Radiation Safety: New International Standards

Total Page:16

File Type:pdf, Size:1020Kb

Radiation Safety: New International Standards FEATURES Radiation safety: New international standards The forthcoming International Basic Safety Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources are the product of unprecedented co-operation by Abel J. B*y the end of the 1980s, a vast amount of new This article highlights an important result of Gonzalez information had accumulated to prompt a new this work for the international harmonization of look at the standards governing protection radiation safety: specifically, it presents an over- against exposures to ionizing radiation and the view of the forthcoming International Basic safety of radiation sources. Safety Standards for Protection Against Ionizing First and foremost, a re-evaluation of the Radiation and for the Safety of Radiation Sour- radioepidemiological findings from Hiroshima ces — the so-called BSS. They have been jointly and Nagasaki suggested that exposure to low- developed by six organizations — the Food and level radiation was riskier than previously es- Agriculture Organization of the United Nations timated. (FAO), the International Atomic Energy Agency Other developments — notably the nuclear (IAEA), the International Labour Organization accidents at Three Mile Island in 1979 and at (ILO), the Nuclear Energy Agency of the Or- Chernobyl in 1986 with its unprecedented ganization for Economic Co-operation and transboundary contamination — had a great ef- Development (NEA/OECD), the Pan American fect on the public perception of the potential Health Organization (PAHO), and the World danger from radiation exposure. Accidents with Health Organization (WHO). radiation sources used in medicine and industry also have attracted widespread public attention: Cuidad Juarez (Mexico), Mohamadia (Moroc- The framework for harmonization co), Goiania (Brazil), San Salvador (El Sal- vador), and Zaragoza (Spain) are names that ap- In 1991, within the framework of the Inter- peared in the news after people were injured in agency Committee on Radiation Safety, the six radiation accidents. Furthermore, the decade saw organizations created a Joint Secretariat under the rediscovery of natural radiation as a cause of the co-ordination of the IAEA. The action concern for health: some dwellings were found capped decades of continuing efforts and marked to have surprisingly high levels of radon in air; an unprecedented international co-operation that natural radiation exposures of some non-radia- has involved hundreds of experts from the Mem- tion-related workers were discovered to be at ber States of the sponsoring organizations for levels much higher than the occupational limits establishing the BSS. These international stand- specified in recognized standards. ards supersede any previous ones in the field of Following these developments, the Interna- radiation safety, in particular those developed tional Commission on Radiological Protection under the auspices of the IAEA. (See box, next (ICRP) in 1990 revised its standing recommen- page.) dations. The concerned organizations of the Radiation effects. From the time of early United Nations family and other multinational studies on X-rays and radioactive minerals it was agencies promptly followed by triggering a recognized that exposure to high levels of radia- review of their own standards. tion can harm exposed tissues of the human body. These radiation effects can be clinically diagnosed in the exposed individual; they are called deterministic effects because, given a Dr Gonzalez is Deputy Director of the IAEA Division of radiation dose, they are determined to occur. Nuclear Safety. Posteriorly, long-term studies of populations ex- IAEA BULLETIN, 2/1994 FEATURES A number of bodies have supported the United Nations Scientific Committee on International work to harmonize international radiation the Effects of Atomic Radiation (UNSCEAR). harmonization in safety standards which draw upon information In developing the BSS, UNSCEAR provided radiation safety derived from extensive research and develop- the scientific information on which the stand- ment by scientific and engineering organiza- ards are based. The Committee — which was tions at national and international levels. For established by the UN General Assembly in its part, the IAEA has the statutory authoriza- 1955 and today includes representatives from tion to establish or adopt, in consultation and, 21 countries — compiles, assesses, and dis- where appropriate, in collaboration with the seminates information on the health effects of competent organs of the United Nations and radiation and on the levels of radiation ex- with the specialized agencies concerned, posure from different sources. standards of safety for protection of health...". International Commission on Radiologi- In discharging this function, the IAEA Board of cal Protection (ICRP). Radiation safety stand- Governors first approved Agency health and ards are based on the recommendations of the safety measures in March 1960. The Board ICRP, a non-governmental scientific organiza- approved the first version of the IAEA's Basic tion founded in 1928. Its most recent recommen- Safety Standards for Radiation Protection in dations were issued in 1990 (Publication 60, June 1962 and a revised version in September Annals of the ICRP, Vol. 21, No.1-3)) and form 1965. A third revision was published by the IAEA the basis of the BSS. as the 1982 Edition of Safely Series No. 9; this International Commission on Radiation edition was jointly sponsored by the IAEA, fie Units and Measurements (ICRU). The quan- ILO, the OECD/NEA, and the WHO.* tities and units used in the BSS are primarily The Inter-Agency Committee on Radia- those recommended by the ICRU, a sister or- tion Safety (IACRS). A number of years ago, ganization of the ICRP. (See box, next page.) the IAEA promoted the formation of IACRS as The International Nuclear Safety Ad- a mechanism for consultation and collabora- visory Group (INSAG). This advisory body of tion in radiation safety matters with competent nuclear safety experts serves as a forum for organs of the United Nations and with the the exchange of information and for the specialized agencies. The Committee aims provision of advice to the IAEA on safety is- inter alia to encourage the co-ordination of sues of international significance. In 1988, it policies and consistency in radiation safety issued through the IAEA the Basic Safety Prin- principles and standards. Members are the ciples for Nuclear Power Plants (Safety Series FAO, ILO, NEA/OECD, PAHO, UNSCEAR, No. 75-INSAG-3). Many of these principles are WHO, Commission of the European Com- relevant to the safety of other radiation sour- munities (CEC) and the IAEA. A number of ces and installations and have been used in organizations — the ICRP, the International the BSS. Commission on Radiation Units and Measure- ments (ICRU), the International Electrotechni- cal Commission (IEC), the International Radiation Protection Association (IRPA) and * For a description of these previous international the International Standards Organization standards see the author's article in the IAEA Bul- (ISO) — have observer status. letin; Vol. 25, No. 3; (September 1983). posed to radiation, especially of the survivors of the advance, may be expected to increase the back- atomic bombing of Hiroshima and Nagasaki, have ground exposure that people already receive: demonstrated that exposure to radiation also has a they are termed practices. potential for the delayed induction of malignancies On the other hand, there are radiation ex- and possibly of hereditary effects. These radiation posures incurred de facto by people. The ac- effects cannot be related to any particular in- tivities which are intended to reduce these ex- dividual exposed but can be inferred from posures are termed interventions. epidemiological studies of large populations; Because of the radiation effects on health, they are called stochastic effects because of their practices and interventions need to be subject to aleatory statistical nature. (See box, next page.) certain standards of radiation safety to protect Human activities and radiation exposure: those persons adventitiously exposed.The BSS practices and interventions. Many beneficial are intended to harmonize internationally the human activities involve the exposure of people basic requirements for protecting people against to radiation from both natural and man-made undue radiation exposure in practices and inter- sources. These activities, which are planned in ventions. (See box, page 5.) IAEA BULLETIN, 2/1994 FEATURES Radiation health effects Exposure to radiation can cause detrimental health ef- impair the function of the exposed tissue. The severity of a fects. At large acute doses, radiation effects — such as particular deterministic effect is higher as doses increase nausea, reddening of the skin and, in severe cases, acute above the threshold which varies depending on the type of syndromes — are clinically expressed in exposed in- effects. The lower thresholds are a few sieverts for acute dividuals within a short period of time after exposure. Large exposures and a few hundred millisieverts per year for chronic dose rates also cause clinically detectable chronic exposures. The likelihood of incurring the deter- deleterious effects. These effects are called deterministic ministic effect, therefore, is nil at lower doses and ap- because they are certain to occur if the dose exceeds a proaches certainty at threshold doses. certain threshold level.
Recommended publications
  • 小型飛翔体/海外 [Format 2] Technical Catalog Category
    小型飛翔体/海外 [Format 2] Technical Catalog Category Airborne contamination sensor Title Depth Evaluation of Entrained Products (DEEP) Proposed by Create Technologies Ltd & Costain Group PLC 1.DEEP is a sensor analysis software for analysing contamination. DEEP can distinguish between surface contamination and internal / absorbed contamination. The software measures contamination depth by analysing distortions in the gamma spectrum. The method can be applied to data gathered using any spectrometer. Because DEEP provides a means of discriminating surface contamination from other radiation sources, DEEP can be used to provide an estimate of surface contamination without physical sampling. DEEP is a real-time method which enables the user to generate a large number of rapid contamination assessments- this data is complementary to physical samples, providing a sound basis for extrapolation from point samples. It also helps identify anomalies enabling targeted sampling startegies. DEEP is compatible with small airborne spectrometer/ processor combinations, such as that proposed by the ARM-U project – please refer to the ARM-U proposal for more details of the air vehicle. Figure 1: DEEP system core components are small, light, low power and can be integrated via USB, serial or Ethernet interfaces. 小型飛翔体/海外 Figure 2: DEEP prototype software 2.Past experience (plants in Japan, overseas plant, applications in other industries, etc) Create technologies is a specialist R&D firm with a focus on imaging and sensing in the nuclear industry. Createc has developed and delivered several novel nuclear technologies, including the N-Visage gamma camera system. Costainis a leading UK construction and civil engineering firm with almost 150 years of history.
    [Show full text]
  • Radiation Risk in Perspective
    PS010-1 RADIATION RISK IN PERSPECTIVE POSITION STATEMENT OF THE HEALTH HEALTH PHYSICS SOCIETY* PHYSICS SOCIETY Adopted: January 1996 Revised: August 2004 Contact: Richard J. Burk, Jr. Executive Secretary Health Physics Society Telephone: 703-790-1745 Fax: 703-790-2672 Email: [email protected] http://www.hps.org In accordance with current knowledge of radiation health risks, the Health Physics Society recommends against quantitative estimation of health risks below an individual dose of 5 rem1 in one year or a lifetime dose of 10 rem above that received from natural sources. Doses from natural background radiation in the United States average about 0.3 rem per year. A dose of 5 rem will be accumulated in the first 17 years of life and about 25 rem in a lifetime of 80 years. Estimation of health risk associated with radiation doses that are of similar magnitude as those received from natural sources should be strictly qualitative and encompass a range of hypothetical health outcomes, including the possibility of no adverse health effects at such low levels. There is substantial and convincing scientific evidence for health risks following high-dose exposures. However, below 5–10 rem (which includes occupational and environmental exposures), risks of health effects are either too small to be observed or are nonexistent. In part because of the insurmountable intrinsic and methodological difficulties in determining if the health effects that are demonstrated at high radiation doses are also present at low doses, current radiation protection standards and practices are based on the premise that any radiation dose, no matter how small, may result in detrimental health effects, such as cancer and hereditary genetic damage.
    [Show full text]
  • G20070354/G20070331 Fact Sheet, Biological Effects of Radiation
    Fact Sheet 11 Ofice of Public Affairs Telephone: 301/415-8200 E-mail : opa @nrc.g ov I Biological Effects of Radiation Background Radiation is all around us. It is naturally present in our environment and has been since the birth of this planet. Consequently, life has evolved in an environment which has significant levels of ionizing radiation. It comes from outer space (cosmic), the ground (terrestrial), and even from within our own bodies. It is present in the air we breathe, the food we eat, the water we drink, and in the construction materials used to build our homes. Certain foods such as bananas and brazil nuts naturally contain higher levels of radiation than other foods. Brick and stone homes have higher natural radiation levels than homes made of other building materials such as wood. Our nation's Capitol, which is largely constructed of granite, contains higher levels of natural radiation than most homes. Levels of natural or background radiation can vary greatly from one location to the next. For example, people residing in Colorado are exposed to more natural radiation than residents of the east or west coast because Colorado has more cosmic radiation at a higher altitude and more terrestrial radiation from soils enriched in naturally occurring uranium. Furthermore, a lot of our natural exposure is due to radon, a gas from the earth's crust that is present in the air we breathe. The average annual radiation exposure from natural sources to an individual in the United States is about 300 millirem (3 millisieverts)*. Radon gas accounts for two-thirds of this exposure, while cosmic, terrestrial, and internal radiation account for the remainder.
    [Show full text]
  • Estimation of the Collective Effective Dose to the Population from Medical X-Ray Examinations in Finland
    Estimation of the collective effective dose to the population from medical x-ray examinations in Finland Petra Tenkanen-Rautakoskia, Hannu Järvinena, Ritva Blya aRadiation and Nuclear Safety Authority (STUK), PL 14, 00880 Helsinki, Finland Abstract. The collective effective dose to the population from all x-ray examinations in Finland in 2005 was estimated. The numbers of x-ray examinations were collected by a questionnaire to the health care units (response rate 100 %). The effective doses in plain radiography were calculated using a Monte Carlo based program (PCXMC), as average values for selected health care units. For computed tomography (CT), weighted dose length product (DLPw) in a standard phantom was measured for routine CT protocols of four body regions, for 80 % of CT scanners including all types. The effective doses were calculated from DPLw values using published conversion factors. For contrast-enhanced radiology and interventional radiology, the effective dose was estimated mainly by using published DAP values and conversion factors for given body regions. About 733 examinations per 1000 inhabitants (excluding dental) were made in 2005, slightly less than in 2000. The proportions of plain radiography, computed tomography, contrast-enhanced radiography and interventional procedures were about 92, 7, 1 and 1 %, respectively. From 2000, the frequencies (number of examinations per 1000 inhabitants) of plain radiography and contrast-enhanced radiography have decreased about 8 and 33 %, respectively, while the frequencies of CT and interventional radiology have increased about 28 and 38 %, respectively. The population dose from all x-ray examinations is about 0,43 mSv per person (in 1997 0,5 mSv).
    [Show full text]
  • Nuclear Radiation 1. an Atom Contains Electrons, Protons and Neutrons
    Nuclear Radiation 1. An atom contains electrons, protons and neutrons. Which of these particles a) are outside the nucleus b) are uncharged c) have a negative charge d) are nucleons e) are much lighter than the others? 2. Complete the table below. Name Symbol Charge What is it? Alpha particle β -1 Gamma ray An electromagnetic wave 3. How is an ionised material different from a material that is not ionised? National 5 Physics: Waves & Radiation 1 Absorption of Radiation 1. The figure below shows a Geiger tube used to detect radiation from a radioactive source. thick lead plate 0 4 2 5 start counter stop ON OFF reset Geiger tube radioactive source The following measurements were made using the apparatus above. Counts in 300 seconds Readings Average 1 No source present 102 94 110 2 Source present at fixed distance from tube a) No lead plate present 3466 3420 3410 b) Thick lead plate present 105 109 89 c) Aluminium sheet in place of the 1834 1787 1818 thick lead sheet a) Complete the table by calculating the average readings. b) Why are the readings on each line not the same? c) What can you say from the table about the effect on the radiation of: i. The lead plate? ii. The aluminium plate? d) Why is it possible to say from the readings that: i. gamma radiation is emitted by the source? ii. alpha and beta radiation might be emitted by the source? e) What further tests could you make using this arrangement to find out whether or not the source emits alpha radiation? National 5 Physics: Waves & Radiation 2 2.
    [Show full text]
  • THE COLLECTIVE EFFECTIVE DOSE RESULTING from RADIATION EMITTED DURING the FIRST WEEKS of the FUKUSHIMA DAIICHI NUCLEAR ACCIDENT Matthew Mckinzie, Ph.D
    THE COLLECTIVE EFFECTIVE DOSE RESULTING FROM RADIATION EMITTED DURING THE FIRST WEEKS OF THE FUKUSHIMA DAIICHI NUCLEAR ACCIDENT Matthew McKinzie, Ph.D. and Thomas B. Cochran, Ph.D., Natural Resources Defense Council April 10, 2011 The Magnitude 9.0 earthquake off Japan’s Pacific Coast, which was the initiating event for accidents at four of the six reactors at the Fukushima Daiichi nuclear power plant, occurred at 14:46 local time on March 11th. At 15:41 a tsunami hit the plant and a station blackout ensued. A reconstruction of the accident progression by Areva1 posited that the final option for cooling the reactors – the reactor core isolation pumps – failed just hours later in Unit 1 (at 16:36), failed in the early morning of March 13th in Unit 3 (at 02:44), and failed early in the afternoon of March 14th in Unit 2 (at 13:25). Radiological releases spiked beginning on March 15th and in the Areva analysis are attributed to the venting of the reactor pressure vessels, explosion in Unit 2, and – significantly – explosion and fire in Unit 4. Fuel had been discharged from the Unit 4 reactor core to the adjacent spent fuel pool on November 30, 2010, raising the possibility of a core melt “on fresh air.” The Japanese Ministry of Education, Culture, Sports, Science and Technology (MEXT) has posted hourly dose rates by prefecture2 on its website. We do not currently know the geographic coordinates of these radiation monitoring sites. The English language versions of the hourly dose rate measurements by prefecture begin in table form at 17:00 on March 16th, and hourly dose rates are provided as charts3 beginning at 00:00 on March 14th.
    [Show full text]
  • Copyright by Arthur Bryan Crawford 2004
    Copyright by Arthur Bryan Crawford 2004 The Dissertation Committee for Arthur Bryan Crawford Certifies that this is the approved version of the following dissertation: Evaluation of the Impact of Non -Uniform Neutron Radiation Fields on the Do se Received by Glove Box Radiation Workers Committee: Steven Biegalski, Supervisor Sheldon Landsberger John Howell Ofodike Ezekoye Sukesh Aghara Evaluation of the Impact of Non -Uniform Neutron Radiation Fields on the Dose Received by Glove Box Radiation Workers by Arthur Bryan Crawford, B.S., M.S. Dissertation Presented to the Faculty of the Graduate School of The University of Texas at Austin in Partial Fulfillment of the Requirements for the Degree of Doctor of Philosophy The University of Texas at Austin December, 2004 Dedication I was born to goodly parents Harvey E. Crawford and Johnnie Lee Young Crawford Acknowledgements I would like to express my gratitude to Dr. Sheldon Landsberger for his vision in starting a distance learning program at the University of Texas at Austin and for his support and encouragement on this quest. I would like to thank my advisor, Dr. Steven Biegalski, for his support and encouragement even though the topic area was new to him. I would like to thank the members of my dissertation committee for finding the time to review this dissertation. To the staff of the Nuclear Engineering Teaching Laboratory I say thank you for your kindness and support during those brief times that I was on cam pus. A special thanks to my past and present group leaders, David Seidel, Eric McNamara, and Bill Eisele and my Division Leader, Lee McAtee, at Los Alamos National Laboratory, for their support in being allowed to use time and material resources at the Lab oratory and for financial support in the form of tuition reimbursement and travel expenses.
    [Show full text]
  • Individual and Collective Dose Limits and Radionuclide Release Limits
    UNITED STATES NUCLEAR REGULATORY COMMISSION ADVISORY COMMITTEE ON NUCLEAR WASTE WASHINGTON, D.C. 20555 April 29, 1991 r' Mr. Robert M. Bernero, Director Office of Nuclear Material Safety and Safeguards u.s. Nuclear Regulatory Commission Washington, DC 20555 Dear Mr. Bernero: SUBJECT: INDIVIDUAL AND COLLECTIVE DOSE LIMITS AND RADIONUCLIDE RELEASE LIMITS The Advisory Committee . on Nuclear waste has been developing comments, thoughts, and suggestions relative to individual and collective dose limits and radionuclide release limits. Since we understand that your staff is reviewing these same topics, we wanted to share our thoughts with you. In formulating these comments, we have had discussions with a number of people, including members of the NRC staff and Committee consultants. The Committee also had the benefit of the documents listed. Basic Definitions As a basic philosophy, individual dose limits are used to place restrictions on the risk to individual members of the public due to operations at a nuclear facility. If the limits have been properly established and compliance is observed, a regulatory agency can be confident that the associated risk to individual members of the pUblic is acceptable. Because the determination of the dose to individual members of the pUblic is difficult, the International Commission on Radiological Protection (ICRP) has developed the concept of the "critical group" and recommends that it be used in assessing doses resulting from environmental releases. As defined by the ICRP, a critical group is a relatively homogeneous group of people whose location and living habits are such that they receive the highest doses as a result of radio­ nuclide releases.
    [Show full text]
  • Industrial Radiography
    RADIATION PROTECTION OF WORKERS Industrial Radiography RADIATION AND RADIOGRAPHS RADIOACTIVE SOURCES PROCEDURES RADIOGRAPHERS DO follow the procedures. Ionizing radiation can pen- Materials of higher den Sealed sources are small þ Safe storage Precautions þ DO use the appropriate equipment, including collimators. in size and contain material etrate objects and create sity absorb more radiation. þ DO confi rm that there are no other people working in the images on photographic The metal components are which emits penetrating area of radiography. fi lm. The technique is revealed inside this tele radiation continuously. Radioactive sources should be kept in a secure, fi re þ DO use clear working signs and signals. called radiography and phone because they have Special containers made þ DO set up the controlled area and the necessary barriers. the processed fi lms are absorbed more radiation of dense metal shielding resistant and adequately shielded storage location þ DO confi rm the location of the source, or that X rays are called radiographs. than the surrounding plastic. are necessary to store, not being generated, by use of a survey meter. when not in use, and should move and manipulate these þ DO secure and store the source or X ray machine when sources. Due to their small be kept separate from other not in use. materials. The storage loca- size and manoeuvrability, Portable and mobile radiographic þ DO wear your personal dosimeter. sealed sources can be containers. ~ tion for X ray machines that used in confined spaces. are not in use is not required to be shielded. OTHER WORKERS Iridium-192 is a common radioactive source used þ DO observe the access restrictions, however remote it may in gamma radiography.
    [Show full text]
  • Radiation Basics
    Environmental Impact Statement for Remediation of Area IV \'- f Susana Field Laboratory .A . &at is radiation? Ra - -.. - -. - - . known as ionizing radiatios bScause it can produce charged.. particles (ions)..- in matter. .-- . 'I" . .. .. .. .- . - .- . -- . .-- - .. What is radioactivity? Radioactivity is produced by the process of radioactive atmi trying to become stable. Radiation is emitted in the process. In the United State! Radioactive radioactivity is measured in units of curies. Smaller fractions of the curie are the millicurie (111,000 curie), the microcurie (111,000,000 curie), and the picocurie (1/1,000,000 microcurie). Particle What is radioactive material? Radioactive material is any material containing unstable atoms that emit radiation. What are the four basic types of ionizing radiation? Aluminum Leadl Paper foil Concrete Adphaparticles-Alpha particles consist of two protons and two neutrons. They can travel only a few centimeters in air and can be stopped easily by a sheet of paper or by the skin's surface. Betaparticles-Beta articles are smaller and lighter than alpha particles and have the mass of a single electron. A high-energy beta particle can travel a few meters in the air. Beta particles can pass through a sheet of paper, but may be stopped by a thin sheet of aluminum foil or glass. Gamma rays-Gamma rays (and x-rays), unlike alpha or beta particles, are waves of pure energy. Gamma radiation is very penetrating and can travel several hundred feet in air. Gamma radiation requires a thick wall of concrete, lead, or steel to stop it. Neutrons-A neutron is an atomic particle that has about one-quarter the weight of an alpha particle.
    [Show full text]
  • Occupational Radiation Protection Record-Keeping and Reporting Guide
    DOE G 441.1-11 (formerly G-10 CFR 835/H1) 05-20-99 OCCUPATIONAL RADIATION PROTECTION RECORD-KEEPING AND REPORTING GUIDE for use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection Assistant Secretary for Environment, Safety and Health (THIS PAGE INTENTIONALLY LEFT BLANK) DOE G 441.1-11 i 05-20-99 CONTENTS CONTENTS PAGE 1. PURPOSE AND APPLICABILITY ........................................................ 1 2. DEFINITIONS ........................................................................ 2 3. DISCUSSION ........................................................................ 3 4. IMPLEMENTATION GUIDANCE ......................................................... 4 4.1 RECORDS TO BE GENERATED AND MAINTAINED ................................ 4 4.1.1 Individual Monitoring and Dose Records ........................................ 4 4.1.2 Monitoring and Workplace Records ............................................ 8 4.1.3 Administrative Records .................................................... 11 4.2 REPORTS ................................................................... 15 4.2.1 Reports to Individuals ...................................................... 16 4.2.2 Reports of Planned Special Exposures ......................................... 17 4.3 PRIVACY ACT CONSIDERATIONS .............................................. 17 4.3.1 Informing Individuals ...................................................... 17 4.3.2 Identifying Individuals ..................................................... 17
    [Show full text]
  • General Guidelines for the Estimation of Committed Effective Dose from Incorporation Monitoring Data
    Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaftt Wissenschaftliche Berichte FZKA 7243 General Guidelines for the Estimation of Committed Effective Dose from Incorporation Monitoring Data (Project IDEAS – EU Contract No. FIKR-CT2001-00160) H. Doerfel, A. Andrasi, M. Bailey, V. Berkovski, E. Blanchardon, C.-M. Castellani, C. Hurtgen, B. LeGuen, I. Malatova, J. Marsh, J. Stather Hauptabteilung Sicherheit August 2006 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft Wissenschaftliche Berichte FZKA 7243 GENERAL GUIDELINES FOR THE ESTIMATION OF COMMITTED EFFECTIVE DOSE FROM INCORPORATION MONITORING DATA (Project IDEAS – EU Contract No. FIKR-CT2001-00160) H. Doerfel, A. Andrasi 1, M. Bailey 2, V. Berkovski 3, E. Blanchardon 6, C.-M. Castellani 4, C. Hurtgen 5, B. LeGuen 7, I. Malatova 8, J. Marsh 2, J. Stather 2 Hauptabteilung Sicherheit 1 KFKI Atomic Energy Research Institute, Budapest, Hungary 2 Health Protection Agency, Radiation Protection Division, (formerly National Radiological Protection Board), Chilton, Didcot, United Kingdom 3 Radiation Protection Institute, Kiev, Ukraine 4 ENEA Institute for Radiation Protection, Bologna, Italy 5 Belgian Nuclear Research Centre, Mol, Belgium 7 Institut de Radioprotection et de Sûreté Nucléaire, Fontenay-aux-Roses, France 8 Electricité de France (EDF), Saint-Denis, France 9 National Radiation Protection Institute, Praha, Czech Republic Forschungszentrum Karlsruhe GmbH, Karlsruhe 2006 Für diesen Bericht behalten wir uns alle Rechte vor Forschungszentrum Karlsruhe GmbH Postfach 3640, 76021 Karlsruhe Mitglied der Hermann von Helmholtz-Gemeinschaft Deutscher Forschungszentren (HGF) ISSN 0947-8620 urn:nbn:de:0005-072434 IDEAS General Guidelines – June 2006 Abstract Doses from intakes of radionuclides cannot be measured but must be assessed from monitoring, such as whole body counting or urinary excretion measurements.
    [Show full text]