Transcript 1.8 MB - eundetraf

RADIOACTIVE WASTE MANAGEMENT
(PART 4)
A RAHMAN
RWE NUKEM Ltd (UK)
1
Name, company and chapter
Process Flow
HAL
Calciner
Melter
Product
Container
2
Overview of Vitrification
Process
3
Calciner in vitrification cell
4
Glass granules to the lower end
of the calciner
5
Melter Crucible
6
Pour Cell
7
WVP
8
Vitrified Product Store (VPS)
Charge Face
9
Storage vs. Disposal
The IAEA defines disposal as:
‘The emplacement of waste in an
approved, specified facility (e.g.
near surface or deep geological
repository) without the intention
of retrieval’.
10
Storage and Disposal
Radioactive
waste
Interim
storage
Retrieval from
storage
Disposal
Storage
Treatment &
conditioning
11
Transportation
Transportation includes
•Packaging – design, fabrication and
maintenance
•Consignment – preparation, handling,
storage in transit and final receipt
12
IAEA Waste Packages
•
•
•
•
•
Excepted packages
Industrial packages
Type A packages
Type B packages
Type C packages
13
Nirex Standard Containers
Waste
Container
Typical Contents
4 m LLW Box
For LLW
2 m LLW Box
For LLW
Overall Dimensions
4013 mm x 2438 mm
plan x 2200 mm high
1960 mm x 2438 mm
plan x 2200 mm high
4 m Box
For large items–from 4013 mm x 2438 mm
decommissioning
plan x 2200 mm high
3 m3 Box
For large solid waste 1720 mm x 1720 mm
plan x1225 mm height
3 m3 Drum
For liquid and sludge 1720 mm diameter x
type wastes
1225 mm height
500 litre Drum For most operational 800 mm diameter x
ILW
1200 mm height
14
Gross
Mass (kg)
30,000
30,000
65,000
12,000
12,000
2,000
4 metre box for LLW (Nirex)
15
4 metre box for ILW
16
Prototype 3 m3 box during manufacture
17
Prototype 3 m3 box
18
3 m3 drum
19
3 m3 box inside RSTC285
20
Waste Disposal Objectives
• To protect human beings and the
environment
• To eliminate or reduce dose burden
and responsibilities to future
generations
21
Possible Disposal Facilities
• Near surface disposal
 Short lived LLW
• Deep geological disposal
 Long lived LLW
 Short or long lived ILW
 HLW after interim storage
22
Safety Considerations
• Pre-closure or operational safety –
similar to operational nuclear
facilities
• Post-closure safety – risk based over
thousands of years
23
SAFETY DOCUMENTATION
Safety documentation covering design,
construction, commissioning,
operation and decommissioning
• Decommissioning Plan (DP)
• Decommissioning Safety Case (DSC)
• Post Decommissioning Report (PDR)
24