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CSA - CAN/CSA-N288.1-M87

Guidelines for Calculating Derived Release Limits for Radioactive Material in Airborne and Liquid Effluents for Normal Operation of Nuclear Facilities

inactive
Organization: CSA
Publication Date: 1 January 1987
Status: inactive
Page Count: 73
scope:

General

This Standard applies to airborne and liquid effluents associated with the normal operation of CANDU Nuclear Power Plants.

It provides guidelines and a methodology for calculating the upper limits (the Derived Release Limits) for the rate of release of radionuclides discharged into the atmosphere and surface waters, based on limiting radiation exposures to members of the public.

Applicability to Other Nuclear Facilities

The range of radionuclides and environmental pathways considered is extensive enough to make the Standard applicable to releases associ ated with many other nuclear facilities such as research reactors, radioisotope-processing facilities, and some waste- processing facilities such as incinerators.

Limitations

Neither the list of radionuclides nor the environmental pathways included in this Standard are complete enough to cover releases from certain other sources, eg, uranium mine tailings and mills, fuel fabrication plants and refineries, in-ground waste storage facilities, and permanent geologic disposal facilities. For the types and conditions of releases of radionuclides in these facilities, a somewhat different methodology to that outlined in this Standard may apply.

Document History

January 1, 2020
Guidelines for modelling radionuclide environmental transport, fate, and exposure associated with the normal operation of nuclear facilities
Facilities These Guidelines and the CDG are intended to apply to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make these Guidelines...
January 1, 2020
Guidelines for modelling radionuclide environmental transport, fate, and exposure associated with the normal operation of nuclear facilities
Facilities These Guidelines and the CDG are intended to apply to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make these Guidelines...
January 1, 2020
Guidelines for modelling radionuclide environmental transport, fate, and exposure associated with the normal operation of nuclear facilities
Facilities These Guidelines and the CDG are intended to apply to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make these Guidelines...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities This Guideline and the CDG are intended to apply primarily to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make this Guideline...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities This Guideline and the CDG are intended to apply primarily to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make this Guideline...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities This Guideline and the CDG are intended to apply primarily to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make this Guideline...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
0 Introduction 0.1 Derived release limit (DRL) The DRL for a given radionuclide is the release rate that would cause an individual of the most highly exposed group to receive and be committed to a...
January 1, 2014
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities This Guideline and the CDG are intended to apply primarily to CANDU nuclear power stations in Canada. However, the radionuclides and environmental pathways addressed make this Guideline...
September 1, 2008
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities The previous edition of CSA N288.1 and the CDG were intended to apply primarily to CANDU nuclear power stations in Canada; this remains the focus of this Guideline. However, the...
September 1, 2008
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities The previous edition of CSA N288.1 and the CDG were intended to apply primarily to CANDU nuclear power stations in Canada; this remains the focus of this Guideline. However, the...
January 1, 2008
Guidelines for calculating derived release limits for radioactive material in airborne and liquid effluents for normal operation of nuclear facilities
Facilities The previous edition of CSA N288.1 and the CDG were intended to apply primarily to CANDU nuclear power stations in Canada; this remains the focus of this Guideline. However, the...
CAN/CSA-N288.1-M87
January 1, 1987
Guidelines for Calculating Derived Release Limits for Radioactive Material in Airborne and Liquid Effluents for Normal Operation of Nuclear Facilities
General This Standard applies to airborne and liquid effluents associated with the normal operation of CANDU Nuclear Power Plants. It provides guidelines and a methodology for calculating the upper...
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