Considerations for waste minimization at the design stage of nuclear facilities (Vienna, 2007). - ОГЛАВЛЕНИЕ / CONTENTS
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ОбложкаConsiderations for waste minimization at the design stage of nuclear facilities. - Vienna: International Atomic Energy Agency, 2007. - 143 p. - (Technical Reports Series; N 460). - ISBN: 978-92-0-105407-4
 

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Оглавление / Contents
 
SUMMARY ......................................................... 1

1. INTRODUCTION ................................................. 3
   1.1. Background .............................................. 3
   1.2. Objective ............................................... 4
   1.3. Scope ................................................... 5
   1.4. Structure ............................................... 5

2. TYPES AND QUANTITIES OF WASTE GENERATED DURING FACILITY
   OPERATION AND DECOMMISSIONING ................................ 6
   2.1. Introduction ............................................ 6
   2.2. Generation of low and intermediate level radioactive
        waste in nuclear facilities ............................ 10
        2.2.1. Waste generation from nuclear fuel facilities ... 10
        2.2.2. Waste generation from operation of nuclear
               power plants .................................... 14
        2.2.3. Waste from spent fuel reprocessing .............. 19
        2.2.4. Waste from decontamination and decommissioning
               of nuclear facilities ........................... 21
        2.2.5. Waste from institutional and industrial
               facilities, including research laboratories ..... 26
   2.3. Mixed waste streams .................................... 28

3. METHODOLOGIES FOR WASTE MINIMIZATION ........................ 29
   3.1.	Objectives of waste minimization ....................... 29
   3.2.	Waste minimization options ............................. 29
        3.2.1. Control of radioactive waste generation ......... 30
        3.2.2. Prevention of activation/contamination .......... 31
        3.2.3. Reuse and recycling of materials ................ 32
        3.2.4. Reduction of radioactive waste volumes .......... 32

4. DESIGN OPTION CONSIDERATIONS FOR WASTE MINIMIZATION ......... 35
   4.1. Introduction ........................................... 35
   4.2.	Considerations for minimizing contamination problems ... 37
        4.2.1. Building and equipment layout ................... 38
        4.2.2. Selection of components ......................... 44
        4.2.3. Reducing surface contamination .................. 49
        4.2.4. Reducing leakage and crud traps ................. 53
        4.2.5. Quality control ................................. 53
        4.2.6. Limiting corrosion .............................. 54
        4.2.7. Minimizing the spread of contamination .......... 54
   4.3. Provisions to facilitate decontamination ............... 55
   4.4. Provisions to facilitate dismantling and
        segmentation ........................................... 57
        4.4.1. Minimum use of hazardous materials .............. 57
        4.4.2. Additional plant layout requirements to
               facilitate dismantling .......................... 57
        4.4.3. Preplacement of dismantling aids ................ 58
        4.4.4. Shielding ....................................... 59
        4.4.5. Connectors ...................................... 61
        4.4.6. Intact removal of large components .............. 61
        4.4.7. Documentation ................................... 63
        4.4.8. Planning ........................................ 66
   4.5. Development and improvement of techniques for
        decontamination and decommissioning .................... 67
        4.5.1. Development and improvement of decontamination
               techniques ...................................... 67
        4.5.2. Development and improvement of dismantling
               techniques ...................................... 69
        4.5.3. Development and improvement of measurement
               techniques ...................................... 71
        4.5.4. Developments to simplify waste management ....... 73
        4.5.5. Design for safe enclosure and deferred
               dismantling ..................................... 79
   4.6. Development and improvement of the regulatory
        approach ............................................... 82
   4.7. Nuclear facility design basis guidelines for waste
        minimization ........................................... 83

5. CONCLUSIONS ................................................. 90

REFERENCES ..................................................... 95
ANNEX ......................................................... 103
GLOSSARY ...................................................... 141
CONTRIBUTORS TO DRAFTING AND REVIEW ........................... 143


 
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