Decommissioning of nuclear facilities other than reactors:
Gespeichert in:
| Format: | Buch |
|---|---|
| Sprache: | English |
| Veröffentlicht: |
Vienna
IAEA
1998
|
| Schriftenreihe: | International Atomic Energy Agency: Technical reports series
386 |
| Schlagworte: | |
| Online-Zugang: | Inhaltsverzeichnis |
| Beschreibung: | 205 S. Ill. |
| ISBN: | 9201009984 |
Internformat
MARC
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| 245 | 1 | 0 | |a Decommissioning of nuclear facilities other than reactors |c International Atomic Energy Agency |
| 246 | 1 | 3 | |a STI DOC 010 386 |
| 264 | 1 | |a Vienna |b IAEA |c 1998 | |
| 300 | |a 205 S. |b Ill. | ||
| 336 | |b txt |2 rdacontent | ||
| 337 | |b n |2 rdamedia | ||
| 338 | |b nc |2 rdacarrier | ||
| 490 | 1 | |a International Atomic Energy Agency: Technical reports series |v 386 | |
| 650 | 4 | |a Nuclear facilities |x Decommissioning | |
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Datensatz im Suchindex
| _version_ | 1804126773275787264 |
|---|---|
| adam_text | CONTENTS
1.
INTRODUCTION
......................................... !
1.1.
Background
..........................................
I
1.2.
Objective
............................................ 2
1.3.
Scope
.............................................. 2
1.4.
Structure
............................................ 2
2.
OVERVIEW OF NON-REACTOR NUCLEAR FACILITIES
........ 3
2.1.
Decommissioning of non-reactor versus reactor facilities
....... 4
2.2.
Uranium conversion facilities
............................ 4
2.3.
Uranium enrichment facilities
............................ 6
2.4.
Fuel fabrication facilities
................................ 11
2.4.1.
Uranium oxide fuel fabrication
...................... 11
2.4.2.
Fabrication of fuel containing
plutonium
.............. 11
2.4.3.
Uranium Magnox fuel fabrication facilities
............. 15
2.4.4.
Other metallic fuel fabrication facilities
............... 17
2.5.
Reprocessing plants
................................... 19
2.6.
Waste treatment, conditioning and storage
................... 21
2.7.
Fuel storage facilities
.................................. 23
2.7.1.
Fuel ponds
..................................... 23
2.7.2.
Dry fuel storage facilities
.......................... 25
2.8.
Support and development facilities
........................ 27
3.
BASIC SAFETY AND RADIOLOGICAL PROTECTION
.......... 28
3.1.
Radiological protection
................................. 28
3.2.
Other hazards
........................................ 31
3.3.
Management of radioactive wastes and effluent discharges
...... 32
3.4.
Management of personnel
............................... 33
3.5.
Regulatory considerations
............................... 33
4.
DECOMMISSIONING STRATEGY AND PLANNING
............ 34
4.1.
The basic stages of decommissioning
...................... 34
4.2.
Selection of a strategy
.................................. 35
4.2.1.
National policy on decommissioning
................. 36
4.2.2.
Current and future safety of the facility
............... 36
4.2.3.
The existence of technical resources, specialist teams
and local support
................................ 37
4.2.4.
Waste management and storage
..................... 38
4.2.5.
Costs and financing
.............................. 38
4.2.6.
Social considerations
............................. 39
4.3.
Planning
............................................ 39
4.3.1.
Initial planning phase of decommissioning
............. 39
4.3.2.
Detailed planning
................................ 41
4.4.
Decommissioning costs
................................. 42
4.5.
Safeguards during the decommissioning process
.............. 45
5.
DECOMMISSIONING TECHNIQUES AND EQUIPMENT
......... 45
5.1.
General
............................................. 45
5.2.
Measurements
........................................ 46
5.2.1.
Characterization objectives
......................... 46
5.2.2.
Inventory measurement
............................ 48
5.2.3.
Measurements during dismantling
................... 49
5.2.4.
Radwaste characterization
.......................... 50
5.2.5.
Measurements for recycling, reuse and free release
....... 52
5.3.
Decontamination of systems and dismantled components
....... 53
5.3.1.
Objectives
...................................... 54
5.3.2.
Techniques
..................................... 54
5.3.3.
Conclusions
.................................... 58
5.4.
Dismantling, segmenting and packaging
.................... 59
5.4.1.
General considerations and objectives
................. 59
5.4.2.
Preparation of the work area
........................ 60
5.4.3.
Segmenting of materials and equipment
............... 61
5.4.4.
Packaging and transport
........................... 66
5.5.
Remote handling equipment
............................. 68
5.5.1.
Considering the use of remote handling equipment
....... 68
5.5.2.
Selecting remote handling equipment
................. 68
5.6.
Handling decommissioning waste
......................... 70
5.6.1.
Waste production during decommissioning operations
.... 70
5.6.2.
Minimization of waste arisings during decommissioning
operations
...................................... 74
5.6.3.
Waste treatment and conditioning
.................... 76
5.6.4.
Temporary storage
............................... 77
5.6.5.
Final disposal
................................... 77
5.7.
Decontamination of buildings and structures
................. 77
5.7.1.
Techniques
..................................... 79
5.7.1.1.
Concrete
................................ 74
5.7.1.2.
Structural
steel
...........................
ХО
5.7.1.3.
Other hazardous materials
...................
XI
5.7.2.
Monitoring and sentencing
......................... 82
5.7.3.
Removal from controlled area
....................... 82
5.7.4.
Demolition
..................................... 82
5.7.5.
Release tor various uses
........................... 83
5.8.
Protection techniques
.................................. 83
5.8.1.
Working area systems
............................. 83
5.8.2.
Personnel protection
.............................. 84
5.8.3.
Environmental protection
.......................... 85
6.
DESIGN AND OPERATIONAL FEATURES TO SIMPLIFY
DECOMMISSIONING
..................................... 86
6.1.
Design objectives
..................................... 86
6.2.
Planning for decommissioning during design and operation
..... 87
6.3.
Detailed features for decommissioning
..................... 87
6.3.1.
Remote maintenance
............................. 88
6.3.2.
Compartmentalization of process functions
............ 88
6.3.3.
Process cell liners
............................... 88
6.3.4.
Protective coatings
.............................. 88
6.3.5.
High level liquid waste storage
..................... 89
6.3.6.
Access to process equipment
...................... 89
6.3.7.
Built-in provisions for chemical decontamination
....... 90
6.3.8.
Capability to process low level wastes
............... 90
6.3.9.
Isolation of sections of the ventilation systems
......... 90
6.3.10.
Process equipment sizing
......................... 90
6.3.1 1.
Stainless steel liners in pipe trenches
................ 91
6.3.12.
Built-in capability for mechanical decontamination
...... 91
6.3.13.
Collocation of fuel cycle facilities
................... 91
7.
DECOMMISSIONING EXPERIENCE
......................... 91
7.1.
Uranium conversion, enrichment, recovery and fuel
fabrication facilities
.................................... 91
7.1.1.
Uranium conversion
.............................. 92
7.1.2.
Uranium enrichment
.............................. 93
7.1.3.
Uranium recovery
................................ 95
7.1.4.
Uranium fuel fabrication
........................... 97
7.2.
Mixed oxide
(МОХ)
and
plutonium
fuel facilities
............. 99
7.2.1.
United
Kingdom
................................. 99
7.2.2.
United States
of
America
...........................101
7.2.3.
France.........................................
104
7.2.4.
Canada
........................................104
7.2.5.
Belgium
.......................................104
7.2.6.
Japan
..........................................105
7.2.7.
Italy
...........................................105
7.3.
Spent fuel reprocessing facilities
..........................106
7.3.1.
Eurochemic reprocessing plant, Dessel, Belgium
......106
7.3.2.
Reprocessing facility AT-1, La Hague, France
.........108
7.3.3.
Pilot reprocessing facility,
Tokai
Mura,
Japan
.........109
7.3.4.
Trombay Plutonium Plant, India
...................114
7.3.5.
Reprocessing plant, Sellafield, UK
.................116
7.3.6.
West Valley Demonstration Project, USA
............119
7.3.7.
Reprocessing facility, Marcoule, France
.............120
7.3.8.
Reprocessing plant UP2
(Pu
finishing facility),
La Hague, France
..............................122
7.3.9.
Rooms
82
and
100
of
Pu
purification facility,
Marcoule, France
..............................123
7.3.10.
Reprocessing plant UP1 (fuel decladding
and dissolution facility), Marcoule, France
...........124
7.3.11.
WAK
prototype reprocessing facility,
Karlsruhe, Germany
............................125
7.3.12.
Pilot reprocessing facility, Dounreay, UK
............126
7.3.13.
Pilot reprocessing facility, Trisaia, Italy
..............127
7.3.14.
Pilot reprocessing plant, Saluggia, Italy
..............127
7.3.15.
Pilot uranium reprocessing plant, Kjeller, Norway
.....127
7.4.
Spent fuel storage, waste management and other facilities
.......130
7.4.1.
Hot cell facility, Ris0, Denmark
...................130
7.4.2.
Hot cells, Casaccia. Italy
.........................131
7.4.3.
Tunney s Pasture facility, Ottawa, Canada
............132
7.4.4.
Storage vessels at Eurochemic reprocessing plant,
Dessel, Belgium
...............................132
7.4.5.
Vitrification plant. Marcoule, France
................133
7.4.6.
UP2 sea discharge pipe. La Hague, France
...........133
7.4.7.
Nouvelle
Piscine La Hague (NPH) spent fuel
storage facility, France
..........................134
7.4.8.
Liquid waste treatment facility
(STEL),
Marcoule, France
..............................134
7.4.9.
Spent fuel storage facility, Sellafield, UK
............135
7.4.10.
Radium and polonium laboratory, Khlopin Radium
Institute. St. Petersburg, Russian Federation
..........135
8.
CONCLUSIONS
..........................................
I
37
APPENDIX I: SHUT DOWN NON-REACTOR NUCLEAR
FACILITIES
....................................139
APPENDIX II: DETAILED DATA FROM VARIOUS NON-REACTOR
NUCLEAR FACILITIES DECOMMISSIONING
PROJECTS
.....................................147
ANNEX: PROBLEMS ENCOUNTERED AND LESSONS LEARNED
FROM DECOMMISSIONING OF SELECTED
NON-REACTOR NUCLEAR FACILITIES
.................157
REFERENCES
................................................183
BIBLIOGRAPHY
..............................................198
GLOSSARY
.................................................201
CONTRIBUTORS TO DRAFTING AND REVIEW
....................205
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| indexdate | 2024-07-09T18:22:47Z |
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| isbn | 9201009984 |
| language | English |
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| physical | 205 S. Ill. |
| publishDate | 1998 |
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| publisher | IAEA |
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| series | International Atomic Energy Agency: Technical reports series |
| series2 | International Atomic Energy Agency: Technical reports series |
| spelling | Decommissioning of nuclear facilities other than reactors International Atomic Energy Agency STI DOC 010 386 Vienna IAEA 1998 205 S. Ill. txt rdacontent n rdamedia nc rdacarrier International Atomic Energy Agency: Technical reports series 386 Nuclear facilities Decommissioning Kerntechnische Anlage (DE-588)4135481-3 gnd rswk-swf Stilllegung (DE-588)4125246-9 gnd rswk-swf (DE-588)1071861417 Konferenzschrift gnd-content Kerntechnische Anlage (DE-588)4135481-3 s Stilllegung (DE-588)4125246-9 s DE-604 International Atomic Energy Agency: Technical reports series 386 (DE-604)BV000022590 386 Digitalisierung TU Muenchen application/pdf http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=008238741&sequence=000002&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA Inhaltsverzeichnis |
| spellingShingle | Decommissioning of nuclear facilities other than reactors International Atomic Energy Agency: Technical reports series Nuclear facilities Decommissioning Kerntechnische Anlage (DE-588)4135481-3 gnd Stilllegung (DE-588)4125246-9 gnd |
| subject_GND | (DE-588)4135481-3 (DE-588)4125246-9 (DE-588)1071861417 |
| title | Decommissioning of nuclear facilities other than reactors |
| title_alt | STI DOC 010 386 |
| title_auth | Decommissioning of nuclear facilities other than reactors |
| title_exact_search | Decommissioning of nuclear facilities other than reactors |
| title_full | Decommissioning of nuclear facilities other than reactors International Atomic Energy Agency |
| title_fullStr | Decommissioning of nuclear facilities other than reactors International Atomic Energy Agency |
| title_full_unstemmed | Decommissioning of nuclear facilities other than reactors International Atomic Energy Agency |
| title_short | Decommissioning of nuclear facilities other than reactors |
| title_sort | decommissioning of nuclear facilities other than reactors |
| topic | Nuclear facilities Decommissioning Kerntechnische Anlage (DE-588)4135481-3 gnd Stilllegung (DE-588)4125246-9 gnd |
| topic_facet | Nuclear facilities Decommissioning Kerntechnische Anlage Stilllegung Konferenzschrift |
| url | http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=008238741&sequence=000002&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA |
| volume_link | (DE-604)BV000022590 |