Radiological impacts of spent nuclear fuel management options : a comparative study
- Bib ID:
- 598832
- Format:
- Book
- Author:
- OECD Nuclear Energy Agency. Ad Hoc Expert Group on Spent Fuel Management Options
- Online Access:
- http://new.sourceoecd.org/9264176578
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- Online Version:
- Table of contents
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- Description:
-
- Paris : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, c2000
- 124 p. : ill. ; 27 cm.
- ISBN:
- 9264176578
- Series:
- Radiation protection
- Full contents:
-
- Machine derived contents note: FOREW ORD 3
- EXECUTIVE SUM MARY 7
- 1. SCOPE OF THE STUDY 13
- 1.1 Background 13
- 1.2 Scope of the Study 13
- 2. THE PRINCIPLES OF RADIOLOGICAL PROTECTION 17
- 2.1 Introduction 17
- 2.2 ICRP Recommendations 17
- 2.3 National Regulatory Practices 20
- 2.4 The Environment 20
- 3. FUEL CYCLE FACILITIES AND RADIOACTIVE DISCHARGES 23
- 3.1 Uranium M ining and M illing 23
- 3.2 Conversion, Enrichm ent and Fuel Fabrication 25
- 3.3 Power Generation 29
- 3.4 Interim Storage and Conditioning of Spent Fuel 30
- 3.5 Reprocessing and Vitrification 32
- 3.6 Decommissioning and Dismantling of Nuclear Facilities 33
- 3.7 Disposal of Solid W aste 34
- 3.8 Transportation 35
- 4. DOSE ESTIM ATION FOR W ORKERS 37
- 4.1 Uranium M ining and M illing 37
- 4.2 Conversion, Enrichment and Fuel Fabrication 38
- 4.3 Power Generation 39
- 4.4 Interim Storage and Conditioning of Spent Fuel 40
- 4.5 Reprocessing and Vitrification 41
- 4.6 Decommissioning and Dismantling of Nuclear Facilities 42
- 4.7 Disposal of Solid W aste 42
- 4.8 Transportation 42
- 4.9 Summ ary of Results and Discussion 45
- 5. METHODOLOGY FOR GENERIC DOSE ASSESSMENT 47
- 5.1 Introduction 47
- 5.2 Radiological Indicators 47
- 5.3 Methodology for Estimating Doses to Members of the Public from Discharges 48
- 6. DOSE ESTIMATION FOR THE PUBLIC 51
- 6.1 Introduction 51
- 6.2 Uranium Mining and Milling 51
- 6.3 Conversion, Enrichment and Fuel Fabrication 53
- 6.4 Power Generation 53
- 6.5 Interim Storage and Conditioning 53
- 6.6 Reprocessing and Vitrification 54
- 6.7 Disposal of Solid Waste 55
- 6.8 Summary of Results and Discussion 56
- 7. CONCLUSIONS 61
- MEMBERS OF THE EXPERT GROUP 65
- BIBLIOGRAPHY 66
- Annex A - TECHNICAL SITE-SPECIFIC INFORMATION 69
- Annex B - GENERIC DOSE ASSESSMENT OF THE NUCLEAR FUEL CYCLE 93
- Annex C - GLOSSARY AND CONVERSION FACTORS 121.
- Notes:
-
- "This study was carried out by the Ad Hoc Expert Group on Spent Fuel Management Options under the NEA Committee on Radiation Protection and Public Health"--P. 3.
- Includes bibliographical references.
- Subject:
-
- Spent reactor fuels -- Management
- Nuclear fuels -- Management
- Ionizing radiation -- Health aspects
- Radioactive wastes -- Vitrification
- Ionizing radiation -- Dose-response relationship
- Nuclear energy -- Health aspects
- Radioactive wastes
- Radiation side effects
- Public health
- Occupational health and safety
- Statistics
- International comparisons
- Overseas item
- Other authors/contributors:
- OECD Nuclear Energy Agency
- Copyright:
-
In Copyright
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- Reason for copyright status:
- Until 2070 [Created/Published Date + 70 Years]
Copyright status was determined using the following information:
- Material type:
- Literary Dramatic Musical
- Published status:
- Published
- Publication date:
- 2000
Copyright status may not be correct if data in the record is incomplete or inaccurate. Other access conditions may also apply. For more information please see: Copyright in library collections.
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