Radiological impacts of spent nuclear fuel management options : a comparative study.

Author/creator OECD Nuclear Energy Agency
Format Book
Publication InfoParis : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, ©2000.
Description124 pages : illustrations ; 27 cm.
Supplemental ContentTable of contents
Supplemental Contenthttp://new.sourceoecd.org/9264176578
Supplemental ContentFull Text
Subjects

SeriesRadiation protection
Radiation protection (OECD Nuclear Energy Agency) ^A476326
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.
General note"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"--Page 3.
Bibliography noteIncludes bibliographical references.
Other formsAlso issued online.
LanguageIssued also in French under title: Les incidences radiologiques des options de gestion du combustible nucléaire usé : une étude comparative.
Issued in other formOnline version: OECD Nuclear Energy Agency. Ad Hoc Expert Group on Spent Fuel Management Options. Radiological impacts of spent nuclear fuel management options. Paris : Nuclear Energy Agency, Organisation for Economic Co-operation and Development, ©2000
LCCN 00398482
ISBN9264176578
ISBN9789264176577

Availability

Library Location Call Number Status Item Actions
Joyner General Stacks TK9360 .O734 2000 ✔ Available Place Hold