| | Safety aspects of nuclear plants coupled with seawater |
| | 2,17 | | MB | desalination units |
| | 88 | | stron |
| | 4688 | | ID | International Atomic Energy Agency |
| | 2001 | | rok |
| | CONTENTS |
| | 1. INTRODUCTION.1 |
| | 1.1. Nuclear desalination and other heat utilization applications 1 |
| | 1.2. Desalination processes1 |
| | 1.3. Reactors for desalination applications2 |
| | 1.4. Safety and licensing considerations2 |
| | 2. SAFETY STANDARDS AND THEIR APPLICABILITY TO NUCLEAR DESALINATION AND |
| | OTHER HEAT UTILIZATION APPLICATIONS .3 |
| | 2.1. Existing IAEA safety standards .3 |
| | 2.1.1. Safety Fundamentals 3 |
| | 2.1.2. Safety Requirements 4 |
| | 2.1.3. Safety Guides .5 |
| | 2.2. Concerns arising from the use of existing IAEA safety standards5 |
| | 2.3. Specific requirements applicable to nuclear desalination and other heat utilization applications .6 |
| | |
| | 3. SAFETY CONSIDERATIONS SPECIFIC TO NUCLEAR DESALINATION (AND OTHER HEAT |
| | UTILIZATION APPLICATIONS).6 |
| | 3.1. Coupling.7 |
| | 3.1.1. Thermal coupling to distillation systems (MED or MSF) .7 |
| | 3.1.2. Thermal coupling to distillation systems from a heat-only reactor10 |
| | 3.1.3. Electrical and thermal coupling to an RO preheat system .10 |
| | 3.1.4. Electrical only coupling to a contiguous RO system .11 |
| | 3.1.5. Coupling nuclear power plants to hybrid desalination systems .11 |
| | 3.1.6. Carry-over of radioactive material into the product water .13 |
| | 3.1.7. Sharing of resources.13 |
| | 3.1.8. Brine discharge.13 |
| | 3.2. Transients .13 |
| | 3.2.1. Accident scenarios .13 |
| | 3.2.2. Operational transients 14 |
| | 3.3. Water quality and monitoring 15 |
| | 3.4. Availability of product water .16 |
| | 3.5. Siting and the proximity of population centres 16 |
| | 3.6. Licensing 17 |
| | 4. A SYSTEMATIC APPROACH TO THE IDENTIFICATION OF COMPREHENSIVE |
| | REQUIREMENTS APPLICABLE TO A SPECIFIC NUCLEAR INSTALLATION.18 |
| | 4.1. The hierarchical, or “top-down” approach.18 |
| | 4.2. Guidelines for implementing a hierarchical, top-down approach to the systematic identification |
| | of a comprehensive set of safety requirements 19 |
| | 4.2.1. The hierarchical, top-down approach as an iterative process.19 |
| | 4.2.2. Preliminary selection of technologies for the nuclear desalination installation .22 |
| | 4.2.3. Review of the proposed design in relation to Safety Fundamentals for nuclear power plants22 |
| | |
| | 4.2.4. Review of the proposed design in relation to Safety Requirements for nuclear power plants |
| | .22 |
| | 4.2.5. Project specific safety design and licensing basis requirements 23 |
| | 4.2.6. Exercise of application of the top-down methodology for the preparation of the Safety |
| | Requirements.23 |
| | 5. CONCLUSIONS .24 |
| | REFERENCES .25 |
| | ANNEX 1: EXAMPLE OF THE APPLICATION OF THE GENERAL METHODOLOGY FOR THE |
| | IDENTIFICATION OF COMPREHENSIVE REQUIREMENTS APPLICABLE TO THE DESIGN OF |
| | SPECIFIC NUCLEAR PLANTS27 |
| | ANNEX II: POSSIBLE PROCEDURE FOR THE DEFINITION OF TARGET WATER |
| | RADIOACTIVITY CONTENT63 |
| | ANNEX III: PREVENTION OF THE RADIOACTIVE CONTAMINATION OF PRODUCT WATER.64 |
| | ANNEX IV: AN ASSESSMENT OF PUBLIC EXPOSURES FROM NORMAL OPERATION OF THE |
| | CANDESAL® NUCLEAR DESALINATION FACILITY.66 |
| | ANNEX V: SAFETY ASPECTS OF THE DESALINATION OF SEA WATER USING NUCLEAR |
| | ENERGY69 |
| | CONTRIBUTORS TO DRAFTING AND REVIEW ..81 |