Odpady jądrowe – globalny raport Focus Europe

Page 97

WNWR 2019  — 7. COUNTRY STUDIES

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QUANTITIES OF WASTE ANDRA publishes an inventory of nuclear materials and waste every three years. The last comprehensive inventory was published in 2018, providing data for the end of 2016. A summary update published in 2019 provides data for the end of 2017 for some categories. As of December 2017, ANDRA estimated 3,740 m³ of high-level waste (HLW), 42,800 m³ of intermediate-level long-lived waste (ILW-LL), 93,600 m³ of low-level long-lived waste (LLW-LL), 938,000 m³ of lowand intermediate-level short-lived waste (LILW-SL), and 537,000 m³ of very low-level waste (VLLW). In addition, 1,770 m³ of waste was not included in any category. Detailed information is provided in Table 11. Data provided by ANDRA include foreign waste when it is stored on French territory. This mostly relates to spent fuel reprocessing contracts with foreign customers. Solid wastes stemming from that processing has to be returned to the countries of origin, since French law forbids the disposal of nuclear waste of foreign origin on the national territory. However, substitution occurs between different types of waste so as to minimize the volumes to be shipped. The substitution can also circumvent problematic waste forms (e.g. bituminized intermediate-level waste) that have not been accepted by foreign reprocessing customers. Moreover, past and current activities related to nuclear materials of foreign origin have generated waste (e.g. unirradiated breeder fuel), and “reusable materials” (e.g. reprocessed uranium) with no actual use that are now accounted for as French. HLW almost entirely arises from spent fuel reprocessing. As of the end of 2018, more than 34,000 tHM of French and foreign fuel have been reprocessed at La Hague. Most of the resultant HLW, at least 95 percent, is conditioned as vitrified waste packages. A small fraction is stored for cooling in tanks, while awaiting vitrification. For ILW-LL, the situation is quite heterogeneous: some waste is conditioned for final disposal, while some is pre-conditioned or even raw. This waste can be cemented in metal drums, in sludges or other raw forms, bituminized, vitrified or concreted. However, some old packages or sludges need characterization before reconditioning. A large quantity of bituminized, inflammable waste packages represent a particular reconditioning challenge.


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Articles inside

Quantities of waste

2hr
pages 97-148

Summary

1min
page 94

Costs and financing

2min
page 93

Waste management policies and facilities

2min
page 92

Financing schemes for interim storage

2min
page 84

Integrated financing schemes

2min
page 87

6.4 Summary

5min
pages 88-89

Financing schemes for disposal

6min
pages 85-86

Quantities of waste

2min
page 91

Decommissioning costs

6min
pages 80-81

Accumulation of the funds

3min
page 78

Overview and nature of the funds

2min
page 77

5.5 Summary

2min
page 75

Extended storage

4min
pages 73-74

Deep borehole disposal

3min
page 70

LILW-repositories

3min
page 67

Host rocks

2min
page 66

5.1 Historical background

16min
pages 58-62

5.2 The context of nuclear waste management

5min
pages 63-64

4.7 Summary

2min
page 57

4.5 Risks from the reprocessing of spent nuclear fuel

5min
pages 53-54

Risks to nuclear workers

3min
page 51

Uranium mine tailings

3min
page 49

Health risks from exposures to uranium

3min
page 47

4.1 Radiation risks of nuclear waste

2min
page 45

Uranium mining

3min
page 48

4.2 Risks from uranium mining, mine tailings, enrichment, and fuel fabrication

2min
page 46

3.4 Summary

4min
pages 43-44

Decommissioning waste

2min
page 34

Uranium mining, milling, processing and fuel fabrication

1min
page 22

Executive summary

28min
pages 11-20

Operational waste

2min
page 32

2.4 Summary

2min
page 30

2.3.1 The IAEA classification

5min
pages 25-26

2.1 Types of waste: the nuclear fuel chain

2min
page 21

Foreword

5min
pages 3-4

Key Insights

2min
pages 9-10
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