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22、for calculating theradiological consequences to thepublic of a release of airborneradioactive material for nuclearreactor accidentsN288.2-14N288.2-14Guidelines for calculating the radiological consequences to the publicof a release of airborne radioactive material for nuclearreactor accidentsDecembe
23、r 2014 2014 CSA Group 1ContentsTechnical Committee on Environmental Management 5Subcommittee on Radiation Doses From Releases of Radioactive Material Under AccidentConditions 8Preface 100 Introduction 120.1 Previous edition 120.2 Evolution of methodology 120.3 Industry review 130.4 New edition 131 S
24、cope 131.1 Type of consequence assessments 131.2 Facilities 141.3 Operating conditions 141.4 Time scale 141.5 Spatial scale 141.6 Meteorological sampling 141.7 Pathways 141.8 Contaminants 151.9 Receptors and end points 151.10 Exclusions 151.10.1 Routine releases during normal operation 151.10.2 Spil
25、ls and liquid releases 151.10.3 Urban dispersion 151.10.4 Fire and explosions 151.10.5 Hurricanes and tornados 151.10.6 Regional and global dispersion 151.10.7 Chemical contaminants 151.10.8 Ingestion pathway 161.10.9 Economic costs 161.10.10 Logistics of protective actions 161.10.11 Non-human biota
26、 161.11 Interpretation 161.12 Terminology 162 Reference publications 173 Definitions and abbreviations 313.1 Definitions 313.2 Abbreviations 354 Treatment of meteorology 374.1 Types of consequence calculations 374.2 General requirements 38N288.2-14Guidelines for calculating the radiological conseque
27、nces to the publicof a release of airborne radioactive material for nuclearreactor accidentsDecember 2014 2014 CSA Group 24.2.1 Deterministic calculations 384.2.2 Probabilistic calculations 404.3 Meteorological data requirements 404.3.1 Representativeness 404.3.2 Meteorological station data 414.4 St
28、ochastic sampling 454.5 Statistical quantities 464.6 Real-time and forecast weather data for emergency response 484.6.1 Sources of data 484.6.2 Meteorological data 484.6.3 Short-range dose assessment 494.6.4 Medium- and long-range dose assessment 494.6.5 Point of contact 494.6.6 Emergency response p
29、roducts 505 Source characterization 505.1 Source term 505.2 Source characteristics important for calculation of doses 505.2.1 Characteristics to be defined 505.2.2 Radiological characteristics 505.2.3 Physical characteristics 515.3 Acceptable methods to account for different release durations and ti
30、me dependence 525.3.1 Definitions 525.3.2 Instantaneous or short-term release 525.3.3 Prolonged or long-term release 525.3.4 Level of detail of source term representation 525.3.5 Number of release segments 535.4 Attributes required to allow the containment models to be coupled with the releasemodels
31、 535.4.1 Periodicity 535.4.2 Decay and ingrowth 545.5 Radionuclides to be considered 545.5.1 Selection of radionuclides 545.5.2 Justification 545.5.3 Unfiltered release 555.5.4 Filtered release 555.5.5 Tritium 565.6 Treatment of decay and daughter products 565.6.1 Accounting for decay and build-up 5
32、65.6.2 Precursors 565.6.3 Application of release fractions 565.7 Multiple point, area, or volume sources 575.7.1 Initial dimensions 575.7.2 Multiple release points 576 Modelling atmospheric dispersion 576.1 Model applicability 576.1.1 General requirements 576.1.2 Release characteristics 58N288.2-14G
33、uidelines for calculating the radiological consequences to the publicof a release of airborne radioactive material for nuclearreactor accidentsDecember 2014 2014 CSA Group 36.1.3 Meteorological conditions 586.1.4 Distance from source 586.1.5 Terrain 586.2 Atmospheric dispersion phenomena and model c
34、apabilities 596.2.1 Important phenomena and corresponding default model capabilities 596.2.2 Specialized model capabilities 596.3 Functional requirements for default models 606.3.1 Plume rise 606.3.2 Downwash 606.3.3 Entrainment 606.3.4 Effective release height 616.3.5 Plume broadening 616.3.6 Mixin
35、g height 616.3.7 Height of TIBL 626.3.8 Reflection at an elevated inversion 636.3.9 Fumigation 646.3.10 Plume transport 646.3.11 Plume diffusion 646.3.12 Wet deposition 646.3.13 Dry deposition 656.3.14 Plume depletion 656.4 Functional requirements for specialized models 666.4.1 General definition of
36、 conditions requiring specialized models 666.4.2 Complex terrain 666.4.3 Non-stationary conditions 666.4.4 Shoreline dispersion 676.4.5 Low wind speeds and calms 676.4.6 Fog effects 676.4.7 Resuspension and re-emission 676.4.8 Tritiated hydrogen gas (HT) 686.4.9 Multiple point, area, and volume sour
37、ces 686.5 Justification of the model choice 686.5.1 General requirements 686.5.2 Model validation 697 Calculation of consequences 697.1 Quantities 697.2 Receptors 707.3 Concentrations 707.4 Doses 717.4.1 General 717.4.2 Compliance with regulatory dose limits 717.4.3 Severe accident assessment 717.4.
38、4 Dose intervention levels and emergency reference levels 717.5 Pathways 727.6 Dose from external exposure to the cloud 727.6.1 Definition 727.6.2 Semi-infinite cloud approximation 727.6.3 Finite cloud effects 72N288.2-14Guidelines for calculating the radiological consequences to the publicof a rele
39、ase of airborne radioactive material for nuclearreactor accidentsDecember 2014 2014 CSA Group 47.6.4 Dose conversion factors for external exposure to the cloud 737.7 Dose from internal exposure to the cloud 737.7.1 Definition 737.7.2 Inhalation rates 737.7.3 Committed dose conversion factors for inh
40、alation 747.7.4 Period of integration 747.7.5 Chemical form of particulates 747.7.6 Noble gases 757.7.7 HTO absorption through skin 757.8 Dose from external exposure to ground deposition 757.8.1 Definition 757.8.2 Period of exposure 757.8.3 Dose conversion factors for external exposure to ground dep
41、osition 757.8.4 Surface roughness 767.9 Decay and daughter products 767.9.1 Dose calculations 767.9.2 Secular equilibrium 767.9.3 Decay-chain calculation 767.9.4 Ground contamination 767.10 Phases of exposure Definition 777.11 Shielding and filtration effects 777.11.1 Definition 777.11.2 Basis 777.1
42、1.3 Occupancy factors 777.11.4 Shielding factor 777.11.5 Filtration effect 787.12 Stochastic health effect calculation 787.13 Deterministic health effect calculation 797.13.1 Severe accident assessment 797.13.2 Detailed models 797.13.3 Simplified model 797.13.4 Calculation 797.14 Collective dose 807
43、.14.1 Definition 807.14.2 Limits of integration 808 Model uncertainties 808.1 Identification of sources of uncertainty 808.2 Use of uncertainty assessment 808.3 Uncertainty assessment 818.3.1 Documentation 818.3.2 Method 818.3.3 Sensitivity calculations 818.3.4 Quantitative uncertainty assessment 83
44、Annex A (informative) Meteorological data 86Annex B (informative) Dispersion phenomena and acceptable modelling approaches 102Annex C (informative) Classification of atmospheric dispersion models and their capabilities 127Annex D (informative) Deterministic health effects models 133N288.2-14Guidelin
45、es for calculating the radiological consequences to the publicof a release of airborne radioactive material for nuclearreactor accidentsDecember 2014 2014 CSA Group5Technical Committee on EnvironmentalManagementJ.R. Ryan CANDU Owners Group Inc.,Toronto, OntarioCategory: General InterestChairA. Rosaa
46、sen AREVA Resources Canada Inc.,Saskatoon, SaskatchewanCategory: Supplier/Fabricator/ContractorVice-ChairN. Ali Environment Canada,Toronto, OntarioAssociateP.J. Allsop Candu Energy Inc,Mississauga, OntarioAssociateI. Benovich Thornhill, OntarioCategory: General InterestD.B. Chambers SENES Consultant
47、s Limited,Richmond Hill, OntarioAssociateP.A. Davis Deep River, OntarioCategory: General InterestSecretaryJ. DeWilde Golder Associates Ltd.,Whitby, OntarioAssociateG.M. Dolinar Canadian Nuclear Laboratories,Chalk River, OntarioCategory: Owner/Operator/ProducerC. Elwood Bruce Power,Tiverton, OntarioC
48、ategory: Owner/Operator/ProducerK. England Cameco Corporation,Saskatoon, SaskatchewanAssociateN.C. Garisto ARCADIS SENES Canada Inc.,Richmond Hill, OntarioCategory: Supplier/Fabricator/ContractorN288.2-14Guidelines for calculating the radiological consequences to the publicof a release of airborne r
49、adioactive material for nuclearreactor accidentsDecember 2014 2014 CSA Group 6M. Gerchikov AMEC NSS,Toronto, OntarioAssociateM.G. Grey Candesco,Toronto, OntarioCategory: Service IndustryM. Hamlat Canadian Nuclear Safety Commission,Ottawa, OntarioCategory: Government and/or Regulatory AuthorityD.R. Hart EcoMetrix Incorporated,Mississauga, OntarioCategory: Supplier/Fabricator/ContractorT. Jarv Kinectrics Inc.,Toronto, OntarioCategory: Service IndustryF.J. Lemay International Safety Research,Ottawa, OntarioCategory: Service IndustryR. McCalla Ontario Power Ge
