| | Derivation of activity limits for the disposal of radioactive waste |
| | 0,83 | | MB | in near surface disposal facilities |
| | 150 | | stron |
| | 2493 | | ID | International Atomic Energy Agency |
| | 2004 | | rok |
| | CONTENTS |
| | 1. INTRODUCTION 1 |
| | 1.1. Background . 1 |
| | 1.2. Objective.. 2 |
| | 1.3. Scope.. 2 |
| | 1.4. Structure 3 |
| | 2. ACTIVITY LIMITS AND DISPOSAL SYSTEM SAFETY . 3 |
| | 3. RADIATION PROTECTION CRITERIA .. 5 |
| | 3.1. General.. 5 |
| | 3.2. Radiological protection during the operational period . 5 |
| | 3.3. Radiological protection in the long term . 6 |
| | 3.3.1. Objective. 6 |
| | 3.3.2. Criteria . 7 |
| | 3.4. Use of radiation protection criteria . 8 |
| | 4. APPROACH TO DERIVING ACTIVITY LIMITS 8 |
| | 4.1. General.. 8 |
| | 4.2. Assessment context.. 10 |
| | 4.3. Disposal system description. 12 |
| | 4.4. Scenario development and justification. 12 |
| | 4.5. Model formulation and implementation 13 |
| | 4.6. Derivation of activity limits. 14 |
| | 5. ILLUSTRATIVE APPLICATION OF THE APPROACH .. 15 |
| | 5.1. Assessment context.. 15 |
| | 5.1.1. Purpose . 15 |
| | 5.1.2. Radiological protection criteria 16 |
| | 5.1.3. Calculation end points .. 16 |
| | 5.1.4. Assessment philosophy. 16 |
| | 5.1.5. Time frames 16 |
| | 5.2. Disposal system description. 16 |
| | 5.2.1. Waste characteristics.. 16 |
| | 5.2.2. Engineered barrier characteristics 17 |
| | 5.2.3. Geosphere and biosphere characteristics . 20 |
| | 5.3. Scenario and model development - Operational period. 21 |
| | 5.3.1. Development of scenarios 21 |
| | 5.3.2. Identification of scenarios 22 |
| | 5.3.3. Selection of scenarios 25 |
| | 5.3.4. Model formulation and implementation .. 26 |
| | 5.4. Scenario and model development - Post-closure period 33 |
| | 5.4.1. Development of scenarios 33 |
| | 5.4.2. Identification of scenarios 33 |
| | 5.4.3. Selection of scenarios 35 |
| | 5.4.4. Model formulation and implementation .. 36 |
| | 5.5. Derivation of illustrative activity limits. 43 |
| | 5.5.1. Operational period .. 44 |
| | 5.5.2. Post-closure period . 46 |
| | 5.5.3. Combined operational and post-closure periods.. 63 |
| | 5.6. Treatment of uncertainties arising from the assessment 67 |
| | 6. GUIDANCE ON THE USE OF THE APPROACH AND THE DERIVED ILLUSTRATIVE ACTIVITY |
| | LIMITS 70 |
| | APPENDIX I: DISPOSAL SYSTEM DATA.. 73 |
| | APPENDIX II: MATHEMATICAL MODELS.. 78 |
| | APPENDIX III: SOURCE TERM AND HUMAN EXPOSURE DATA 114 |
| | APPENDIX IV: RADIONUCLIDE AND ELEMENT DEPENDENT DATA 128 |
| | APPENDIX V: COMPUTATIONAL TOOLS USED.. 139 |
| | REFERENCES. 143 |
| | CONTRIBUTORS TO DRAFTING AND REVIEW 145 |