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CSA N288.1 : 2014

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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GUIDELINES FOR CALCULATING DERIVED RELEASE LIMITS FOR RADIOACTIVE MATERIAL IN AIRBORNE AND LIQUID EFFLUENTS FOR NORMAL OPERATION OF NUCLEAR FACILITIES

Available format(s)

Hardcopy , PDF

Superseded date

21-05-2019

Superseded by

CSA N288.1:14 (R2019)

Language(s)

French, English

Published date

01-01-2014

€1,624.15
Excluding VAT

Preface
0 Introduction
1 Scope
2 Reference publications
3 Definitions and abbreviations
4 Basic concepts
5 Environmental transfer model
6 Transfer parameters for airborne releases
7 Transfer parameters for releases to surface water
8 Application guides
Annexes
A - Default values of transfer parameters
B - Sample calculations
C - Dose coefficients
D - Selection of limiting radionuclides for mixed effluents
E - Half-lives and decay constants for the radionuclides
    considered in this Guideline
F - Hydrologic and aquatic transport models
G - Parameter values for terrestrial pathways models
H - The finite cloud model for air immersion dose
I - Equations for transfer factors for progeny in decay chains

Pertains to apply primarily to CANDU nuclear power stations in Canada.

DevelopmentNote
French Edition of GEN INS 1 17 issued on 01-06-2017. (07/2017)
DocumentType
Standard
Pages
408
PublisherName
Canadian Standards Association
Status
Superseded
SupersededBy
Supersedes

CSA N288.5 : 2011 : R2016 EFFLUENT MONITORING PROGRAMS AT CLASS 1 NUCLEAR FACILITIES AND URANIUM MINES AND MILLS
CSA N288.6 : 2012 ENVIRONMENTAL RISK ASSESSMENTS AT CLASS 1 NUCLEAR FACILITIES AND URANIUM MINES AND MILLS
CSA N288.4:2010 ENVIRONMENTAL MONITORING PROGRAMS AT CLASS 1 NUCLEAR FACILITIES AND URANIUM MINES AND MILLS
CSA N288.5 : 2011 EFFLUENT MONITORING PROGRAMS AT CLASS 1 NUCLEAR FACILITIES AND URANIUM MINES AND MILLS
N288.8-17 Establishing and implementing action levels for releases to the environment from nuclear facilities
CSA N290.0 & N290.2 PACKAGE : 2017 CONSISTS OF N290.0-17, GENERAL REQUIREMENTS FOR SAFETY SYSTEMS OF NUCLEAR POWER PLANTS AND N290.2-17, REQUIREMENTS FOR EMERGENCY CORE COOLING SYSTEMS OF NUCLEAR POWER PLANTS

CFR 40(PTS1-51) : JUL 96 PROTECTION OF ENVIRONMENT - ENVIRONMENTAL PROTECTION AGENCY

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