

International Nuclear Information System (INIS)

2004-01-01

This manual contains the radiological control requirements to be used for all radiological activities conducted by programs under the purview of the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) and the Yucca Mountain Office of Repository Development (YMORD). Compliance with these requirements will ensure compliance with Title 10 Code of Federal Regulations Part 835 (10 CFR 835), Occupational Radiation Protection. Programs covered by this manual are located at the Nevada Test Site (NTS); Nellis Air Force Base and North Las Vegas, Nevada; Santa Barbara and Pleasanton, California; and at Andrews Air Force Base, Maryland. In addition, field work by NNSA/NSO at other locations is also covered by this manual

WE-H-207A-07: Image-Based Versus Atlas-Based Internal Dosimetry

Energy Technology Data Exchange (ETDEWEB)

Fallahpoor, M; Abbasi, M [Vali-Asr Hospital, School of Medicine, Tehran University of Medical Science, Tehran, Tehran (Iran, Islamic Republic of); Parach, A [Shahid Sadoughi University of Medical Sciences, Yazd, Yazd (Iran, Islamic Republic of); Kalantari, F [UT Southwestern Medical Center, Dallas, TX (United States)

2016-06-15

Purpose: Monte Carlo (MC) simulation is known as the gold standard method for internal dosimetry. It requires radionuclide distribution from PET or SPECT and body structure from CT for accurate dose calculation. The manual or semi-automatic segmentation of organs from CT images is a major obstacle. The aim of this study is to compare the dosimetry results based on patient’s own CT and a digital humanoid phantom as an atlas with pre-specified organs. Methods: SPECT-CT images of a 50 year old woman who underwent bone pain palliation with Samarium-153 EDTMP for osseous metastases from breast cancer were used. The anatomical date and attenuation map were extracted from SPECT/CT and three XCAT digital phantoms with different BMIs (i.e. matched (38.8) and unmatched (35.5 and 36.7) with patient’s BMI that was 38.3). Segmentation of patient’s organs in CT image was performed using itk-SNAP software. GATE MC Simulator was used for dose calculation. Specific absorbed fractions (SAFs) and S-values were calculated for the segmented organs. Results: The differences between SAFs and S-values are high using different anatomical data and range from −13% to 39% for SAF values and −109% to 79% for S-values in different organs. In the spine, the clinically important target organ for Samarium Therapy, the differences in the S-values and SAF values are higher between XCAT phantom and CT when the phantom with identical BMI is employed (53.8% relative difference in S-value and 26.8% difference in SAF). However, the whole body dose values were the same between the calculations based on the CT and XCAT with different BMIs. Conclusion: The results indicated that atlas-based dosimetry using XCAT phantom even with matched BMI for patient leads to considerable errors as compared to image-based dosimetry that uses the patient’s own CT Patient-specific dosimetry using CT image is essential for accurate results.

Effect of Adding Interferential Current in an Exercise and Manual Therapy Program for Patients With Unilateral Shoulder Impingement Syndrome: A Randomized Clinical Trial.

Science.gov (United States)

Gomes, Cid André Fidelis de Paula; Dibai-Filho, Almir Vieira; Moreira, William Arruda; Rivas, Shirley Quispe; Silva, Emanuela Dos Santos; Garrido, Ana Claudia Bogik

The purpose of this study was to measure the additional effect of adding interferential current (IFC) to an exercise and manual therapy program for patients with unilateral shoulder impingement syndrome. Forty-five participants were randomly assigned to group 1 (exercise and manual therapy), group 2 (exercise and manual therapy + IFC), or group 3 (exercise and manual therapy + placebo ultrasound). Individuals participated in 16 treatment sessions, twice a week for 8 weeks. The primary outcome of the study was total score of the Shoulder Pain and Disability Index (SPADI). The secondary outcomes were the pain and disability subscales of SPADI, Numeric Rating Scale, and Pain-Related Self-Statement Scale. Adjusted between-group mean differences (MDs) and 95% confidence intervals (CIs) were calculated using linear mixed models. After 16 treatment sessions, statistically significant but not clinically important differences were identified in favor of the exercise and manual therapy program alone in the SPADI-total (group 1 vs group 2, MD 11.12 points, 95% CI 5.90-16.35; group 1 vs group 3, MD 13.43 points, 95% CI 8.21-18.65). Similar results were identified for secondary outcomes. The addition of IFC does not generate greater clinical effects in an exercise and manual therapy program for individuals with unilateral shoulder impingement syndrome. Copyright © 2018. Published by Elsevier Inc.

Quantitative imaging for clinical dosimetry

Energy Technology Data Exchange (ETDEWEB)

Bardies, Manuel [INSERM U601, 9 Quai Moncousu, 44093 Nantes (France)]. E-mail: manu@nantes.inserm.fr; Flux, Glenn [Department of Physics, Royal Marsden NHS Trust, Sutton (United Kingdom); Lassmann, Michael [Department of Nuclear Medicine, Julis-Maximilians University, Wuerzburg (Germany); Monsieurs, Myriam [Department of Health Physics, University of Ghent, 9000 Ghent (Belgium); Savolainen, Sauli [Department of Physical Sciences, University of Helsinki and HUS, Helsinki Medical Imaging Center, Helsinki University Central Hospital (Finland); Strand, Sven-Erik [Medical Radiation Physics, Department of Clinical Sciences Lund, Lund University (Sweden)

2006-12-20

Patient-specific dosimetry in nuclear medicine is now a legal requirement in many countries throughout the EU for targeted radionuclide therapy (TRT) applications. In order to achieve that goal, an increased level of accuracy in dosimetry procedures is needed. Current research in nuclear medicine dosimetry should not only aim at developing new methods to assess the delivered radiation absorbed dose at the patient level, but also to ensure that the proposed methods can be put into practice in a sufficient number of institutions. A unified dosimetry methodology is required for making clinical outcome comparisons possible.

Revue of some dosimetry and dose assessment European projects

International Nuclear Information System (INIS)

Bolognese-Milsztajn, T.; Frank, D.; Lacoste, V.; Pihet, P.

2006-01-01

internal exposure monitoring programmes. Current monitoring programmes were critically reviewed, the major sources of uncertainty in assessed internal dose investigated, and guidance formulated on factors such as programme design, choice of method/techniques, monitoring intervals, and monitoring frequency. OMINEX promoted a common and harmonized approach to the design and implementation of internal dose monitoring programmes throughout the EU. The Coordination Action 'CONRAD' of the 6. Framework Programme will continue the work initiated within the 5. Framework Program in specific areas of dosimetry requiring coordination of research activities: computational dosimetry, internal dosimetry, complex mixed radiation fields at workplaces and radiation protection dosimetry of medical staff. (authors)

New FORTRAN computer programs to acquire and process isotopic mass spectrometric data: Operator's manual

International Nuclear Information System (INIS)

Smith, D.H.; McKown, H.S.

1993-09-01

This TM is one of a pair that describes ORNL-developed software for acquisition and processing of isotope ratio mass spectral data. This TM is directed at the laboratory analyst. No technical knowledge of the programs and programming is required. It describes how to create and edit files, how to acquire and process data, and how to set up files to obtain the desired results. The aim of this TM is to serve as a utilitarian instruction manual, a open-quotes how toclose quotes approach rather than a open-quotes why?close quotes

Biological and clinical dosimetry, July 1, 1964 to December 31, 1984. Final report

International Nuclear Information System (INIS)

Laughlin, J.S.; Zeitz, L.

1986-01-01

The goal was to develop systems for the determination of absorbed dose in biological research and clinical applications. The primary method under study is the local absorbed dose calorimeter. In addition, secondary dosimetric systems such as ionization chambers, chemical dosimeters and thermoluminescent dosimeters (TLD) are being developed and applied to provide an absolute basis for the evaluation and comparison of experiments, treatments and other procedures using radiation. In keeping with these objectives this project has accomplished significant advances in the following areas: (1) local absorbed dose calorimetry; (2) neutron dosimetry; (3) dosimetry of ultra-high intensity radiation sources; (4) solid state detector and germanium gamma camera program; (5) dosimetry for brachytherapy; and (6) ''non-isolated sensor'' calorimeters

Alanine EPR dosimetry of therapeutic irradiators

International Nuclear Information System (INIS)

Bugay, O.; Bartchuk, V.; Kolesnik, S.; Mazin, M.; Gaponenko, H.

1999-01-01

The high-dose alanine EPR dosimetry is a very precise method in the dose range 1-100 kGy. The system is used generally as the standard high-dose transfer dosimetry in many laboratories. This is comparatively expensive technique so it is important to use it as a more universal dosimetry system also in the middle and low dose ranges. The problems of the middle-dose alanine dosimetry are discussed and the solution of several problems is proposed. The alanine EPR dosimetry has been applied to the dose measurements of medical irradiators in the Kiev City Oncology Center. (author)

Radiological survey activities: uranium mill tailings remedial action project procedures manual

International Nuclear Information System (INIS)

Little, C.A.; Berven, B.A.; Carter, T.E.

1986-07-01

The US Department of Energy (DOE) was assigned the responsibility for conducting remedial action at 24 sites, which are located in one eastern and nine western states. The DOE's responsibilities are being met through its Uranium Mill Tailings Remedial Action Project Office (UMTRA-PO) in Albuquerque, New Mexico. The purpose of this Procedures Manual is to provide a standardized set of procedures that document in an auditable manner the activities performed by the Radiological Survey Activities (RASA) group in the Dosimetry and Biophysical Transport Section (DABTS) of the Health and Safety Research Division (HASRD) at the Oak Ridge National Laboratory (ORNL), in its role as the Inclusion Survey Contractor (ISC). Members of the RASA group assigned to the UMTRA Project are headquartered in the ORNL/RASA office in Grand Junction, Colorado, and report to the ORNL/RASA Project Manager. The Procedures Manual ensures that the organizational, administrative, and technical activities of the RASA/UMTRA group conform properly to those of the ISC as described in the Vicinity Properties Management and Implementation Manual and the Summary Protocol. This manual also ensures that the techniques and procedures used by the RASA/UMTRA group and contractor personnel meet the requirements of applicable governmental, scientific, and industrial standards

Assessment of national dosimetry quality audits results for teletherapy machines from 1989 to 2015.

Science.gov (United States)

Muhammad, Wazir; Ullah, Asad; Mahmood, Khalid; Matiullah

2016-01-01

The purpose of this study was to ensure accuracy in radiation dose delivery, external dosimetry quality audit has an equal importance with routine dosimetry performed at clinics. To do so, dosimetry quality audit was organized by the Secondary Standard Dosimetry Laboratory (SSDL) of Pakistan Institute of Nuclear Science and Technology (PINSTECH) at the national level to investigate and minimize uncertainties involved in the measurement of absorbed dose, and to improve the accuracy of dose measurement at different radiotherapy hospitals. A total of 181 dosimetry quality audits (i.e., 102 of Co-60 and 79 of linear accelerators) for teletherapy units installed at 22 different sites were performed from 1989 to 2015. The percent deviation between users’ calculated/stated dose and evaluated dose (in the result of on-site dosimetry visits) were calculated and the results were analyzed with respect to the limits of ± 2.5% (ICRU "optimal model") ± 3.0% (IAEA on-site dosimetry visits limit) and ± 5.0% (ICRU minimal or "lowest acceptable" model). The results showed that out of 181 total on-site dosimetry visits, 20.44%, 16.02%, and 4.42% were out of acceptable limits of ± 2.5% ± 3.0%, and ± 5.0%, respectively. The importance of a proper ongoing quality assurance program, recommendations of the followed protocols, and properly calibrated thermometers, pressure gauges, and humidity meters at radiotherapy hospitals are essential in maintaining consistency and uniformity of absorbed dose measurements for precision in dose delivery.

Quality Control in the Dosimetric System of the Personnel Dosimetry Service of the Spanish National Health Service

Energy Technology Data Exchange (ETDEWEB)

Casal, E.; Gil, J.A.; Roig, F.; Soriano, A. [Valencia (Spain)

1999-07-01

The main operating and quality control procedures implemented at the Centro Nacional de Dosimetria (CND) of the Spanish National Health Service to ensure the acceptance of the dosimetry service are described. The operating procedures are routinely performed at every step, since the dosemeters are received from the manufacturer until the doses are assigned to the dosimetric history and their main aim is to ensure the traceability of the doses. They make use of control and background dosemeters and frequent cross reference (automatic and manual) of different sources of data. The control procedures are performed at the end of each monthly process to detect possible errors or systematic bias in the dosimetry service and include analysis of the measurements of quality control dosemeters irradiated at the CND's laboratory and randomly read. The results of this analysis since 1996 are presented. (author)

Quality Control in the Dosimetric System of the Personnel Dosimetry Service of the Spanish National Health Service

International Nuclear Information System (INIS)

Casal, E.; Gil, J.A.; Roig, F.; Soriano, A.

1999-01-01

The main operating and quality control procedures implemented at the Centro Nacional de Dosimetria (CND) of the Spanish National Health Service to ensure the acceptance of the dosimetry service are described. The operating procedures are routinely performed at every step, since the dosemeters are received from the manufacturer until the doses are assigned to the dosimetric history and their main aim is to ensure the traceability of the doses. They make use of control and background dosemeters and frequent cross reference (automatic and manual) of different sources of data. The control procedures are performed at the end of each monthly process to detect possible errors or systematic bias in the dosimetry service and include analysis of the measurements of quality control dosemeters irradiated at the CND's laboratory and randomly read. The results of this analysis since 1996 are presented. (author)

Users Manual for the FEHMN application

International Nuclear Information System (INIS)

Zyvoloski, G.A.; Robinson, B.A.; Dash, Z.V.; Trease, L.L.

1996-01-01

The user's manual documents the use of the Yucca Mountain Site Characterization Projects Finite element heat and mass transfer code (FEHMN) application. The manual covers: Program considerations, data files, input data, output, system interface, and examples

Nevada test site neutron dosimetry-problems/solutions

International Nuclear Information System (INIS)

Sygitowicz, L.S.; Bastian, C.T.; Wells, I.J.; Koch, P.N.

1991-01-01

Historically, neutron dosimetry at the NTS was done using NTA film and albedo LiF TLD's. In 1987 the dosimeter type was changed from the albedo TLD based system to a CR-39 track etch based system modeled after the program developed by D. Hankins at LLNL. Routine issue and return is performed quarterly for selected personnel using bar-code readers at permanent locations. The capability exists for work site issue as-needed. Issue data are transmitted by telephone to a central computer where it is stored until the dosimeter is returned, processed and read, and the dose calculation is performed. Dose equivalent calculations are performed using LOTUS 123 and the results are printed as a hard copy record. The issue and dose information are hand-entered into the Dosimetry database. An application is currently being developed to automate this sequence

Comparison of Real-Time Intraoperative Ultrasound-Based Dosimetry With Postoperative Computed Tomography-Based Dosimetry for Prostate Brachytherapy

International Nuclear Information System (INIS)

Nag, Subir; Shi Peipei; Liu Bingren; Gupta, Nilendu; Bahnson, Robert R.; Wang, Jian Z.

2008-01-01

Purpose: To evaluate whether real-time intraoperative ultrasound (US)-based dosimetry can replace conventional postoperative computed tomography (CT)-based dosimetry in prostate brachytherapy. Methods and Materials: Between December 2001 and November 2002, 82 patients underwent 103 Pd prostate brachytherapy. An interplant treatment planning system was used for real-time intraoperative transrectal US-guided treatment planning. The dose distribution was updated according to the estimated seed position to obtain the dose-volume histograms. Postoperative CT-based dosimetry was performed a few hours later using the Theraplan-Plus treatment planning system. The dosimetric parameters obtained from the two imaging modalities were compared. Results: The results of this study revealed correlations between the US- and CT-based dosimetry. However, large variations were found in the implant-quality parameters of the two modalities, including the doses covering 100%, 90%, and 80% of the prostate volume and prostate volumes covered by 100%, 150%, and 200% of the prescription dose. The mean relative difference was 38% and 16% for doses covering 100% and 90% of the prostate volume and 10% and 21% for prostate volumes covered by 100% and 150% of the prescription dose, respectively. The CT-based volume covered by 200% of the prescription dose was about 30% greater than the US-based one. Compared with CT-based dosimetry, US-based dosimetry significantly underestimated the dose to normal organs, especially for the rectum. The average US-based maximal dose and volume covered by 100% of the prescription dose for the rectum was 72 Gy and 0.01 cm 3 , respectively, much lower than the 159 Gy and 0.65 cm 3 obtained using CT-based dosimetry. Conclusion: Although dosimetry using intraoperative US-based planning provides preliminary real-time information, it does not accurately reflect the postoperative CT-based dosimetry. Until studies have determined whether US-based dosimetry or

Dosimetry for radiation processing

International Nuclear Information System (INIS)

Miller, Arne

1986-01-01

During the past few years significant advances have taken place in the different areas of dosimetry for radiation processing, mainly stimulated by the increased interest in radiation for food preservation, plastic processing and sterilization of medical products. Reference services both by international organizations (IAEA) and national laboratories have helped to improve the reliability of dose measurements. In this paper the special features of radiation processing dosimetry are discussed, several commonly used dosimeters are reviewed, and factors leading to traceable and reliable dosimetry are discussed. (author)

Radiochromic film dosimetry

International Nuclear Information System (INIS)

Xu Zhiyong

2002-01-01

Radiochromic film dosimetry was developed to measure ionization irradiation dose for industry and medicine. At this time, there are no comprehensive guideline on the medical application, calibration method and densitometer system for medicine. The review gives update on Radiochromic film dosimetry used for medicine, including principles, film model and material, characteristics, calibration method, scanning densitometer system and medical application

BeOSL system for personal dosimetry : dosimetric characteristics and practical application

International Nuclear Information System (INIS)

Mende, E.

2015-10-01

Full text: BeOSL system of Dosimetric s is very easy to use, assimilate and maintain. Our dosimeter defines a milestone in the supervision of personal equivalent dose of Hp (10) and Hp (0.07) it covers the range of total energy of 16 KeV to 10 MeV. For this energy range is exceptional in its energy dependence for official personal dosimetry. The BeOSL system consists of two modules, one of them is the BeOSL reader that measures the radiation exposure using the latest technology, optically stimulated luminescence (OSL). The reading is extremely fast; it does not require consumables such as nitrogen or other. The detector material is beryllium oxide (Be O); this is an OSL material tissue equivalent and therefore is ideal for personal dosimetry. The BeOSL technology allows multiple readings of the dosimeter (re-read) to verify the dose or archive the dosimeter. One of the biggest advantages of BeOSL system is its modular concept allows the system to run as a manual solution or as a complete automated robotic system, which can be filled with up to 5,000 dosimeters as bulk cargo. (Author)

11. International conference on solid radiation dosimetry

International Nuclear Information System (INIS)

Krylova, I.V.

1996-01-01

The main problems discussed during the international conference on solid radiation dosimetry which took place in June 1995 in Budapest are briefly considered. These are the basic physical processes, materials applied for dosimetry, special techniques, personnel monitoring, monitoring of environmental effects, large-dose dosimetry, clinic dosimetry, track detector used for dosimetry, dosimetry in archaeology and geology, equipment and technique for dosimetric measurements. The special attention was paid to superlinearity in the TLD-100 (LiF, Mg, Ti) response function when determining doses of gamma radiation, heavy charged particles, low-energy particle fluxes in particular. New theoretical models were considered

Dental Chairside Technique. Student's Manual.

Science.gov (United States)

Apfel, Maura; Weaver, Trudy Karlene

This manual is part of a series dealing with skills and information needed by students in dental assisting. The individualized student materials are suitable for classroom, laboratory, or cooperative training programs. This student manual contains four units covering the following topics: local anesthesia; dental office emergencies; oral hygiene;…

A microcomputer controlled thermoluminescence dosimetry system

International Nuclear Information System (INIS)

Huyskens, C.J.; Kicken, P.J.H.

1980-01-01

Using a microcomputer, an automatic thermoluminescence dosimetry system for personal dosimetry and thermoluminescence detector (TLD) research was developed. Process automation, statistical computation and dose calculation are provided by this microcomputer. Recording of measurement data, as well as dose record keeping for radiological workers is carried out with floppy disk. The microcomputer also provides a human/system interface by means of a video display and a printer. The main features of this dosimetry system are its low cost, high degree of flexibility, high degree of automation and the feasibility for use in routine dosimetry as well as in TLD research. The system is in use for personal dosimetry, environmental dosimetry and for TL-research work. Because of its modular set-up several components of the system are in use for other applications, too. The system seems suited for medium sized health physics groups. (author)

Characterising an aluminium oxide dosimetry system.

Science.gov (United States)

Conheady, Clement F; Gagliardi, Frank M; Ackerly, Trevor

2015-09-01

In vivo dosimetry is recommended as a defence-in-depth strategy in radiotherapy treatments and is currently employed by clinics around the world. The characteristics of a new optically stimulated luminescence dosimetry system were investigated for the purpose of replacing an aging thermoluminescence dosimetry system for in vivo dosimetry. The stability of the system was not sufficient to satisfy commissioning requirements and therefore it has not been released into clinical service at this time.

Clinical implementation of a quality assurance program in HDR brachytherapy by in vivo dosimetry with diodes

International Nuclear Information System (INIS)

Alecu, R.; Feldmeier, J.J.; Court, W.S.; Alecu, M.; Orton, C.G.

1996-01-01

Despite the possibilities of in vivo dosimetry with diodes (e.g. control of dose to organs at risk, recorded confirmational measurements of the dose actually delivered, check of the whole treatment chain, avoidance of misadministrations, etc.) and the fact that it has proven to be very useful as part of a departmental QA program in external beam therapy, few attempts to implement it for HDR brachytherapy procedures have been reported. The reason for this is probably that there are significant technical challenges that must be met prior to its clinical use. The purpose of this study is to investigate the practicability and usefulness of dose measurements for brachytherapy patients in daily clinical practice. In our clinic a high precision patient dosimetry method has been developed, based on the use of silicon diodes. First, calibration factors have been determined under 'reference' irradiation conditions. Secondly, correction factors have been evaluated for situations deviating from the reference conditions, i.e. for different distances from the implanted sources, tissue heterogeneities, presence of different type of applicators, etc. For certain intracavitary, interstitial and surface mold applications this procedure has proven to be sufficiently accurate to allow dose determinations with diodes to be in good agreement with the expected values, i.e. calculated by the treatment planning system (VariSource unit) and checked by ion chamber measurements. The results of in vivo measurements are discussed along with the possibilities and limitations of the employed techniques

Dosimetry optimization at COGEMA-La Hague

International Nuclear Information System (INIS)

Kalimbadjian, J.

2000-01-01

At the present time, the la Hague site strives to apply international recommendations together with national regulations concerning radiation protection, and especially the respect of limitation and optimization principles. The application of these principles is based on the implementation of a passive dosimetry and an active dosimetry. The monthly passive dosimetry is monitored by means of a photographic dosimetry film, completed with lithium fluorine thermoluminescent film badges. This personal dosimetry common to X, β, γ and neutron radiations is carried out in close relationship between the Radiation Protection Department, the Occupational Medical Department and the staff running the Plant. The application or ALARA's principle as well as that of radiation protection optimization implies to implement a complementary active dosimetry enabling to gain in real time, the personal dosimetry of each intervening person, either they be COGEMA's workers or external companies'. This active dosimetry provides with following information: This preventive dosimetry is based on the knowledge of doses integration in real time and is fitted with alarm thresholds according to the total amount of doses and dose rates. Thresholds on the dose rate are also set relatively to the radiological environment. This knowledge of doses and dose rates allows a stricter management of the works, while analyzing them according to the nature of the work, to the location and to the skills of the intervening people. This dosimetry allows to analyze and optimize doses integration according to the works nature for the whole intervening staff. The la Hague Site has developed an active personal dosimetry system, common to every intervening person, COGEMA or external companies. The DOSICARD was thus elaborated, shaped as an electronic dosimeter fitted with an alarm and a smart card. The access to controlled areas is conditioned to information given by the DOSICARD concerning medical aptitudes and

FINAS. Example manual. 2

International Nuclear Information System (INIS)

Iwata, Koji; Tsukimori, Kazuyuki; Ueno, Mutsuo

2003-12-01

FINAS is a general purpose structural analysis computer program which was developed by Japan Nuclear Cycle Development Institute for the analysis of static, dynamic and thermal responses of elastic and inelastic structures by the finite element method. This manual contains typical analysis examples that illustrate applications of FINAS to a variety of structural engineering problems. The first part of this manual presents fundamental examples in which numerical solutions by FINAS are compared with some analytical reference solutions, and the second part of this manual presents more complex examples intended for practical application. All the input data images and principal results for each problem are included in this manual for beginners' convenience. All the analyses are performed by using the FINAS Version 13.0. (author)

The dosimetry of ionizing radiation

CERN Document Server

1990-01-01

A continuation of the treatise The Dosimetry of Ionizing Radiation, Volume III builds upon the foundations of Volumes I and II and the tradition of the preceeding treatise Radiation Dosimetry. Volume III contains three comprehensive chapters on the applications of radiation dosimetry in particular research and medical settings, a chapter on unique and useful detectors, and two chapters on Monte Carlo techniques and their applications.

Secondary standard dosimetry laboratory (SSDL)

International Nuclear Information System (INIS)

Md Saion bin Salikin.

1983-01-01

A secondary Standard Dosimetry Laboratory has been established in the Tun Ismail Research Centre, Malaysia as a national laboratory for reference and standardization purposes in the field of radiation dosimetry. This article gives brief accounts on the general information, development of the facility, programmes to be carried out as well as other information on the relevant aspects of the secondary standard dosimetry laboratory. (author)

Dosimetry in nuclear power plants

International Nuclear Information System (INIS)

Lastra B, J. A.

2008-12-01

To control the occupationally exposed personnel dose working at the Laguna Verde nuclear power plant, two types of dosemeters are used, the thermoluminescent (TLD) which is processed monthly, and the direct reading dosemeter that is electronic and works as daily control of personal dose. In the case of the electronic dosemeters of direct reading conventional, the readings and dose automatic registers and the user identity to which he was assigned to each dosemeter was to carry out the restricted area exit. In activities where the ionizing radiation sources are not fully characterized, it is necessary to relocate the personal dosemeter or assigned auxiliary dosemeters (TLDs and electronics) to determine the dose received by the user to both whole body and in any specific area of it. In jobs more complicated are used a tele dosimetry system where the radiation protection technician can be monitoring the user dose to remote control, the data transmission is by radio. The dosimetry activities are documented in procedures that include dosemeter inventories realization, the equipment and dosemeters calibration, the dosimetry quality control and the discrepancies investigation between the direct reading and TLD systems. TLD dosimetry to have technical expertise in direct and indirect dosimetry and two technicians in TLD dosimetry; electronic dosimetry to have 4 calibration technicians. For the electronic dosemeters are based on a calibrator source of Cesium-137. TLD dosemeters to have an automatic radiator, an automatic reader which can read up to 100 TLD dosemeters per hour and a semiautomatic reader. To keep the equipment under a quality process was development a process of initial entry into service and carried out a periodic verification of the heating cycles. It also has a maintenance contract for the equipment directly with the manufacturer to ensure their proper functioning. The vision in perspective of the dosimetry services of Laguna Verde nuclear power plant

User's manual of a supporting system for treatment planning in boron neutron capture therapy. JAERI computational dosimetry system

CERN Document Server

Kumada, H

2002-01-01

A boron neutron capture therapy (BNCT) with epithermal neutron beam is expected to treat effectively for malignant tumor that is located deeply in the brain. It is indispensable to estimate preliminarily the irradiation dose in the brain of a patient in order to perform the epithermal neutron beam BNCT. Thus, the JAERI Computational Dosimetry System (JCDS), which can calculate the dose distributions in the brain, has been developed. JCDS is a software that creates a 3-dimensional head model of a patient by using CT and MRI images and that generates a input data file automatically for calculation neutron flux and gamma-ray dose distribution in the brain by the Monte Carlo code: MCNP, and that displays the dose distribution on the head model for dosimetry by using the MCNP calculation results. JCDS has any advantages as follows; By treating CT data and MRI data which are medical images, a detail three-dimensional model of patient's head is able to be made easily. The three-dimensional head image is editable to ...

Modern methods of personnel dosimetry

International Nuclear Information System (INIS)

Kraus, W.; Herrmann, D.; Kiesewetter, W.

The physical properties of radiation detectors for personnel dosimetry are described and compared. The suitability of different types of dosimeters for operational and central monitoring of normal occupational exposure, for accident and catastrophe dosimetry and for background and space-flight dosimetry is discussed. The difficulties in interpreting the dosimeter reading with respect to the dose in individual body organs are discussed briefly. 430 literature citations (up to Spring 1966) are given

Use of metrics in an effective ALARA program

International Nuclear Information System (INIS)

Bates, B.B. Jr.

1996-01-01

ALARA radiological protection programs require metrics to meet their objectives. Sources of metrics include external dosimetry; internal dosimetry; radiological occurrences from the occurrence reporting an processing system (ORPS); and radiological incident reports (RIR). The sources themselves contain an abundance of specific open-quotes indicators.close quotes To choose the site-specific indicators that will be tracked and trended requires careful review. Justification is needed to defend the indicators selected and maybe even stronger justification is needed for those indicators that are available, but not chosen as a metric. Historically, the many different sources of information resided in a plethora of locations. Even the same type of metric had data located in different areas and could not be easily totaled for the entire Site. This required the end user to expend valuable time and effort to locate the data they needed. To address this problem, a central metrics database has been developed so that a customer can have all their questions addressed quickly and correctly. The database was developed in the beginning to answer some of the customer's most frequently asked questions. IL is now also a tool to communicate the status of the radiation protection program to facility managers. Finally, it also addresses requirements contained in the Rad Con manual and the 10CFR835 implementation guides. The database uses currently available, open-quotes user friendly,close quotes software and contains information from RIR's, ORPS, and external dosimetry records specific to ALARA performance indicators. The database is expandable to allow new metrics input. Specific reports have been developed to assist customers in their tracking and trending of ALARA metrics. These include quarterly performance indicator reports, monthly radiological incident reports, monthly external dose history and goals tracking reports, and the future use of performance indexing

Radiology Aide. Instructor Key [and] Student Manual.

Science.gov (United States)

Hartwein, Jon; Dunham, John

This manual can be used independently by students in secondary health occupations programs or by persons receiving on-the-job training in a radiology department. The manual includes an instructor's key that provides answers to the activity sheets and unit evaluations. The manual consists of the following five units: (1) orientation to radiology;…

Theoretical basis for dosimetry

International Nuclear Information System (INIS)

Carlsson, G.A.

1985-01-01

Radiation dosimetry is fundamental to all fields of science dealing with radiation effects and is concerned with problems which are often intricate as hinted above. A firm scientific basis is needed to face increasing demands on accurate dosimetry. This chapter is an attempt to review and to elucidate the elements for such a basis. Quantities suitable for radiation dosimetry have been defined in the unique work to coordinate radiation terminology and usage by the International Commission on Radiation Units and Measurements, ICRU. Basic definitions and terminology used in this chapter conform with the recent ''Radiation Quantities and Units, Report 33'' of the ICRU

The stability of liquid-filled matrix ionization chamber electronic portal imaging devices for dosimetry purposes

International Nuclear Information System (INIS)

Louwe, R.J.W.; Tielenburg, R.; Ingen, K.M. van; Mijnheer, B.J.; Herk, M.B. van

2004-01-01

This study was performed to determine the stability of liquid-filled matrix ionization chamber (LiFi-type) electronic portal imaging devices (EPID) for dosimetric purposes. The short- and long-term stability of the response was investigated, as well as the importance of factors influencing the response (e.g., temperature fluctuations, radiation damage, and the performance of the electronic hardware). It was shown that testing the performance of the electronic hardware as well as the short-term stability of the imagers may reveal the cause of a poor long-term stability of the imager response. In addition, the short-term stability was measured to verify the validity of the fitted dose-response curve immediately after beam startup. The long-term stability of these imagers could be considerably improved by correcting for room temperature fluctuations and gradual changes in response due to radiation damage. As a result, the reproducibility was better than 1% (1 SD) over a period of two years. The results of this study were used to formulate recommendations for a quality control program for portal dosimetry. The effect of such a program was assessed by comparing the results of portal dosimetry and in vivo dosimetry using diodes during the treatment of 31 prostate patients. The improvement of the results for portal dosimetry was consistent with the deviations observed with the reproducibility tests in that particular period. After a correction for the variation in response of the imager, the average difference between the measured and prescribed dose during the treatment of prostate patients was -0.7%±1.5% (1 SD), and -0.6%±1.1% (1 SD) for EPID and diode in vivo dosimetry, respectively. It can be concluded that a high stability of the response can be achieved for this type of EPID by applying a rigorous quality control program

STICAP: A linear circuit analysis program with stiff systems capability. Volume 1: Theory manual. [network analysis

Science.gov (United States)

Cooke, C. H.

1975-01-01

STICAP (Stiff Circuit Analysis Program) is a FORTRAN 4 computer program written for the CDC-6400-6600 computer series and SCOPE 3.0 operating system. It provides the circuit analyst a tool for automatically computing the transient responses and frequency responses of large linear time invariant networks, both stiff and nonstiff (algorithms and numerical integration techniques are described). The circuit description and user's program input language is engineer-oriented, making simple the task of using the program. Engineering theories underlying STICAP are examined. A user's manual is included which explains user interaction with the program and gives results of typical circuit design applications. Also, the program structure from a systems programmer's viewpoint is depicted and flow charts and other software documentation are given.

Managerial Accounting. Course Administrative Manual.

Science.gov (United States)

Central Michigan Univ., Mount Pleasant. Inst. for Personal and Career Development.

This manual is part of the materials for a college-level programmed course in managerial accounting and intended to aid instructors in helping students to work their way through the self-instructional study guide around which the course is organized. The manual describes the various materials and components used in the self-instructional sequence…

Dosimetry of 64Cu-DOTA-AE105, a PET tracer for uPAR imaging

International Nuclear Information System (INIS)

Persson, Morten; El Ali, Henrik H.; Binderup, Tina; Pfeifer, Andreas; Madsen, Jacob; Rasmussen, Palle; Kjaer, Andreas

2014-01-01

64 Cu-DOTA-AE105 is a novel positron emission tomography (PET) tracer specific to the human urokinase-type plasminogen activator receptor (uPAR). In preparation of using this tracer in humans, as a new promising method to distinguish between indolent and aggressive cancers, we have performed PET studies in mice to evaluate the in vivo biodistribution and estimate human dosimetry of 64 Cu-DOTA-AE105. Methods: Five mice received iv tail injection of 64 Cu-DOTA-AE105 and were PET/CT scanned 1, 4.5 and 22 h post injection. Volume-of-interest (VOI) were manually drawn on the following organs: heart, lung, liver, kidney, spleen, intestine, muscle, bone and bladder. The activity concentrations in the mentioned organs [%ID/g] were used for the dosimetry calculation. The %ID/g of each organ at 1, 4.5 and 22 h was scaled to human value based on a difference between organ and body weights. The scaled values were then exported to OLINDA software for computation of the human absorbed doses. The residence times as well as effective dose equivalent for male and female could be obtained for each organ. To validate this approach, of human projection using mouse data, five mice received iv tail injection of another 64 Cu-DOTA peptide-based tracer, 64 Cu-DOTA-TATE, and underwent same procedure as just described. The human dosimetry estimates were then compared with observed human dosimetry estimate recently found in a first-in-man study using 64 Cu-DOTA-TATE. Results: Human estimates of 64 Cu-DOTA-AE105 revealed the heart wall to receive the highest dose (0.0918 mSv/MBq) followed by the liver (0.0815 mSv/MBq), All other organs/tissue were estimated to receive doses in the range of 0.02–0.04 mSv/MBq. The mean effective whole-body dose of 64 Cu-DOTA-AE105 was estimated to be 0.0317 mSv/MBq. Relatively good correlation between human predicted and observed dosimetry estimates for 64 Cu-DOTA-TATE was found. Importantly, the effective whole body dose was predicted with very high

Dosimetry of 64Cu-DOTA-AE105, a PET tracer for uPAR imaging.

Science.gov (United States)

Persson, Morten; El Ali, Henrik H; Binderup, Tina; Pfeifer, Andreas; Madsen, Jacob; Rasmussen, Palle; Kjaer, Andreas

2014-03-01

(64)Cu-DOTA-AE105 is a novel positron emission tomography (PET) tracer specific to the human urokinase-type plasminogen activator receptor (uPAR). In preparation of using this tracer in humans, as a new promising method to distinguish between indolent and aggressive cancers, we have performed PET studies in mice to evaluate the in vivo biodistribution and estimate human dosimetry of (64)Cu-DOTA-AE105. Five mice received iv tail injection of (64)Cu-DOTA-AE105 and were PET/CT scanned 1, 4.5 and 22 h post injection. Volume-of-interest (VOI) were manually drawn on the following organs: heart, lung, liver, kidney, spleen, intestine, muscle, bone and bladder. The activity concentrations in the mentioned organs [%ID/g] were used for the dosimetry calculation. The %ID/g of each organ at 1, 4.5 and 22 h was scaled to human value based on a difference between organ and body weights. The scaled values were then exported to OLINDA software for computation of the human absorbed doses. The residence times as well as effective dose equivalent for male and female could be obtained for each organ. To validate this approach, of human projection using mouse data, five mice received iv tail injection of another (64)Cu-DOTA peptide-based tracer, (64)Cu-DOTA-TATE, and underwent same procedure as just described. The human dosimetry estimates were then compared with observed human dosimetry estimate recently found in a first-in-man study using (64)Cu-DOTA-TATE. Human estimates of (64)Cu-DOTA-AE105 revealed the heart wall to receive the highest dose (0.0918 mSv/MBq) followed by the liver (0.0815 mSv/MBq), All other organs/tissue were estimated to receive doses in the range of 0.02-0.04 mSv/MBq. The mean effective whole-body dose of (64)Cu-DOTA-AE105 was estimated to be 0.0317 mSv/MBq. Relatively good correlation between human predicted and observed dosimetry estimates for (64)Cu-DOTA-TATE was found. Importantly, the effective whole body dose was predicted with very high precision

The DS86 neutron dosimetry enigma: Some missing pieces to the puzzle

International Nuclear Information System (INIS)

Gold, R.

1994-01-01

International programs have been conducted over the last four decades to quantify the exposure of atom bomb survivors from Hiroshima and Nagasaki. Unfortunately, the quest for accurate gamma-ray and neutron exposure doses of atom bomb survivors has proven illusive. Efforts in the most recent of these programs, designated as Dosimetry System 1986 (DS86), have revealed a serious and persistent discrepancy between neutron transport calculations and thermal neutron activation measurements at the Hiroshima site, which will be called the DS86 neutron dosimetry enigma. It is established that this enigma is a complex puzzle that precludes simple solutions. This conclusion is deduced through the identification of a number of missing pieces to the puzzle. Implications and conclusions that can be inferred from these missing puzzle pieces are advanced

SU-E-T-497: Semi-Automated in Vivo Radiochromic Film Dosimetry Using a Novel Image Processing Algorithm

International Nuclear Information System (INIS)

Reyhan, M; Yue, N

2014-01-01

Purpose: To validate an automated image processing algorithm designed to detect the center of radiochromic film used for in vivo film dosimetry against the current gold standard of manual selection. Methods: An image processing algorithm was developed to automatically select the region of interest (ROI) in *.tiff images that contain multiple pieces of radiochromic film (0.5x1.3cm 2 ). After a user has linked a calibration file to the processing algorithm and selected a *.tiff file for processing, an ROI is automatically detected for all films by a combination of thresholding and erosion, which removes edges and any additional markings for orientation. Calibration is applied to the mean pixel values from the ROIs and a *.tiff image is output displaying the original image with an overlay of the ROIs and the measured doses. Validation of the algorithm was determined by comparing in vivo dose determined using the current gold standard (manually drawn ROIs) versus automated ROIs for n=420 scanned films. Bland-Altman analysis, paired t-test, and linear regression were performed to demonstrate agreement between the processes. Results: The measured doses ranged from 0.2-886.6cGy. Bland-Altman analysis of the two techniques (automatic minus manual) revealed a bias of -0.28cGy and a 95% confidence interval of (5.5cGy,-6.1cGy). These values demonstrate excellent agreement between the two techniques. Paired t-test results showed no statistical differences between the two techniques, p=0.98. Linear regression with a forced zero intercept demonstrated that Automatic=0.997*Manual, with a Pearson correlation coefficient of 0.999. The minimal differences between the two techniques may be explained by the fact that the hand drawn ROIs were not identical to the automatically selected ones. The average processing time was 6.7seconds in Matlab on an IntelCore2Duo processor. Conclusion: An automated image processing algorithm has been developed and validated, which will help minimize

Pilot program on patient dosimetry in pediatric interventional cardiology in Chile

International Nuclear Information System (INIS)

Ubeda, Carlos; Vano, Eliseo; Miranda, Patricia; Leyton, Fernando

2012-01-01

Purpose: The aim of this study was to present the results of a pilot program on patient dosimetry carried out in Chile during the last 5 yr, using a biplane x-ray angiography system settled for pediatrics. This research was conducted in Latin America under the auspices of the International Atomic Energy Agency (IAEA) supporting programs on radiological protection (RP) of patients. Methods: Patient age, gender, weight, height, number of cine series, total number of cine frames, fluoroscopy time, and two dosimetric quantities [air kerma-area product (P ka ) and cumulative dose (CD) at the patient entrance reference point] were recorded for each procedure. Results: The study includes 544 patients grouped into four age groups. The distributions by age group were 150 for ka and CD for the four age groups were 0.94, 1.46, 2.13, and 5.03 Gy cm 2 and 23.9, 26.8, 33.5, and 51.6 mGy, respectively. No significant statistical differences were found between diagnostic and therapeutic procedures. A moderate correlation (r = 0.64) was seen between P ka and patient weight. Conclusions: The dose values reported in this paper were lower than those published in the previous work for the same age groups as a result of the optimization actions carried out by cardiologists and medical physicists with the support of the IAEA. Methodology and results will be used as a starting point for a wider survey in Chile and Latin America with the goal to obtain regional diagnostic reference levels as recently recommended by the International Commission on Radiological Protection for interventional procedures.

The Bristol University neutron dosimetry system

International Nuclear Information System (INIS)

Worley, A.; Fews, A.P.; Henshaw, D.L.

1987-01-01

The neutron dosimetry system developed at Bristol is based on recording recoil proton tracks in conventionally etched PADC plastic using a fully automated image analysis system. Two features contribute to the achievement of a low dose threshold: high quality plastic is manufactured and undergoes extensive quality control tests prior to acceptance for use in dosimetry, and a readout system with high efficiency for rejecting background events is used. The principal dosemeter that has been developed consists of three orthogonal elements, each containing two 3 cm x 1 cm plastics on either side of a polyethylene radiator. On each plastic an area of 0.15 cm 2 is scanned giving a total active area of 0.90 cm 2 . Each plastic is coded for manual identification and for computer recognition. The track counts from the six plastics are added with different weightings to achieve a measure of dose which is independent of irradiation direction when worn on the body. The device has been calibrated using monoenergetic neutrons in the range 100 keV to 14.7 MeV at NPL, and using the recent CENDOS exposure. If the track counts are added without weighting, the device has a nominal response of 120 tracks cm -2 .mSv -1 and an energy threshold at 200 keV. Taken together with a background of 20 track cm -2 , a dose threshold of around 80μSv is implied. A simpler dosemeter, using a single plastic/radiator combination, may also be considered. If a 1 cm 2 device is used for normal incidence exposure, the dose threshold is calculated to be 25 μSv. (author)

MAP user's manual copyright

International Nuclear Information System (INIS)

Pillsbury, R.D. Jr.

1991-12-01

The program MITMAP represents a set of general purpose, two- dimensional, finite element programs for the calculation of magnetic fields. It consists of the program MAP and MAP2DJ. The two programs are used to solve different electromagnetic problems, but they have a common set of subrountines for pre- and postprocessing. Originally separate programs, they have been combined to make modification easier. The manuals, however, will remain separate. The program MAP is described in this manual. MAP is applicable to the class of problems with two-dimensional-planar or axisymmetric - geometries, in which the current density and the magnetic vector potential have only a single nonvanishing component. The single component is associated with the direction that is perpendicular to the plane of the problem and is invariant with respect to that direction. Maxwell's equations can be reduced to a solver diffusion equation in terms of the single, nonvanishing component of the magnetic vector potential for planar problems and to a single component of a vector potential for planar problems and to a single component of a vector diffusion equation for axisymmetric problems. The magnetic permeability appears in the governing equation. The permeability may be a function of the magnetic flux density. In addition, any electrically conducting material present will have eddy currents induced by a time varying magnetic field. These eddy currents must be included in the solution process. This manual provides a description of the structure of the input data and output for the program. There are several example problems presented that illustrate the major program features. Appendices are included that contain a derivation of the governing equations and the application of the finite element method to the solution of the equations

Latin-American Biological Dosimetry Network (LBDNET) Intercomparison Exercise. Evaluation through triage and conventional scoring criteria. Development of a new approach for statistical data analysis

International Nuclear Information System (INIS)

Di Giorgio, M.; Vallerga, M.B.; Radl, A.

2011-01-01

Biological Dosimetry is a necessary support for National Radiation Protection Programs and Emergency Response Schemes. A Latin-American Biological Dosimetry Network (LBDNET) has been constituted by the biological dosimetry laboratories from: Argentina, Brazil, Chile, Cuba, Mexico, Peru, and Uruguay (IAEA Regional Project RLA9/054, 2007). The biological dosimetry laboratory of Argentina organized an international biological dosimetry intercomparison for the analysis of some relevant parameters involved in dose assessment, to reinforce the response capability in accidental situations requiring the activation of mutual assistance mechanisms and thus, constituting the bases of the LBDNET organization. (authors)

Procedures manual for the ORNL Radiological Survey Activities (RASA) Program

International Nuclear Information System (INIS)

Myrick, T.E.; Berven, B.A.; Cottrell, W.D.; Goldsmith, W.A.; Haywood, F.F.

1987-04-01

The portion of the radiological survey program performed by ORNL is the subject of this Procedures Manual. The RASA group of the Health and Safety Research Division (HASRD) at ORNL is responsible for the planning, conducting, and reporting of the results of radiological surveys at specified sites and associated vicinity properties. The results of these surveys are used by DOE in determining the need for and extent of remedial actions. Upon completion of the necessary remedial actions, the ORNL-RASA group or other OOS contractor may be called upon to verify the effectiveness of the remedial action. Information from these postremedial action surveys is included as part of the data base used by DOE in certifying a site for unrestricted use

Procedures manual for the ORNL Radiological Survey Activities (RASA) Program

Energy Technology Data Exchange (ETDEWEB)

Myrick, T.E.; Berven, B.A.; Cottrell, W.D.; Goldsmith, W.A.; Haywood, F.F.

1987-04-01

The portion of the radiological survey program performed by ORNL is the subject of this Procedures Manual. The RASA group of the Health and Safety Research Division (HASRD) at ORNL is responsible for the planning, conducting, and reporting of the results of radiological surveys at specified sites and associated vicinity properties. The results of these surveys are used by DOE in determining the need for and extent of remedial actions. Upon completion of the necessary remedial actions, the ORNL-RASA group or other OOS contractor may be called upon to verify the effectiveness of the remedial action. Information from these postremedial action surveys is included as part of the data base used by DOE in certifying a site for unrestricted use.

25 CFR 900.5 - Effect of these regulations on Federal program guidelines, manual, or policy directives.

Science.gov (United States)

2010-04-01

... SELF-DETERMINATION AND EDUCATION ASSISTANCE ACT General Provisions § 900.5 Effect of these regulations... 25 Indians 2 2010-04-01 2010-04-01 false Effect of these regulations on Federal program guidelines, manual, or policy directives. 900.5 Section 900.5 Indians BUREAU OF INDIAN AFFAIRS, DEPARTMENT OF THE...

The Smartphone Peer Physical Activity Counseling (SPPAC) Program for Manual Wheelchair Users: Protocol of a Pilot Randomized Controlled Trial.

Science.gov (United States)

Best, Krista L; Routhier, François; Sweet, Shane N; Arbour-Nicitopoulos, Kelly P; Borisoff, Jaimie F; Noreau, Luc; Martin Ginis, Kathleen A

2017-04-26

Physical activity (PA) must be performed regularly to accrue health benefits. However, the majority of manual wheelchair users do not meet PA recommendations. Existing community-based PA programs for manual wheelchair users appear to work, but effect sizes are small and retention is low. Existing PA programs may not fully implement some psychosocial factors that are strongly linked with PA (eg, autonomy). The use of peers and mobile phone technology in the Smartphone Peer PA Counseling (SPPAC) program represents a novel approach to cultivating a PA-supportive environment for manual wheelchair users. The primary objective is to compare change in objective PA between the experimental (SPPAC) and control groups from baseline to postintervention (10 weeks) and follow-up (3 months). Changes in and relationships between subjective PA, wheelchair skills, motivation, self-efficacy (for overcoming barriers to PA for manual wheelchair use), satisfaction of psychological needs for PA, and satisfaction with PA participation will be explored (secondary outcome). Program implementation will be explored (tertiary objective). A total of 38 community-living manual wheelchair users (≥18 years) will be recruited in a randomized controlled trial (RCT). Participants in both the control and experimental groups will receive existing PA guidelines. Participants in the experimental group will also receive the SPPAC program: 14 sessions (~30 min) over a 10-week period delivered by a peer trainer using a mobile phone. PA activities will be based on individuals' preferences and goals. Implementation of important theoretical variables will be enforced through a peer-trainer checklist. Outcomes for objective PA (primary) and subjective PA, wheelchair skills, motivation, self-efficacy, satisfaction of psychological needs, and satisfaction with participation will be collected at three time points (baseline, postintervention, follow-up). Multiple imputations will be used to treat missing data. A

Personal dosimetry in Kazakhstan

International Nuclear Information System (INIS)

Khvoshnyanskaya, I.R.; Vdovichenko, V.G.; Lozbin, A.Yu.

2003-01-01

KATEP-AE Radiation Laboratory is the first organization in Kazakhstan officially licensed by the Kazakhstan Atomic Energy Committee to provide individual dosimetry services. The Laboratory was established according to the international standards. Nowadays it is the largest company providing personal dosimetry services in the Republic of Kazakhstan. (author)

Status of neutron dosimetry cross sections

International Nuclear Information System (INIS)

Griffin, P.J.; Kelly, J.G.

1992-01-01

Several new cross section libraries, such as ENDF/B-VI(release 2), IRDF-90,JEF-2.2, and JENDL-3 Dosimetry, have recently been made available to the dosimetry community. the Sandia National Laboratories (SNL) Radiation Metrology Laboratory (RML) has worked with these libraries since pre-release versions were available. this paper summarizes the results of the intercomparison and testing of dosimetry cross sections. As a result of this analysis, a compendium of the best dosimetry cross sections was assembled from the available libraries for use within the SNL RML. this library, referred to as the SNLRML Library, contains 66 general dosimetry sensors and 3 special dosimeters unique to the RML sensor inventory. The SNLRML cross sections have been put into a format compatible with commonly used spectrum determination codes

Handbook of laboratory techniques; Manual de tecnicas de laboratorio

Energy Technology Data Exchange (ETDEWEB)

NONE

2002-07-01

The Nuclear Regulatory Authority in Argentina have laboratories of support to regulations functions on radiological and nuclear safety, safeguards and physical protection, that have a surface of 2950 m{sup 2} in the Ezeiza Atomic Center. The manual describes in seven chapters the different techniques developed and applied in the laboratories along four decades of existence. The chapter 1: Dedicated to the treatment of environmental samples, described the procedures associated with the different types of samples: deposits, waters, sediments, vegetables, milk, fish and diet. The chapter 2: Details 48 radiochemical techniques associated to the measurements of americium 241, carbon 16, strontium 90, iodine 129, plutonium, radium 226, radon, uranium, nickel and actinides. The chapter 3: Describes the measurements techniques of alpha and gamma spectrometry. The different techniques of biological and physical dosimetry are described in the chapters 5 and 6 respectively. The final chapter is dedicated the techniques of external and internal contamination. It s important to emphasize that this manual contains the standardized technologies that the Nuclear Regulatory Authority of Argentina submits regularly to international comparisons.

MO-B-BRB-00: Three Dimensional Dosimetry

Energy Technology Data Exchange (ETDEWEB)

NONE

2016-06-15

Full three-dimensional (3D) dosimetry using volumetric chemical dosimeters probed by 3D imaging systems has long been a promising technique for the radiation therapy clinic, since it provides a unique methodology for dose measurements in the volume irradiated using complex conformal delivery techniques such as IMRT and VMAT. To date true 3D dosimetry is still not widely practiced in the community; it has been confined to centres of specialized expertise especially for quality assurance or commissioning roles where other dosimetry techniques are difficult to implement. The potential for improved clinical applicability has been advanced considerably in the last decade by the development of improved 3D dosimeters (e.g., radiochromic plastics, radiochromic gel dosimeters and normoxic polymer gel systems) and by improved readout protocols using optical computed tomography or magnetic resonance imaging. In this session, established users of some current 3D chemical dosimeters will briefly review the current status of 3D dosimetry, describe several dosimeters and their appropriate imaging for dose readout, present workflow procedures required for good dosimetry, and analyze some limitations for applications in select settings. We will review the application of 3D dosimetry to various clinical situations describing how 3D approaches can complement other dose delivery validation approaches already available in the clinic. The applications presented will be selected to inform attendees of the unique features provided by full 3D techniques. Learning Objectives: L. John Schreiner: Background and Motivation Understand recent developments enabling clinically practical 3D dosimetry, Appreciate 3D dosimetry workflow and dosimetry procedures, and Observe select examples from the clinic. Sofie Ceberg: Application to dynamic radiotherapy Observe full dosimetry under dynamic radiotherapy during respiratory motion, and Understand how the measurement of high resolution dose data in an

Dosimetry and shielding

International Nuclear Information System (INIS)

Farinelli, U.

1977-01-01

Today, reactor dosimetry and shielding have wide areas of overlap as concerns both problems and methods. Increased interchange of results and know-how would benefit both. The areas of common interest include calculational methods, sensitivity studies, theoretical and experimental benchmarks, cross sections and other nuclear data, multigroup libraries and procedures for their adjustment, experimental techniques and damage functions. This paper reviews the state-of-the-art and the latest development in each of these areas as far as shielding is concerned, and suggests a number of interactions that could be profitable for reactor dosimetry. Among them, re-evaluation of the potentialities of calculational methods (in view of the recent developments) in predicting radiation environments of interest; the application of sensitivity analysis to dosimetry problems; a common effort in the field of theoretical benchmarks; the use of the shielding one-material propagation experiments as reference spectra for detector cross sections; common standardization of the detector nuclear data used in both fields; the setting up of a common (or compatible) multigroup structure and library applicable to shielding, dosimetry and core physics; the exchange of information and experience in the fields of cross section errors, correlations and adjustment; and the intercomparison of experimental techniques

The Latin American Biological Dosimetry Network (LBDNet)

International Nuclear Information System (INIS)

Garcia, O.; Lamadrid, A.I.; Gonzalez, J.E.; Romero, I.; Mandina, T.; Di Giorgio, M.; Radl, A.; Taja, M.R.; Sapienza, C.E.; Deminge, M.M.; Fernandez Rearte, J.; Stuck Oliveira, M.; Valdivia, P.; Guerrero-Carbajal, C.; Arceo Maldonado, C.; Cortina Ramirez, G.E.; Espinoza, M.; Martinez-Lopez, W.; Di Tomasso, M.

2016-01-01

Biological Dosimetry is a necessary support for national radiation protection programmes and emergency response schemes. The Latin American Biological Dosimetry Network (LBDNet) was formally founded in 2007 to provide early biological dosimetry assistance in case of radiation emergencies in the Latin American Region. Here are presented the main topics considered in the foundational document of the network, which comprise: mission, partners, concept of operation, including the mechanism to request support for biological dosimetry assistance in the region, and the network capabilities. The process for network activation and the role of the coordinating laboratory during biological dosimetry emergency response is also presented. This information is preceded by historical remarks on biological dosimetry cooperation in Latin America. A summary of the main experimental and practical results already obtained by the LBDNet is also included. (authors)

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2009-03-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.2 Users’ Manual

Energy Technology Data Exchange (ETDEWEB)

Dr. Bradley J Schrader

2010-10-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.2 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users’ manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods.

Radiological Safety Analysis Computer (RSAC) Program Version 7.0 Users Manual

International Nuclear Information System (INIS)

Schrader, Bradley J.

2009-01-01

The Radiological Safety Analysis Computer (RSAC) Program Version 7.0 (RSAC-7) is the newest version of the RSAC legacy code. It calculates the consequences of a release of radionuclides to the atmosphere. A user can generate a fission product inventory from either reactor operating history or a nuclear criticality event. RSAC-7 models the effects of high-efficiency particulate air filters or other cleanup systems and calculates the decay and ingrowth during transport through processes, facilities, and the environment. Doses are calculated for inhalation, air immersion, ground surface, ingestion, and cloud gamma pathways. RSAC-7 can be used as a tool to evaluate accident conditions in emergency response scenarios, radiological sabotage events and to evaluate safety basis accident consequences. This users manual contains the mathematical models and operating instructions for RSAC-7. Instructions, screens, and examples are provided to guide the user through the functions provided by RSAC-7. This program was designed for users who are familiar with radiological dose assessment methods

Internal dosimetry, past and future

International Nuclear Information System (INIS)

Johnson, J.R.

1989-03-01

This paper is a review of the progress in the dosimetry of internally deposited radionuclides (internal dosimetry) since World War II. Previous to that, only naturally occurring radionuclides were available and only a limited number of studies of biokinetics and dosimetry were done. The main radionuclides studied were 226 Ra, 228 Ra, and 224 Ra but natural uranium was also studied mainly because of its toxic effect as a heavy metal, and not because it was radioactive. The effects of 226 Ra in bone, mainly from the radium dial painters, also formed the only bases for the radiotoxicity of radionuclides in bone for many years, and it is still, along with 224 Ra, the main source of information on the effects of alpha emitters in bone. The publications of the International Commission on Radiological Protection that have an impact on internal dosimetry are used as mileposts for this review. These series of publications, more than any other, represent a broad consensus of opinion within the radiation protection community at the time of their publication, and have formed the bases for radiation protection practice throughout the world. This review is not meant to be exhaustive; it is meant to be a personnel view of the evolution of internal dosimetry, and to present the author's opinion of what the future directions in internal dosimetry will be. 39 refs., 2 tabs

Individual neutron dosimetry

International Nuclear Information System (INIS)

Mauricio, C.L.P.

1987-01-01

The most important concepts and development in individual neutron dosimetry are presented, especially the dosimetric properties of the albedo technique. The main problem in albedo dosimetry is to calibrate the dosemeter in the environs of each neutron source. Some of the most used calibration techniques are discussed. The IRD albedo dosemeter used in the routine neutron individual monitoring is described in detail. Its dosimetric properties and calibration methods are discussed. (Author) [pt

Biosafety Manual

Energy Technology Data Exchange (ETDEWEB)

King, Bruce W.

2010-05-18

Work with or potential exposure to biological materials in the course of performing research or other work activities at Lawrence Berkeley National Laboratory (LBNL) must be conducted in a safe, ethical, environmentally sound, and compliant manner. Work must be conducted in accordance with established biosafety standards, the principles and functions of Integrated Safety Management (ISM), this Biosafety Manual, Chapter 26 (Biosafety) of the Health and Safety Manual (PUB-3000), and applicable standards and LBNL policies. The purpose of the Biosafety Program is to protect workers, the public, agriculture, and the environment from exposure to biological agents or materials that may cause disease or other detrimental effects in humans, animals, or plants. This manual provides workers; line management; Environment, Health, and Safety (EH&S) Division staff; Institutional Biosafety Committee (IBC) members; and others with a comprehensive overview of biosafety principles, requirements from biosafety standards, and measures needed to control biological risks in work activities and facilities at LBNL.

Advantages and disadvantages of luminescence dosimetry

Energy Technology Data Exchange (ETDEWEB)

Olko, Pawel, E-mail: Pawel.Olko@ifj.edu.p [Institute of Nuclear Physics Polish Academy of Science (IFJ PAN), Krakow (Poland)

2010-03-15

Owing to their excellent dosimetric properties, luminescence detectors of ionizing radiation are now extensively applied in individual dosimetry services. The most frequently used personal dosemeters are based on Optically Stimulated Luminescence (OSL), radiophotoluminescence (RPL) or thermoluminescence (TL). Luminescence detectors have also found several applications in clinical dosimetry, especially around new radiation modalities in radiotherapy, such as Intensity Modulated Radiotherapy (IMRT) or ion beam radiotherapy. Requirements of luminescence detectors applied in individual and clinical dosimetry and some recent developments in luminescence of detectors and techniques leading to significant improvements of the functionality and accuracy of dosimetry systems are reviewed and discussed.

Radiation Dosimetry Management: Quality Assurance and Investigations

International Nuclear Information System (INIS)

Perle, S.

2001-01-01

Full text: In a litigation-prone society, it is prudent for any business to evaluate its potential exposure to legal action, initiated by either an employee or a member of the general public. This potential is exacerbated when the phobia of radiation exposure and radioactive materials is interjected into the equation. This phobia is fuelled by the perceived risks of radiation exposure, be they fact or fantasy. With the current cancer incidence rate being approximately 1 in every 2.5 individuals (for all types of cancer), it is imperative that all facilities take a proactive look at their business vulnerability. When radiation exposure is the issue, records documentation is a critical factor, and a significant amount of effort should be expended to implement a comprehensive records management system. A comprehensive Radiation Dosimetry Management Program is essential if a business is going to mitigate any regulatory or legal intervention. This lecture will address appropriate Records Quality Assurance, and, the appropriate requirements for investigations of dosimetry results. (author)

Special photographic emulsions for high LET dosimetry

International Nuclear Information System (INIS)

Katz, R.

1978-12-01

The purpose of these investigations into photographic emulsion dosimetry is to attempt to use the photographic emulsion to mimic the response of human tissues to high LET radiations. The program therefore requires that a systematic understanding of the response of mammalian cells to ionizing radiations be achieved. We have been concerned with differences in RBE and in radiation response to both high and LET radiations, and in the interrelationship between observations with these different radiations

Develpment of quality assurance manual for fabrication of DUPIC fuel

Energy Technology Data Exchange (ETDEWEB)

Lee, Young Gun; Lee, J. W.; Kim, S. S. and others

2001-09-01

The Quality Assurance Manual for the fabrication of DUPIC fuel with high quality was developed. The Quality Assurance Policy established by this manual is to assure that the DUPIC fuel element supplied to customer conform to the specified requirements of customer, applicable codes and standards. The management of KAERI is committed to implementation and maintenance of the program described by this manual. This manual describes the quality assurance program for DUPIC fuel fabrication to comply with CAN3-Z299.2-85 to the extent as needed and appropriate. This manual describes the methods which DUPIC Fuel Development Team(DFDT) personnel must follow to achieve and assure high quality of our product. This manual also describes the quality management system applicable to the activities performed at DFDT.

Develpment of quality assurance manual for fabrication of DUPIC fuel

International Nuclear Information System (INIS)

Lee, Young Gun; Lee, J. W.; Kim, S. S. and others

2001-09-01

The Quality Assurance Manual for the fabrication of DUPIC fuel with high quality was developed. The Quality Assurance Policy established by this manual is to assure that the DUPIC fuel element supplied to customer conform to the specified requirements of customer, applicable codes and standards. The management of KAERI is committed to implementation and maintenance of the program described by this manual. This manual describes the quality assurance program for DUPIC fuel fabrication to comply with CAN3-Z299.2-85 to the extent as needed and appropriate. This manual describes the methods which DUPIC Fuel Development Team(DFDT) personnel must follow to achieve and assure high quality of our product. This manual also describes the quality management system applicable to the activities performed at DFDT

Site security personnel training manual

International Nuclear Information System (INIS)

1978-10-01

As required by 10 CFR Part 73, this training manual provides guidance to assist licensees in the development of security personnel training and qualifications programs. The information contained in the manual typifies the level and scope of training for personnel assigned to perform security related tasks and job duties associated with the protection of nuclear fuel cycle facilities and nuclear power reactors

Accidental and retrospective dosimetry using TL method

International Nuclear Information System (INIS)

Mesterházy, D.; Osvay, M.; Kovács, A.; Kelemen, A.

2012-01-01

Retrospective dosimetry is one of the most important tools of accidental dosimetry for dose estimation when dose measurement was not planned. In the affected area many objects can be applied as natural dosimeters. The paper discusses our recent investigations on various electronic components and common salt (NaCl) having useful thermoluminescence (TL) properties. Among materials investigated the electronic components of cell phones seem promising for retrospective dosimetry purposes, having high TL responses, proper glow curve peaks and the intensity of TL peaks vs. gamma dose received provided nearly linear response in the dose range of 10 mGy–1.5 Gy. - Highlights: ► Electronic components and common salt were investigated for accidental and retrospective dosimetry. ► SMD resistors seem promising for retrospective dosimetry purposes. ► Table salt can be used effectively for accidental dosimetry purposes, as well.

Dosimetry and treatment planning of Occu-Prosta 125I seeds for intraocular lesions

International Nuclear Information System (INIS)

Chaudhari, Suresh; Deshpande, Sudesh; Anand, Vivek; De, Sandeep; Kannan, V.; Saxena, Sanjay; Dash, A.; Basu, Mahua; Samant, Preetam

2008-01-01

Intraocular malignant lesions are frequently encountered in clinical practice. Plaque brachytherapy represents an effective means of treatment for intraocular lesions. Recently Radiopharmaceutical Division, BARC, Mumbai, has indigenously fabricated reasonable-cost 125 I sources. Here we are presenting the preliminary experience of dosimetry of sources, configuration of treatment planning system (TPS) and quality assurance (QA) for eye plaque therapy with Occu-Prosta 125 I seeds, treated in our hospital, for a patient with ocular lesions. 125 I seeds were calibrated using well-type chamber. BrachyVision TPS was configured with Monte Carlo computed radial dose functions and anisotropy functions for 125 I sources. Dose calculated by TPS at different points in central axis and off axis was compared with manually calculated dose. Eye plaque was fabricated of 17 karat pure gold, locally. The seeds were arranged in an outer ring near the edge of the plaque and in concentric rings throughout the plaque. The sources were manually digitized on the TPS, and dose distribution was calculated in three dimensions. Measured activity using cross-calibrated well-type chamber was within ± 10% of the activity specified by the supplier. Difference in TPS-calculated dose and manually calculated dose was within 5%. Treatment time calculated by TPS was in concordance with published data for similar plaque arrangement. (author)

Dosimetry and Calibration Section

International Nuclear Information System (INIS)

Otto, T.

1998-01-01

The two tasks of the Dosimetry and Calibration Section at CERN are the Individual Dosimetry Service which assures the personal monitoring of about 5000 persons potentially exposed to ionizing radiation at CERN, and the Calibration Laboratory which verifies all the instruments and monitors. This equipment is used by the sections of the RP Group for assuring radiation protection around CERN's accelerators, and by the Environmental Section of TISTE. In addition, nearly 250 electronic and 300 quartz fibre dosimeters, employed in operational dosimetry, are calibrated at least once a year. The Individual Dosimetry Service uses an extended database (INDOS) which contains information about all the individual doses ever received at CERN. For most of 1997 it was operated without the support of a database administrator as the technician who had assured this work retired. The Software Support Section of TIS-TE took over the technical responsibility of the database, but in view of the many other tasks of this Section and the lack of personnel, only a few interventions for solving immediate problems were possible

Course of training in Specific internal dosimetry for the patient

International Nuclear Information System (INIS)

Rojo, A.M.; Michelin, S.C.; Gomez P, I.M.

2006-01-01

In this work the experience obtained in a course organized in Argentina to qualify professionals in the radiopharmaceutical dosimetry using the methodology MIRD and the patient's images is presented. The motivation to carry out it was based on the continuous development of new radiopharmaceuticals with therapeutic purposes that makes necessary the knowledge of the distribution of the absorbed dose to be able to establish the dose-response relationship. The main objective was the study of the biokinetic model and those techniques available that starting from images can contribute information of specific parameters of the patient to calculate with more accuracy the doses in the tumor and in different organs. In the design of the program of this course it was considered to approach the different focuses for the calculation of specific dose of the patient and includes the following topics: the patient's radiological protection, new concepts in damages by radiations (bystander effect), methodology for the internal dosimetry by radiopharmaceuticals, dosimetric systems (MIRD/ICRP), revision of the physical phantoms, design of kinetic studies, compartmental models, calculation tools and the demonstration of the programs SAAM and OLINDA; calculation of activity starting from the patient's images (planar and SPECT). Principles of the gamma camera: the dispersed radiation, calculation of the activity with planar images, the attenuation, correction of the dispersed radiation, collimation problems. SPECT: the common method of reconstruction, basic principles, method of filtered over head projection and iterative methods (MLEM/OSEM), measurement of the attenuation maps, problems of the penetration in the collimator (I-131, I-123), effects of partial volume, incorporation of corrections in an iterative reconstruction. Dosimetry in bone marrow, discussion of study cases of new radiopharmaceuticals. Internal dosimetry in small scale for electrons and photons. Perspectives of the

Personal dosimetry service of VF, a.s. company

International Nuclear Information System (INIS)

Prasek, P.

2009-01-01

The VF, a.s. Company will extend its services in the area of personal dosimetry at the end of 2008, which is fully in compliance with the requirements of the Atomic Act, section 9 paragraph (1) letter r) and Decree on Radiation Protection, section 59 paragraph (1) letter a). Optically stimulated luminescence was selected in VF .a.s. as the most advantageous and the most advanced technology for the integral personal dosimetry. Optically stimulated luminescence (OSL) has been using in dosimetry for more than ten years. Although it is relatively new technology , its indisputable advantages predetermine that technology has significantly benefited in personal dosimetry services within a short time all over the advanced world. The VF, a.s. personal dosimetry service is based on the licensed products of LANDAUER, the US company, which is the world leader in OSL dosimetry. Crystalline Al 2 O 3 :C was selected as the detection material. All equipment of personal dosimetry service is installed in the VF Centre of Technology in Cerna Hora. The personal dosimetry service is incorporated in the International LANDAUER Dosimetry Service Network, and in the European Union, it is directly linked to the LANDAUER European Headquarters with its office in Paris. As a part of the OSL technology licence, the VF personal dosimetry service was included in the inter-laboratory comparison programme of the LANDAUER syndicate. (author)

Personal dosimetry service of VF, a.s. company

International Nuclear Information System (INIS)

Prasek, P.

2008-01-01

The VF, a.s. Company will extend its services in the area of personal dosimetry at the end of 2008, which is fully in compliance with the requirements of the Atomic Act, section 9 paragraph (1) letter r) and Decree on Radiation Protection, section 59 paragraph (1) letter a). Optically stimulated luminescence was selected in VF .a.s. as the most advantageous and the most advanced technology for the integral personal dosimetry . Optically stimulated luminescence (OSL) has been using in dosimetry for more than ten years. Although it is relatively new technology , its indisputable advantages predetermine that technology has significantly benefited in personal dosimetry services within a short time all over the advanced world. The VF, a.s. personal dosimetry service is based on the licensed products of LANDAUER, the US company, which is the world leader in OSL dosimetry. Crystalline Al 2 O 3 :C was selected as the detection material. All equipment of personal dosimetry service is installed in the VF Centre of Technology in Cerna Hora. The personal dosimetry service is incorporated in the International LANDAUER Dosimetry Service Network, and in the European Union, it is directly linked to the LANDAUER European Headquarters with its office in Paris. As a part of the OSL technology licence, the VF personal dosimetry service was included in the inter-laboratory comparison programme of the LANDAUER syndicate. (author)

Neutron personal dosimetry: state-of-art

International Nuclear Information System (INIS)

Spurný, František

2005-03-01

State-of-art of the personal neutron dosimetry is presented, analysed and discussed. Particular attention is devoted to the problems of this type of the dosimetry of external exposure for radiation fields at nuclear power plants. A review of general problems of neutron dosimetry is given and the active individual dosimetry methods available and/or in the stage of development are briefly reviewed. Main attention is devoted to the analysis of the methods available for passive individual neutron dosimetry. The characteristics of these dosemeters were studied and are compared: their energy response functions, detection thresholds and the highest detection limits, the linearity of response, the influence of environmental factors, etc. Particular attention is devoted to their behavior in reactor neutron fields. It is concluded that the choice of the neutron personal dosemeter depends largely on the conditions in which the instrument should be used (neutron spectrum, the level of exposure and the exposure rate, etc.). The results obtained with some of these dosemeters during international intercomparisons are also presented. Particular attention is paid to the personal neutron dosimeter developed and routinely used by National Personal Dosimetry Service Ltd. in the Czech Republic. (author)

Pilot program on patient dosimetry in pediatric interventional cardiology in Chile

Energy Technology Data Exchange (ETDEWEB)

Ubeda, Carlos; Vano, Eliseo; Miranda, Patricia; Leyton, Fernando [Clinical Sciences Department, Radiological Sciences Center, Health Sciences Faculty and CHIDE, Tarapaca University, Arica (Chile); Radiology Department, Complutense University and San Carlos Hospital, 28040 Madrid (Spain); Hemodynamic Department, Cardiovascular Service, Luis Calvo Mackenna Hospital, Santiago (Chile); Institute of Public Health of Chile, Marathon 1000, Nunoa, Santiago, Chile and Faculty of Medicine, Diego Portales University, Santiago (Chile)

2012-05-15

Purpose: The aim of this study was to present the results of a pilot program on patient dosimetry carried out in Chile during the last 5 yr, using a biplane x-ray angiography system settled for pediatrics. This research was conducted in Latin America under the auspices of the International Atomic Energy Agency (IAEA) supporting programs on radiological protection (RP) of patients. Methods: Patient age, gender, weight, height, number of cine series, total number of cine frames, fluoroscopy time, and two dosimetric quantities [air kerma-area product (P{sub ka}) and cumulative dose (CD) at the patient entrance reference point] were recorded for each procedure. Results: The study includes 544 patients grouped into four age groups. The distributions by age group were 150 for <1 yr; 203 for 1 to <5 yr; 97 for 5 to <10 yr; and 94 for 10 to <16 yr. Median values of P{sub ka} and CD for the four age groups were 0.94, 1.46, 2.13, and 5.03 Gy cm{sup 2} and 23.9, 26.8, 33.5, and 51.6 mGy, respectively. No significant statistical differences were found between diagnostic and therapeutic procedures. A moderate correlation (r = 0.64) was seen between P{sub ka} and patient weight. Conclusions: The dose values reported in this paper were lower than those published in the previous work for the same age groups as a result of the optimization actions carried out by cardiologists and medical physicists with the support of the IAEA. Methodology and results will be used as a starting point for a wider survey in Chile and Latin America with the goal to obtain regional diagnostic reference levels as recently recommended by the International Commission on Radiological Protection for interventional procedures.

Southern Ductile Training Manual.

Science.gov (United States)

Alabama State Dept. of Education, Montgomery.

This instructor's manual contains the materials required to conduct the competency-based workplace literacy program that was developed to help employees at a foundry that has evolved from a small, family-owned business into a major foundry group with several automated production systems. The workplace literacy program consists of 24 lessons in…

ARDS User Manual

Science.gov (United States)

Fleming, David P.

2001-01-01

Personal computers (PCs) are now used extensively for engineering analysis. their capability exceeds that of mainframe computers of only a few years ago. Programs originally written for mainframes have been ported to PCs to make their use easier. One of these programs is ARDS (Analysis of Rotor Dynamic Systems) which was developed at Arizona State University (ASU) by Nelson et al. to quickly and accurately analyze rotor steady state and transient response using the method of component mode synthesis. The original ARDS program was ported to the PC in 1995. Several extensions were made at ASU to increase the capability of mainframe ARDS. These extensions have also been incorporated into the PC version of ARDS. Each mainframe extension had its own user manual generally covering only that extension. Thus to exploit the full capability of ARDS required a large set of user manuals. Moreover, necessary changes and enhancements for PC ARDS were undocumented. The present document is intended to remedy those problems by combining all pertinent information needed for the use of PC ARDS into one volume.

Dosimetry systems for radiation processing

International Nuclear Information System (INIS)

McLaughlin, W.L.; Desrosiers, M.F.

1995-01-01

Dosimetry serves important functions in radiation processing, where large absorbed doses and dose rates from photon and electron sources have to be measured with reasonable accuracy. Proven dosimetry systems are widely used to perform radiation measurements in development of new processes, validation, qualification and verification (quality control) of established processes and archival documentation of day-to-day and plant-to-plant processing uniformity. Proper calibration and traceability of routine dosimetry systems to standards are crucial to the success of many large-volume radiation processes. Recent innovations and advances in performance of systems that enhance radiation measurement assurance and process diagnostics include dose-mapping media (new radiochromic film and solutions), optical waveguide systems for food irradiation, solid-state devices for real-time and passive dosimetry over wide dose-rate and dose ranges, and improved analytical instruments and data acquisition. (author)

Individual dosimetry of workers and patients: implementation and perspectives; La dosimetrie individuelle des travailleurs et de patients: mise en oeuvre et perspectives

Energy Technology Data Exchange (ETDEWEB)

Rannou, A.; Aubert, B.; Lahaye, Th.; Scaff, P.; Casanova, Ph.; Van Bladel, L.; Queinnec, F.; Valendru, N.; Jehanno, J.; Grude, E.; Berard, Ph.; Desbree, A.; Kafrouni, H.; Paquet, F.; Vanhavere, F.; Bridier, A.; Ginestet, Ch.; Magne, S.; Donadille, L.; Bordy, J.M.; Bottollier-Depois, J.F.; Barrere, J.L.; Ferragut, A.; Metivier, H.; Gaillard-Lecanu, E

2008-07-01

These days organised by the section of the technical protection of the S.F.R.P. review the different techniques of dosimetry used in France and Europe, and present the future orientations.The different interventions are as follow: Individual exposures of the workers: historic assessment and perspectives; medical exposure: where are the doses; legal obligations in individual dosimetry: which are the objective and the need on the subject; the dosimetry follow-up of workers by the S.I.S.E.R.I. system: assessment and perspectives; impact of the norm ISO 20553 on the follow-up of internal exposure; the implementation of the patient dose measurement in Belgium; techniques of passive dosimetry used in Europe; Supervision radiation protection at EDF: long term and short term approach; Comparison active and passive dosimetry at Melox; methodology for the choice of new neutron dosemeters; the working group M.E.D.O.R.: guide of internal dosimetry for the use of practitioners; O.E.D.I.P.E.: tool of modeling for the personalized internal dosimetry; the use of the Monte-Carlo method for the planning of the cancer treatment by radiotherapy becomes a reality; the works of the committee 2 of the ICRP; passive dosimetry versus operational dosimetry: situation in Europe; Implementation of the in vivo dosimetry in a radiotherapy department: experience of the Gustave Roussy institute; experience feedback on the in vivo measures in radiotherapy, based on the use of O.S.L. pellets; multi points O.S.L. instrumentation for the radiation dose monitoring in radiotherapy; dosimetry for extremities for medical applications: principle results of the European contract C.O.N.R.A.D.; references and perspectives in dosimetry; what perspectives for numerical dosimetry, an example: Sievert; system of dose management: how to answer to needs; the last technical evolutions in terms of electronic dosimetry in nuclear power plant; the fourth generation type reactors: what dosimetry. (N.C.)

Information from the Dosimetry Service

CERN Multimedia

2006-01-01

Please note the following opening hours of the Service: From 31st July onwards: Every morning from 8:30 to 12:00 The Service is closed in the afternoons. We should like to remind you that dosimeters cannot be sent to customers by internal mail. Short-term dosimeters (VCTs) must always be returned to the Service after use and must not be left on the racks in the experimental areas or in the secretariats. Dosimetry Service Tel 72155 Bldg. 24 E 011 Dosimetry.service@cern.ch http://cern.ch/rp-dosimetry

Manually controlled neutron-activation system

International Nuclear Information System (INIS)

Johns, R.A.; Carothers, G.A.

1982-01-01

A manually controlled neutron activation system, the Manual Reactor Activation System, was designed and built and has been operating at one of the Savannah River Plant's production reactors. With this system, samples can be irradiated for up to 24 hours and pneumatically transferred to a shielded repository for decay until their activity is low enough for them to be handled at a radiobench. The Manual Reactor Activation System was built to provide neutron activation of solid waste forms for the Alternative Waste Forms Leach Testing Program. Neutron activation of the bulk sample prior to leaching permits sensitive multielement radiometric analyses of the leachates

Dosimetry using environmental and biological materials. Final report

International Nuclear Information System (INIS)

Haskell, E.; Kenner, G.; Hayes, R.

1998-02-01

This report summarizes a five year effort to improve the sensitivity and reliability of retrospective dosimetry methods, to collaborate with laboratories engaged in related research and to share the technology with startup laboratories seeking similar capabilities. This research program has focused on validation of electron paramagnetic resonance (EPR) as a dosimetry tool and on optimization of the technique by reducing the lower limits of detection, simplifying the process of sample preparation and analysis and speeding analysis to allow greater throughput in routine measurement situations. The authors have investigated the dosimetric signal of hard tissues in enamel, deorganified dentin, synthetic carbonated apatites and synthetic hydroxyapatite. This research has resulted in a total of 27 manuscripts which have been published, are in press, or have been submitted for publication. Of these manuscripts, 14 are included in this report and were indexed separately for inclusion in the data base

Proposal of a methodology for quality control in thermoluminescent dosimetry laboratory

International Nuclear Information System (INIS)

Feital, Joao Carlos da S.; Almeida, Claudio Domingues de; Bezerra, Marcos A.

2005-01-01

Taken into account that in thermoluminescence dosimetry adequate selection procedures as well as accurate TLD readings are necessary, this paper presents results of methodology that can be applied as part of quality control programs in thermoluminescence dosimetry laboratories. For the experiment, a set of 200 TLDs ( LiF 100 ) were used and 9 from which were selected, a standard source of Cs -137 , a PTW kiln, a TL 'Harshaw' reader - model 5500 operating under the 'Win Rem' software and a Sr 90 / Y 90 'Bicron' irradiator. In the proceeding the selected dosimeters were irradiated and read 28 times during 18 months, then by one of the standard deviation properties, values up to 14 % were found, for a confidence level of 95 %. The results found and the bibliographic data related to the responses (arbitrary reading) in the crystals used in TLDs, have shown that this methodology can be applied in quality control programs. (author)

Computer Processing 10-20-30. Teacher's Manual. Senior High School Teacher Resource Manual.

Science.gov (United States)

Fisher, Mel; Lautt, Ray

Designed to help teachers meet the program objectives for the computer processing curriculum for senior high schools in the province of Alberta, Canada, this resource manual includes the following sections: (1) program objectives; (2) a flowchart of curriculum modules; (3) suggestions for short- and long-range planning; (4) sample lesson plans;…

The Latin American Biological Dosimetry Network (LBDNet).

Science.gov (United States)

García, O; Di Giorgio, M; Radl, A; Taja, M R; Sapienza, C E; Deminge, M M; Fernández Rearte, J; Stuck Oliveira, M; Valdivia, P; Lamadrid, A I; González, J E; Romero, I; Mandina, T; Guerrero-Carbajal, C; ArceoMaldonado, C; Cortina Ramírez, G E; Espinoza, M; Martínez-López, W; Di Tomasso, M

2016-09-01

Biological Dosimetry is a necessary support for national radiation protection programmes and emergency response schemes. The Latin American Biological Dosimetry Network (LBDNet) was formally founded in 2007 to provide early biological dosimetry assistance in case of radiation emergencies in the Latin American Region. Here are presented the main topics considered in the foundational document of the network, which comprise: mission, partners, concept of operation, including the mechanism to request support for biological dosimetry assistance in the region, and the network capabilities. The process for network activation and the role of the coordinating laboratory during biological dosimetry emergency response is also presented. This information is preceded by historical remarks on biological dosimetry cooperation in Latin America. A summary of the main experimental and practical results already obtained by the LBDNet is also included. © The Author 2016. Published by Oxford University Press. All rights reserved. For Permissions, please email: journals.permissions@oup.com.

Research and innovation in radiation dosimetry

International Nuclear Information System (INIS)

Delgado, A.

1999-01-01

In this article some relevant lines of research in radiation dosimetry are presented. In some of them innovative approaches have been recently proposed in recent years. In others innovation is still to come as it is necessary in view of the insufficiency of the actual methods and techniques. mention is made to Thermoluminescence Dosimetry an to the improvement produced by new computational methods for the analysis of the usually complex TL signals. A solid state dosimetric technique recently proposed, Optically Stimulated Luminescence, OSL, is briefly presented. This technique promises advantages over TLD for personal and environmental dosimetry. The necessity of improving the measurement characteristics of neutron personal dosemeters is commented, making reference to some very recent developments. The situation of the dosimetry in connection with radiobiology research is overviewed, commenting the controversy on the adequacy and utility of the quality absorbed dose for these activities. Finally the special problematic of internal dosimetry is discussed. (Author) 25 refs

Dosimetry control for radiation processing - basic requirements and standards

International Nuclear Information System (INIS)

Ivanova, M.; Tsrunchev, Ts.

2004-01-01

A brief review of the basic international codes and standards for dosimetry control for radiation processing (high doses dosimetry), setting up a dosimetry control for radiation processing and metrology control of the dosimetry system is made. The present state of dosimetry control for food processing and the Bulgarian long experience in food irradiation (three irradiation facilities are operational at these moment) are presented. The absence of neither national standard for high doses nor accredited laboratory for calibration and audit of radiation processing dosimetry systems is also discussed

Dosimetry in dentistry.

Science.gov (United States)

Asha, M L; Chatterjee, Ingita; Patil, Preeti; Naveen, S

2015-01-01

The purpose of this paper was to review various dosimeters used in dentistry and the cumulative results of various studies done with various dosimeters. Several relevant PubMed indexed articles from 1999 to 2013 were electronically searched by typing "dosimeters", "dosimeters in dentistry", "properties of dosimeters", "thermoluminescent and optically stimulated dosimeters", "recent advancements in dosimetry in dentistry." The searches were limited to articles in English to prepare a concise review on dental dosimetry. Titles and abstracts were screened, and articles that fulfilled the criteria of use of dosimeters in dental applications were selected for a full-text reading. Article was divided into four groups: (1) Biological effects of radiation, (2) properties of dosimeters, (3) types of dosimeters and (4) results of various studies using different dosimeters. The present review on dosimetry based on various studies done with dosimeters revealed that, with the advent of radiographic technique the effective dose delivered is low. Therefore, selection of radiological technique plays an important role in dental dose delivery.

Intercalibration of radiological measurements for surveillance purposes of the internal dosimetry laboratory coordinated by the IAEA

International Nuclear Information System (INIS)

Alfaro L, M.M.

2002-07-01

The ININ of Mexico participated in this intercomparison organized by the IAEA in 2000. The objective of this activity is that the dosimetry laboratories that participate can validate the programs of internal dosimetry, with the purpose of improving its capacity in the evaluation of the internal dose and have access to a mechanism to evaluate its dosimetry system under real conditions. The specific objectives of this intercomparison were: 1. To evaluate the participant's capacity to manage the measurements of individual monitoring in terms of the activity in the phantom. 2. To provide the access to the unique calibration resources that otherwise would not be available. 3. To compare the operation of several detection systems, the geometry, phantoms, calibration methods and methods for the evaluation of activity of the radionuclide used by each institution. 4. To provide the independent verification of the direct measurement methods of the dosimetry service. (Author)

Internal dosimetry performing dose assessments via bioassay measurements

International Nuclear Information System (INIS)

Bailey, K.M.

1993-01-01

The Internal Dosimetry Department at the Y-12 Plant maintains a state-of-the-art bioassay program managed under the guidance and regulations of the Department of Energy. The two major bioassay techniques currently used at Y-12 are the in vitro (urinalysis) and in vivo (lung counting) programs. Fecal analysis (as part of the in vitro program) is another alternative; however, since both urine and fecal analysis provide essentially the same capabilities for detecting exposures to uranium, the urinalysis is the main choice primarily for aesthetic reasons. The bioassay frequency is based on meeting NCRP 87 objectives which are to monitor the accumulation of radioactive material in exposed individuals, and to ensure that significant depositions are detected

Technical and quality assurance specifications for dosimetry services

International Nuclear Information System (INIS)

1989-01-01

The Canadian Atomic Energy Control Board (AECB) requires its licensees to establish a program to determine or estimate the radiation doses received by workers exposed to radiation as a result of the licensee's activities. The determination of radiation dose is a two-part process. First a measurement is made; then this measurement is used in a dosimetric model to calculate the dose. This document is concerned only with the first step of the process. It gives guidance on the technical specifications for dosimetry services and the quality assurance program that provides confidence that these specifications are achieved. (L.L.)

Results of the dosimetry intercomparison

International Nuclear Information System (INIS)

Dure, Elsa S.

2000-07-01

The appropriate way to verify the accuracy of the results of dose reported by the laboratories that offer lend personal dosimetry service is in the periodic participation of round of intercomparison dosimetry, undertaken by laboratories whose standards are trace (Secondary Laboratory). The Laboratory of External Personal Dosimetry of the CNEA-PY has participated in three rounds of intercomparison. The first two were organized in the framework of the Model Project RLA/9/030 RADIOLOGICAL WASTE SECURITY, and the irradiations were carried out in the Laboratory of Regional Calibration of the Center of Nuclear Technology Development, Belo Horizonte-Brazil (1998) and in the National Laboratory of Metrology of the ionizing radiations of the Institute of Radioprotection and Dosimetry, Rio de Janeiro-Brazil (1999). The third was organized by the IAEA and the irradiations were made in the Physikalisch-Technische Bundesanstalt PTB, Braunschweig - Federal Republic of Germany (1999-2000) [es

Monte Carlo simulations to replace film dosimetry in IMRT verification

International Nuclear Information System (INIS)

Goetzfried, Thomas; Trautwein, Marius; Koelbi, Oliver; Bogner, Ludwig; Rickhey, Mark

2011-01-01

Patient-specific verification of intensity-modulated radiation therapy (IMRT) plans can be done by dosimetric measurements or by independent dose or monitor unit calculations. The aim of this study was the clinical evaluation of IMRT verification based on a fast Monte Carlo (MC) program with regard to possible benefits compared to commonly used film dosimetry. 25 head-and-neck IMRT plans were recalculated by a pencil beam based treatment planning system (TPS) using an appropriate quality assurance (QA) phantom. All plans were verified both by film and diode dosimetry and compared to MC simulations. The irradiated films, the results of diode measurements and the computed dose distributions were evaluated, and the data were compared on the basis of gamma maps and dose-difference histograms. Average deviations in the high-dose region between diode measurements and point dose calculations performed with the TPS and MC program were 0.7 ± 2.7% and 1.2 ± 3.1%, respectively. For film measurements, the mean gamma values with 3% dose difference and 3 mm distance-to-agreement were 0.74 ± 0.28 (TPS as reference) with dose deviations up to 10%. Corresponding values were significantly reduced to 0.34 ± 0.09 for MC dose calculation. The total time needed for both verification procedures is comparable, however, by far less labor intensive in the case of MC simulations. The presented study showed that independent dose calculation verification of IMRT plans with a fast MC program has the potential to eclipse film dosimetry more and more in the near future. Thus, the linac-specific QA part will necessarily become more important. In combination with MC simulations and due to the simple set-up, point-dose measurements for dosimetric plausibility checks are recommended at least in the IMRT introduction phase. (orig.)

Fostering a culture of interprofessional education for radiation therapy and medical dosimetry students

International Nuclear Information System (INIS)

Lavender, Charlotte; Miller, Seth; Church, Jessica; Chen, Ronald C.; Muresan, Petronella A.; Adams, Robert D.

2014-01-01

A less-studied aspect of radiation therapy and medical dosimetry education is experiential learning through attendance at interprofessional conferences. University of North Carolina radiation therapy and medical dosimetry students regularly attended morning conferences and daily pretreatment peer review, including approximately 145 hours of direct interaction with medical attending physicians and residents, medical physicists, and other faculty. We herein assessed the effect of their participation in these interprofessional conferences on knowledge and communication. The students who graduated from our radiation therapy and medical dosimetry programs who were exposed to the interprofessional education initiative were compared with those who graduated in the previous years. The groups were compared with regard to their knowledge (as assessed by grades on end-of-training examinations) and team communication (assessed via survey). The results for the 2 groups were compared via exact tests. There was a trend for the examination scores for the 2012 cohort to be higher than for the 2007 to 2011 groups. Survey results suggested that students who attended the interprofessional education sessions were more comfortable speaking with attending physicians, residents, physicists, and faculty compared with earlier students who did not attend these educational sessions. Interprofessional education, particularly vertical integration, appears to provide an enhanced educational experience both in regard to knowledge (per the examination scores) and in building a sense of communication (via the survey results). Integration of interprofessional education into radiation therapy and medical dosimetry educational programs may represent an opportunity to enrich the learning experience in multiple ways and merits further study

Fostering a culture of interprofessional education for radiation therapy and medical dosimetry students

Energy Technology Data Exchange (ETDEWEB)

Lavender, Charlotte, E-mail: charlavender@gmail.com; Miller, Seth; Church, Jessica; Chen, Ronald C.; Muresan, Petronella A.; Adams, Robert D.

2014-04-01

A less-studied aspect of radiation therapy and medical dosimetry education is experiential learning through attendance at interprofessional conferences. University of North Carolina radiation therapy and medical dosimetry students regularly attended morning conferences and daily pretreatment peer review, including approximately 145 hours of direct interaction with medical attending physicians and residents, medical physicists, and other faculty. We herein assessed the effect of their participation in these interprofessional conferences on knowledge and communication. The students who graduated from our radiation therapy and medical dosimetry programs who were exposed to the interprofessional education initiative were compared with those who graduated in the previous years. The groups were compared with regard to their knowledge (as assessed by grades on end-of-training examinations) and team communication (assessed via survey). The results for the 2 groups were compared via exact tests. There was a trend for the examination scores for the 2012 cohort to be higher than for the 2007 to 2011 groups. Survey results suggested that students who attended the interprofessional education sessions were more comfortable speaking with attending physicians, residents, physicists, and faculty compared with earlier students who did not attend these educational sessions. Interprofessional education, particularly vertical integration, appears to provide an enhanced educational experience both in regard to knowledge (per the examination scores) and in building a sense of communication (via the survey results). Integration of interprofessional education into radiation therapy and medical dosimetry educational programs may represent an opportunity to enrich the learning experience in multiple ways and merits further study.

Dosimetry standards for radiation processing

International Nuclear Information System (INIS)

Farrar, H. IV

1999-01-01

For irradiation treatments to be reproducible in the laboratory and then in the commercial environment, and for products to have certified absorbed doses, standardized dosimetry techniques are needed. This need is being satisfied by standards being developed by experts from around the world under the auspices of Subcommittee E10.01 of the American Society for Testing and Materials (ASTM). In the time period since it was formed in 1984, the subcommittee has grown to 150 members from 43 countries, representing a broad cross-section of industry, government and university interests. With cooperation from other international organizations, it has taken the combined part-time effort of all these people more than 13 years to complete 24 dosimetry standards. Four are specifically for food irradiation or agricultural applications, but the majority apply to all forms of gamma, x-ray, Bremsstrahlung and electron beam radiation processing, including dosimetry for sterilization of health care products and the radiation processing of fruits, vegetables, meats, spices, processed foods, plastics, inks, medical wastes and paper. An additional 6 standards are under development. Most of the standards provide exact procedures for using individual dosimetry systems or for characterizing various types of irradiation facilities, but one covers the selection and calibration of dosimetry systems, and another covers the treatment of uncertainties. Together, this set of standards covers essentially all aspects of dosimetry for radiation processing. The first 20 of these standards have been adopted in their present form by the International Organization of Standardization (ISO), and will be published by ISO in 1999. (author)

Transuranic waste characterization sampling and analysis methods manual. Revision 1

International Nuclear Information System (INIS)

Suermann, J.F.

1996-04-01

This Methods Manual provides a unified source of information on the sampling and analytical techniques that enable Department of Energy (DOE) facilities to comply with the requirements established in the current revision of the Transuranic Waste Characterization Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP) Transuranic (TRU) Waste Characterization Program (the Program) and the WIPP Waste Analysis Plan. This Methods Manual includes all of the testing, sampling, and analytical methodologies accepted by DOE for use in implementing the Program requirements specified in the QAPP and the WIPP Waste Analysis Plan. The procedures in this Methods Manual are comprehensive and detailed and are designed to provide the necessary guidance for the preparation of site-specific procedures. With some analytical methods, such as Gas Chromatography/Mass Spectrometry, the Methods Manual procedures may be used directly. With other methods, such as nondestructive characterization, the Methods Manual provides guidance rather than a step-by-step procedure. Sites must meet all of the specified quality control requirements of the applicable procedure. Each DOE site must document the details of the procedures it will use and demonstrate the efficacy of such procedures to the Manager, National TRU Program Waste Characterization, during Waste Characterization and Certification audits

Individual dosimetry of workers and patients: implementation and perspectives

International Nuclear Information System (INIS)

Rannou, A.; Aubert, B.; Lahaye, Th.; Scaff, P.; Casanova, Ph.; Van Bladel, L.; Queinnec, F.; Valendru, N.; Jehanno, J.; Grude, E.; Berard, Ph.; Desbree, A.; Kafrouni, H.; Paquet, F.; Vanhavere, F.; Bridier, A.; Ginestet, Ch.; Magne, S.; Donadille, L.; Bordy, J.M.; Bottollier-Depois, J.F.; Barrere, J.L.; Ferragut, A.; Metivier, H.; Gaillard-Lecanu, E.

2008-01-01

These days organised by the section of the technical protection of the S.F.R.P. review the different techniques of dosimetry used in France and Europe, and present the future orientations.The different interventions are as follow: Individual exposures of the workers: historic assessment and perspectives; medical exposure: where are the doses; legal obligations in individual dosimetry: which are the objective and the need on the subject; the dosimetry follow-up of workers by the S.I.S.E.R.I. system: assessment and perspectives; impact of the norm ISO 20553 on the follow-up of internal exposure; the implementation of the patient dose measurement in Belgium; techniques of passive dosimetry used in Europe; Supervision radiation protection at EDF: long term and short term approach; Comparison active and passive dosimetry at Melox; methodology for the choice of new neutron dosemeters; the working group M.E.D.O.R.: guide of internal dosimetry for the use of practitioners; O.E.D.I.P.E.: tool of modeling for the personalized internal dosimetry; the use of the Monte-Carlo method for the planning of the cancer treatment by radiotherapy becomes a reality; the works of the committee 2 of the ICRP; passive dosimetry versus operational dosimetry: situation in Europe; Implementation of the in vivo dosimetry in a radiotherapy department: experience of the Gustave Roussy institute; experience feedback on the in vivo measures in radiotherapy, based on the use of O.S.L. pellets; multi points O.S.L. instrumentation for the radiation dose monitoring in radiotherapy; dosimetry for extremities for medical applications: principle results of the European contract C.O.N.R.A.D.; references and perspectives in dosimetry; what perspectives for numerical dosimetry, an example: Sievert; system of dose management: how to answer to needs; the last technical evolutions in terms of electronic dosimetry in nuclear power plant; the fourth generation type reactors: what dosimetry. (N.C.)

The dosimetry programme of the IAEA

International Nuclear Information System (INIS)

1987-01-01

Describes the activities of the IAEA's Dosimetry Laboratory which provides calibration and comparison services for secondary standard dosimetry laboratories (SSDLs) of Member States. In addition, a joint IAEA/WHO postal dosimetry service has been established for radiotherapy centers. The International Measurement System and the calibration ''chain'' from measurement standard instruments of the International Bureau of Weights and Measurements (BIPM) through the primary and secondary standards to the dosimeters of the users are presented as well

Field manual for stream water and sediment reconnaissance

International Nuclear Information System (INIS)

Ferguson, R.B.; Price, V.; Baucom, E.I.

1977-11-01

A manual is presented that is intended to direct and coordinate field operations, site selection, sample collection, and information codes for the Savannah River Laboratory (SRL) contribution to the National Uranium Resource Evaluation (NURE) program. The manual provides technical direction and public relations information for field sampling teams. The program is being conducted to evaluate domestic uranium resources and to identify favorable areas for commercial exploration. The NURE program is expected to increase the activity of commercial exploration for uranium in the United States

Hematological dosimetry

International Nuclear Information System (INIS)

Fluery-Herard, A.

1991-01-01

The principles of hematological dosimetry after acute or protracted whole-body irradiation are reviewed. In both cases, over-exposure is never homogeneous and the clinical consequences, viz medullary aplasia, are directly associated with the mean absorbed dose and the seriousness and location of the overexposure. The main hematological data required to assess the seriousness of exposure are the following: repeated blood analysis, blood precursor cultures, as indicators of whole-body exposure; bone marrow puncture, medullary precursor cultures and medullary scintigraphy as indicators of the importance of a local over-exposure and capacity for spontaneous repair. These paraclinical investigations, which are essential for diagnosis and dosimetry, are also used for surveillance and for the main therapeutic issues [fr

Quality assurance in personal dosimetry of external radiation: present situation and future needs

International Nuclear Information System (INIS)

Ma, N.

2006-01-01

Whole body personal dosimetry is well established for the individual monitoring of radiation workers. High quality radiation dosimetry is essential for workers who rely upon personal dosemeters to record the amount of radiation to which they are exposed. The mandate has been given to the Personal Dosimetry, (secondary standard dosimetry laboratories) S.S.D.L., (Malaysian institute for nuclear energy research) M.I.N.T. to assure the individual monitoring for radiation workers in Malaysia. In 2005, the S.S.D.L;-M.I.N.T. supply, process and read out of personal dosemeters of nearly 13,000 dosimeters monthly, whereby. 12,000 are films and 1,000 are T.L.D.s. The objective of individual monitoring is not limited to the measurement of doses delivered to individuals, but it should demonstrate that limits of exposure have not been exceeded and that working conditions have not unexpectedly deteriorated. Dosimetry measurements are an important component of radiation protection programs and must be of high quality. The exposure of workers to radiation must be controlled and monitored in order to comply with regulatory requirements. S.S.D.L.-M.I.N.T; demonstrates that its performance is at an acceptable level by implementing overall system performance, as evidenced by the ISO 9001 certification of the Personal Dosimetry Service in 2002 and ISO/I.E.C. 17025 accreditation to the calibration laboratory in 2004. The certification and accreditation processes achieved the goal by formalizing the recognition of satisfactory performance, and providing evidence of this performance. Overall performances are assessed, personnel operating the system will be trained and are well qualified and all actions will be documented. The paper describes the overview of the Q.M.S. carried out at the S.S. D.L.-M.I.N.T.. During the implementation of Q.M.S. a few areas has been identified for future consideration. These include performance specification and type testing of dosemeters, which provide a

The Weatherization Assistant User's Manual (Version 8.9)

Energy Technology Data Exchange (ETDEWEB)

Gettings, Michael B. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Malhotra, Mini [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Ternes, Mark P. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2015-01-01

The Weatherization Assistant is a Windows-based energy audit software tool that was developed by Oak Ridge National Laboratory (ORNL) to help states and their local weatherization agencies implement the U.S. Department of Energy (DOE) Weatherization Assistance Program. The Weatherization Assistant is an umbrella program for two individual energy audits or measure selection programs: the National Energy Audit Tool (NEAT) for site-built single-family homes and the Manufactured Home Energy Audit (MHEA) for mobile homes. The Weatherization Assistant User's Manual documents the operation of the user interface for Version 8.9 of the software. This includes how to install and setup the software, navigate through the program, and initiate an energy audit. All of the user interface forms associated with the software and the data fields on these forms are described in detail. The manual is intended to be a training manual for new users of the Weatherization Assistant and as a reference manual for experienced users.

The National Energy Audit (NEAT) Engineering Manual (Version 6)

Energy Technology Data Exchange (ETDEWEB)

Gettings, M.B.

2001-04-20

Government-funded weatherization assistance programs resulted from increased oil prices caused by the 1973 oil embargo. These programs were instituted to reduce US consumption of oil and help low-income families afford the increasing cost of heating their homes. In the summer of 1988, Oak Ridge National Laboratory (ORNL) began providing technical support to the Department of Energy (DOE) Weatherization Assistance Program (WAP). A preliminary study found no suitable means of cost-effectively selecting energy efficiency improvements (measures) for single-family homes that incorporated all the factors seen as beneficial in improving cost-effectiveness and usability. In mid-1989, ORNL was authorized to begin development of a computer-based measure selection technique. In November of 1992 a draft version of the program was made available to all WAP state directors for testing. The first production release, Version 4.3, was made available in october of 1993. The Department of Energy's Weatherization Assistance Program has continued funding improvements to the program increasing its user-friendliness and applicability. initial publication of this engineering manual coincides with availability of Version 6.1, November 1997, though algorithms described generally apply to all prior versions. Periodic updates of specific sections in the manual will permit maintaining a relevant document. This Engineering Manual delineates the assumptions used by NEAT in arriving at the measure recommendations based on the user's input of the building characteristics. Details of the actual data entry are available in the NEAT User's Manual (ORNL/Sub/91-SK078/1) and will not be discussed in this manual.

Generic communications index: User's manual

International Nuclear Information System (INIS)

Dean, R.S.; Steinbrecher, D.H.; Hennick, A.

1987-12-01

This report is a manual for providing information required to use a special computer program developed by the NRC for indexing generic communications. The program is written in a user-friendly menu driven form using dBASE III programming language. It facilitates use of the required dBASE III search and sort capabilities to access records in a database called Generic Communications Index. This index is made up of one record each for all bulletins, circulars, and information notices, including revisions and supplements, from 1971, when such documentation started, through 1986 (or to the latest update). The program is designed for use by anyone modestly acquainted with the general use of IBM-compatible personal computers. The manual contains both a brief overview and a detailed description of the program, as well as detailed instructions for getting started using the program on a personal computer with either a two-floppy disk or a hard disk system. Included at the end are a brief description of how to handle problems which might occur, and notes on the makeup of the program and database files for help in adding records of communications for future years

Development and current state of dosimetry in Cuba

International Nuclear Information System (INIS)

Prieto Miranda, E.F.; Cuesta Fuente, G.; Chavez Ardanza, A.

1999-01-01

In Cuba, the application of the radiation technologies has been growing in the last years, and at present there are several dosimetry systems with different ranges of absorbed dose. Diverse researches were carried out on high dose dosimetry with the following dosimetry systems: Fricke, ceric-cerous sulfate, ethanol-chlorobenzene, cupric sulfate and Perspex (Red 4034 AE and Clear HX). In this paper the development achieved during the last 15 years in the high dose dosimetry for radiation processing in Cuba is presented, as well as, the current state of different dosimetry systems employed for standardization and for process control. The paper also reports the results of dosimetry intercomparison studies that were performed with the Ezeiza Atomic Center of Argentine and the International Dose Assurance Service (IDAS) of IAEA. (author)

The Development of a Postgraduate Orthopaedic Manual Therapy Residency Program in Nairobi, Kenya.

Science.gov (United States)

Cunningham, Shala; Jackson, Richard; Muli, Daniel Kangutu; McFelea, Joni

2017-01-01

There are very few opportunities for long-term, comprehensive postgraduate education in developing countries because of fiscal and human resource constraints. Therefore, physiotherapists have little opportunity following graduation to advance their skills through the improvement of clinical reasoning and treatment planning and application. To address the need for sustainable advanced instruction in physiotherapy within the country, a postgraduate Residency program was initiated in Nairobi, Kenya in 2012. The mission of the program is to graduate advanced orthopedic practitioners who can lead their communities and local profession in the advancement of clinical care and education. Since its inception, six cohorts have been initiated for a total of 90 resident participants. In addition, six program graduates are being trained to continue the Residency program and are serving as teaching assistants for the on campus modules. This training will result in a self-sustaining program by 2020. The manual therapy Residency education model allowed for advancement of the participating physiotherapists professional development utilizing evidence-based practice. This was done without altering the current education system within the country, or accessing expensive equipment. The Residency program was developed and established with the cooperation of a local education institution and a non-profit corporation in the United States. This collaboration has facilitated the advancement of orthopedic clinical standards in the country and will, hopefully, one day serve an as a template for future programs.

Miniature semiconductor detectors for in vivo dosimetry

International Nuclear Information System (INIS)

Rosenfeld, A. B.; Cutajar, D.; Lerch, M. L. F.; Takacs, G.; Cornelius, I. M.; Yudelev, M.; Zaider, M.

2006-01-01

Silicon mini-semiconductor detectors are found in wide applications for in vivo personal dosimetry and dosimetry and Micro-dosimetry of different radiation oncology modalities. These applications are based on integral and spectroscopy modes of metal oxide semiconductor field effect transistor and silicon p-n junction detectors. The advantages and limitations of each are discussed. (authors)

Dosimetry quality audit of high energy photon beams in greek radiotherapy centers

International Nuclear Information System (INIS)

Hourdakis, Constantine J.; Boziari, A.

2008-01-01

discussed in details. Conclusion: This quality audit proved to be a useful tool for the improvement of quality in radiotherapy. It succeeded to disseminate the IAEA TRS-398 protocol in nearly all radiotherapy centers achieving homogenization and consistency of dosimetry within the country. Also, it detected discrepancies in dosimetry and provided guidance and recommendations to eliminate sources of errors. Finally, it proved that quality assurance programs, periodic quality control tests, maintenance and service play an important role for achieving accuracy and safe operation in radiotherapy

Dosimetry quality audit of high energy photon beams in greek radiotherapy centers.

Science.gov (United States)

Hourdakis, Constantine J; Boziari, A

2008-04-01

useful tool for the improvement of quality in radiotherapy. It succeeded to disseminate the IAEA TRS-398 protocol in nearly all radiotherapy centers achieving homogenization and consistency of dosimetry within the country. Also, it detected discrepancies in dosimetry and provided guidance and recommendations to eliminate sources of errors. Finally, it proved that quality assurance programs, periodic quality control tests, maintenance and service play an important role for achieving accuracy and safe operation in radiotherapy.

Chemical dosimetry system for criticality accidents.

Science.gov (United States)

Miljanić, Saveta; Ilijas, Boris

2004-01-01

Ruder Bosković Institute (RBI) criticality dosimetry system consists of a chemical dosimetry system for measuring the total (neutron + gamma) dose, and a thermoluminescent (TL) dosimetry system for a separate determination of the gamma ray component. The use of the chemical dosemeter solution chlorobenzene-ethanol-trimethylpentane (CET) is based on the radiolytic formation of hydrochloric acid, which protonates a pH indicator, thymolsulphonphthalein. The high molar absorptivity of its red form at 552 nm is responsible for a high sensitivity of the system: doses in the range 0.2-15 Gy can be measured. The dosemeter has been designed as a glass ampoule filled with the CET solution and inserted into a pen-shaped plastic holder. For dose determinations, a newly constructed optoelectronic reader has been used. The RBI team took part in the International Intercomparison of Criticality Accident Dosimetry Systems at the SILENE Reactor, Valduc, June 2002, with the CET dosimetry system. For gamma ray dose determination TLD-700 TL detectors were used. The results obtained with CET dosemeter show very good agreement with the reference values.

Retrospective individual dosimetry using EPR of tooth enamel

International Nuclear Information System (INIS)

Skvortzo, V.; Ivannikov, A.; Stepanenko, V.; Wieser, A.; Bougai, A.; Brick, A.; Chumak, V.; Radchuk, V.; Repin, V.; Kirilov, V.

1996-01-01

The results of joint investigations (in the framework of ECP-10 program) aimed on the improvement of the sensitivity and accuracy of the procedure of dose measurement using tooth enamel EPR spectroscopy are presented. It is shown, what the sensitivity of method may be increased using special physical-chemical procedure of the enamel samples treatment, which leads to the reducing of EPR signal of organic components in enamel. Tooth diseases may have an effect on radiation sensitivity of enamel. On the basis of statistical analysis of the results of more then 2000 tooth enamel samples measurements it was shown, what tooth enamel EPR spectroscopy gives opportunity to register contribution into total dose, which is caused by natural environmental radiation and by radioactive contamination. EPR response of enamel to ultraviolet exposure is investigated and possible influences to EPR dosimetry is discussed. The correction factors for EPR dosimetry in real radiation fields are estimated

Overview of the EMRAS biota dosimetry working group

International Nuclear Information System (INIS)

Kawaguchi, Isao; Doi, Masahiro

2008-01-01

Current principle of radiation protection systems is protection of human, because the human is assumed as the most sensitive organism. Protection framework of human is also believed to be effective for protection of non-human species. On the other hand, it is recently attracting the international interests how sustainability of the ecological services is influenced by environmental disturbances such as chemicals and radiation. Therefore, international concern about protection framework of nonhuman biota has arisen. By the international concern, European and American countries were respectively developed models to evaluate effects of radiation to biota. However, the models are based on their own assumptions, so that the international validity has not been confirmed. Therefore, in IAEA, biota dosimetry working group (BWG) was established in Environmental Modeling for Radiation Safety (EMRAS) program, which aimed to intercompare the models to validate their assumptions and estimations. This paper reports summary of the activity in EMRAS biota dosimetry working group. (author)

CANAL user's manual

International Nuclear Information System (INIS)

Faya, A.; Wolf, L.; Todreas, N.

1979-11-01

CANAL is a subchannel computer program for the steady-state and transient thermal hydraulic analysis of BWR fuel rod bundles. The purpose of this manual is to introduce the user into the mechanism of running the code by providing information about the input data and options

Electronic database of patients in radiotherapy: Amedatos

International Nuclear Information System (INIS)

Perez Guevara, Adrian; Rodriguez Zayas, Michael; Gonzalez Perez, Yelina; Sola Rodriguez, Yeline; Reyes Gonzalez, Tommy; Caballero, Roberto

2009-01-01

Registration and monitoring of patients in the departments of radiotherapy in our country are taken manually, which is difficult when very large number of patients and treatment units in service. Due to these problems in the Department of Radiotherapy 'Hospital Hermanos Ameijeiras' AMEDATOS program was designed in Microsoft Excel. The main program relates different books, macros are used to improve visualization and facilitate the management of data on different sheets (dosimetry, Team, Daily Record, Record monitoring, patient data, dosimetry data, not treated and four sheets of Report). (Author)