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Radiological protection

REGULATORY AGENCIES - CHEMICALPROCESS INDUSTRY] (Vol 21) International Commission on Radiological Protection... [Pg.517]

Electromagnetic Fields and the Risk of Cancer, Report of an Advisoy Group on Non-Ioni ng Radiation, documents of the National Radiological Protection Board, U.K., Vol. 3, Mar. 1992. [Pg.348]

Recommendations of the International Commission on Radiological Protection," International Commission on Radiological Protection, Pubhcation 26, Pergamon Press, Oxford, U.K., 1977. [Pg.247]

U.S. radiation protection guidelines are estabHshed by the National CouncH on Radiation Protection and Measurement (NCRP) and are based on the recommendations of the International Commission on Radiological Protection (ICRP). The National Research CouncH also sponsors a report from its advisory committee on the biological effects of ionizing radiations (20). [Pg.439]

The radiological hazard of tritium to operating personnel and the general population is controlled by limiting the rates of exposure and release of material. Maximum permissible concentrations (MPC) of radionucHdes were specified in 1959 by the International Commission on Radiological Protection (79). For purposes of control all tritium is assumed to be tritiated water, the most readily assimilated form. The MPC of tritium ia breathing air (continuous exposure for 40 h/wk) is specified as 185 kBq/mL (5 p.Ci/mL) and the MPC for tritium in drinking water is set at 3.7 GBq/mL (0.1 Ci/mL) (79). The maximum permitted body burden is 37 MBq (one millicurie). Whenever bioassay indicates this value has been exceeded, the individual is withdrawn from further work with tritium until the level of tritium is reduced. [Pg.16]

International Commission on Radiological Protection PubHcation 2, Report of Committee II on Permissible Dose for Internal Radiation, Pergamon press, Oxford, 1959. [Pg.17]

ICRP, (1966). Reommendation of the International Committee on Radiological Protection. Publication 9. Pergamon Press. [Pg.336]

In 1959 the International Commission on Radiological Protection (ICRP) recommended a "maximum permissible concentration of plutonium in water (MPCW) for unlimited public use" of 5x10 5 Ci/m3 ( xlO6 Bq/m3) (64). In 1979 ICRP introduced the concept of ALI ("annual limits of intake"). For 239Pu the value was set at 2xl06 Bq (or 0.9 mg) per year (35). Because man consumes about 0.5 m3 water/year, this ALI value corresponds to 4x106 Bq/m3 potable water. [Pg.290]

ICRP—See International Commission on Radiological Protection Impurity levels after electrorefining... [Pg.463]

The ICRP (1994b, 1995) developed a Human Respiratory Tract Model for Radiological Protection, which contains respiratory tract deposition and clearance compartmental models for inhalation exposure that may be applied to particulate aerosols of americium compounds. The ICRP (1986, 1989) has a biokinetic model for human oral exposure that applies to americium. The National Council on Radiation Protection and Measurement (NCRP) has also developed a respiratory tract model for inhaled radionuclides (NCRP 1997). At this time, the NCRP recommends the use of the ICRP model for calculating exposures for radiation workers and the general public. Readers interested in this topic are referred to NCRP Report No. 125 Deposition, Retention and Dosimetry of Inhaled Radioactive Substances (NCRP 1997). In the appendix to the report, NCRP provides the animal testing clearance data and equations fitting the data that supported the development of the human mode for americium. [Pg.76]

Human Respiratory Tract Model for Radiological Protection (ICRP 1994b)... [Pg.76]

ICRP. 1960. International Commission of Radiological Protection. Report of Committee II on permissible dose for internal radiation. Health Phys 3 146. [Pg.242]

ICRP. 1979. Limits for Intakes of Radionuclides by Workers. International Commission of Radiological Protection. ICRP Publication 30. New York Pergamon Press. [Pg.242]

ICRP. 1989. Age-dependent doses to members of the public from intake of radionuclides Part 1. International Commission on Radiological Protection. Oxford Pergamon Press, 67-68, 75-89. [Pg.242]

James AC. 1878. Lung deposition of sub-micron aerosols calculated as a function of age and breathing rate. In National Radiological Protection Board annual Research and Development Report. National Radiological Protection Board. Harwell, United Kingdom,71-75. [Pg.243]

National Radiological Protection Board. 1982. Gut uptake factors for plutonium, americium and curium. Hartwell, England National Radiological Protection Board. DE83702055. [Pg.252]

Priest ND, Birchall A. 1984. The calculation of bone doses from alpha-emitting bone surface seeking radionuclides for radiological protection purposes. Radiat Environ Biophys 23 149-153. [Pg.256]

ICRP. 1979. International Commission on Radiological Protection. Limits for intakes of radionuclides by workers. ICRP Publication 20. Vol. 3. No. 1-4. Oxford Pergamon Press. [Pg.313]

ICRP, Publication 66. Human respiratory tract model for radiological protection. Ann ICRP 24 1-3, 1994. [Pg.500]

National Radiological Protection Board, Chilton, Didcot, Oxfordshire 0X11 ORQ,... [Pg.110]

Further consideration is being given by the National Radiological Protection Board and the Department of the Environment to the need for standards in the UK and to the means of implementing them. A decision is likely to be made before the end of this year. [Pg.117]

ICRP International Commission on Radiological Protection, Principles for Limiting Exposure of the Public to Natural Sources of Radiation, Publication 39, Ann, of ICRP 14 1-8 (1984). [Pg.117]

The mean radon concentrations determined by the passive detectors are based on calibrations using NBS standard radium-226 solutions and also from participation in the OECD (Nuclear Energy Agency)/CEC radon dosimeter intercomparisons (Commission of the European Communities, 1986) held at the U.K. National Radiological Protection Board (NRPB). Recent calibrations of the new LR-115 based detectors, in terms of response to radon concentrations and F factors have been carried out at the NRPB, which assistance is greatly appreciated. For the etching and track counting procedures used the inner LR-115 piece in the detectors has a mean sensitivity of approximately 1.6 tracks cm 2 kBq l m hr l. [Pg.123]


See other pages where Radiological protection is mentioned: [Pg.36]    [Pg.308]    [Pg.328]    [Pg.20]    [Pg.151]    [Pg.463]    [Pg.251]    [Pg.563]    [Pg.563]    [Pg.100]    [Pg.117]    [Pg.124]   


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