Radiation protection guides

It is particularly interesting to evaluate the contribution of a major nuclear facility, such as the Savannah River Plant, to the radiation dose to the population. Inasmuch as Beaufort, S. C., receives its drinking water primarily from the Savannah River, the expected body burdens may be extrapolated from tritium concentrations of the river at Beaufort. As mentioned previously, the difference between the concentrations at Augusta, Ga., and Beaufort, S. C., may be attributed to the operation of the Savannah River Plant. The difference averages approximately 4 nCi/liter and corresponds to 0.8 mrem./a. This represents 0.5% of the radiation protection guide for an average dose to a suitable sample of the population. 

The Joint Committee heard testimony from witnesses whose scientific investigations and conclusions were similar to those of Harold Knapp. Charles W. Mays, a University of Utah nuclear physicist, estimated that Utah infants had received aimual doses of iodine 131 that exceeded Federal Radiation Council guidelines on several occasions between 1951 and 1962. He announced that since the population of Utah had "been exposed repeatedly in excess of present radiation protection guides," the state would take appropriate countermeasures in the future and "the AEC should not be surprised to receive bills for the cost of these measures." Eric Reiss, a professor of medicine at Washington University and spokesman for the Greater St. Louis Citizens Committee for Nuclear Information, criticized the AEC even more sharply. He contended that the agency had seriously underestimated fallout hazards firom its weapons tests and concluded that "in the period 1951-62, a number of local populations. . . scattered throughout the continental United States have been exposed to fallout so intense as to represent a medically unac-... 

J. Shapiro, Radiation Protection A. Guide for Scientists and Physicians, 2nd ed., Harvard University Press, Cambridge, Mass., 1981. 

MILLS, W.A., FLACK, D.S., ARSENAULT, F.J. and CONTI, E.F. (1988). A Compendium of Major United States Radiation Protection Standards and Guides Legal and Technical Facts, Oak Ridge Associated Universities Report ORAU 88/F-lll (Oak Ridge Associated Universities, Oak Ridge, Tennessee). 

Step 6. Review the procedure for safety concerns. Make a list of warnings and guides, safety devices such as gloves, eyeshields, and clothing, and radiation protection actions. 

The new Standards are intended to ensure the safety of all types of radiation sources and to complement engineering safety standards developed for large and complex radiation sources, such as nuclear reactors and radioactive waste management facilities. The Standards are not mandatory, but can serve as a practical guide to all those involved in radiation protection, taking into account local situations, resources, etc. 

Safety Series No. 101 Operational Radiation Protection A Guide to Optimization (1990). 

ACALA s Radioactive Material Handling Safety - Student Reference Guide. This reference guide outlines the basics of radiation and radiation protection. It focuses on radiation sources in U S. Army commodities. There is a CD version of the Guide. 

Radioactive waste is any waste material—gas, liquid, or solid—whose radioactivity exceeds certain limits. These limits have been established by governments or by local authorities, guided by the recommendations of the International Commission on Radiation Protection (ICRP). The ICRP recommendations define the maximum permissible concentration (MPC) for each individual radionuclide and for mixtures of radionuclides in water or air. The U.S. regulation defines such limiting concentration as the radioactivity concentration limit (C), which is the terminology used in this text, Values of C for selected actinides and long-lived fission products in water or air are given in App. D. 

Federal Radiation Council, Background Material for the Development of Radiation Protection Standards, Rep. No. 5 (1964) Background Material for the Development of Radiation Protection Standards Protective Action Guides for strontium 89, strontium 90 and caesium 137, Rep. No. 7 (1965). Both from U.S. Govt. Printing Office, Washington, DC. 

A Guide to Radiation Protection in the Use of X-Ray Optics Equipment, Science Reviews, Leeds, England, 1986. 

Shapiro, J., Radiation Protection, A Guide for Scientists and Physicians, 3rd ed.. Harvard Press, Cambridge, MA, 1990. 

After the text of this publication had been prepared, the IAEA issued Safety Standards Series No. RS-G-1.1, Occupational Radiation Protection, IAEA, Vienna (1999). This Safety Guide may provide additional guidance on the development and implementation of radiation protection programmes and the monitoring and assessing of radiation doses. 

NAS. Reliability Centered Maintenance Guide for Facilities and Collateral Equipment, February 2000. National Council on Radiation Protection. Report Number 48 Radiation protection for medical and allied health personnel. Washington, DC NCRP, 1976. 

Practical Guide to the Determination of Human Exposure to Radiofrequency Fields, NCRP Report No. 119. National Council on Radiation Protection and Measurements, 1993. 

In the context of this Safety Guide, which concerns the radiation protection of the public against both present and future exposure, the term long lived radionuclide is applied to radionuclides with half-lives of 30 years or more (e.g. Cs), in contrast to the usual terminology in waste safety, where this term is usually used for radionuchdes with half-lives of 1000 years or more. 

Environmental and source monitoring for purposes of radiation protection safety guide. — Vienna International Atomic Energy Agency, 2005. 

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