Review of innovative technologies of radioactive waste ... · PDF fileReview of innovative...
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International Atomic Energy Agency
Bergen, Norway, 15 and 16 May 2014
Review of innovative technologies
of radioactive waste treatment Michael I. Ojovan
Waste Technology Section, Department of Nuclear Energy,
IAEA
CEG Workshop on topical issues of legacy RW and SNF management
in North West and Far East Russia,
International Atomic Energy Agency 2
Contents
I. Background
II. Gaseous
radioactive waste
III. Aqueous
radioactive waste
IV. Solid radioactive
waste
V. Problematic
waste: i-graphite
and DSRS
VI. Conclusions
VII. Scientific Forum
International Atomic Energy Agency 3
It is important for Member States to adopt a mix of radioactive
waste processing technologies which is optimally suited to the
country-specific types and quantities of wastes generated.
Background
Treatment = Operations
intended to benefit safety
and/or economy by changing
the characteristics of the waste.
Three basic treatment
objectives are:
(i) volume reduction,
(ii) removal of radionuclides
from the waste and
(iii) change of composition.
Treatment may result in an
appropriate waste form.
Waste
Generation
Any or all of the operations
prior to waste treatment
such as:
-Collection
-Characterisation
-Segregation
-Adjustment
-Decontamination
Reuse,
recyclingVolume reduction, removal
of radionuclides, changes
in composition
Solidification, embedding,
encapsulation followed by
packaging
Placement of waste in
nuclear facility where
human control and
retrievability are ensured
Storage for decay
Environment or landfill
depending on the physical
form of waste
Transfer of waste
packages
Near surface
repository
Deep
underground
repository
Pretreatment
Treatment
Conditioning
Interim storage
Transport
Disposal
Short-lived waste
(< 30 years)
Long-lived waste
(> 30 years)
Emplacement of waste in a
licensed facility without
intention of retrieval
Transportation to a
centralised storage
facility may be involved
Radioactive
waste
Transportation to a
centralised storage
facility may be involved
Cleared
waste
Candidate for
clearance
Radioactive waste management
Predisposal Disposal
Waste
Generation
Any or all of the operations
prior to waste treatment
such as:
-Collection
-Characterisation
-Segregation
-Adjustment
-Decontamination
Reuse,
recyclingVolume reduction, removal
of radionuclides, changes
in composition
Solidification, embedding,
encapsulation followed by
packaging
Placement of waste in
nuclear facility where
human control and
retrievability are ensured
Storage for decay
Environment or landfill
depending on the physical
form of waste
Transfer of waste
packages
Near surface
repository
Deep
underground
repository
Pretreatment
Treatment
Conditioning
Interim storage
Transport
Disposal
Short-lived waste
(< 30 years)
Long-lived waste
(> 30 years)
Emplacement of waste in a
licensed facility without
intention of retrieval
Transportation to a
centralised storage
facility may be involved
Radioactive
waste
Transportation to a
centralised storage
facility may be involved
Cleared
waste
Candidate for
clearance
Radioactive waste management
Predisposal Disposal
International Atomic Energy Agency
Main WTS Activities
Technical Publications;
Coordinated Research Projects;
International Peer Review Services.
WTS Networks: o International Decommissioning Network (IDN),
o Network for Environmental Management and
Remediation (ENVIRONET),
o Network for Underground Research
Laboratories for Geological Disposal of HLW
(URF),
o Near-surface Disposal Network (DISPONET),
o Waste Characterization Network (LABONET),
o CONNECT - Connecting the Network of
Networks for Enhanced Communications and
Training in RWM, D&ER.
o We investigate the feasibility of a new network
for radioactive waste predisposal management
– IMMONET
4
http://nucleus.iaea.org/sites/CONNECT/Pages/default.aspx
International Atomic Energy Agency 5
http://nucleus.iaea.org/sites/nefw-projects/IMMONET/SitePages/Home.aspx
International Atomic Energy Agency
WA
TE
C-2
014
, 1-4
.04.2
014
WATEC strongly recommends
that the IAEA ensure long-term
sustainability of the networks …. http://www.iaea.org/OurWork/ST/NE/NEFW/Technical_Areas/WTS/WATEC.html
6
International Radioactive Waste Technical Committee (WATEC)
International Atomic Energy Agency
Co
ord
inate
d R
ese
arc
h P
roje
cts
CRP on Planning, Management and
Organizational Aspects in Decommissioning of
Nuclear Facilities (2009-2011), IAEA-TECDOC-
1712 published in 2013;
CRP on Innovative and Adaptive Technologies
in Decommissioning of Nuclear Facilities (2004-
2008), IAEA-TECDOC-1602 published in 2008;
Performance and Behaviour of Cementitious
Materials in Long Term Storage and
Disposal of Radioactive Waste (2007-2010),
IAEA-TECDOC-1701 published in 2013;
Treatment of Irradiated Graphite to Meet
Waste Acceptance Criteria for Disposal
(2011-2013);
Processing Technologies for High Level
Waste, Formulation of Matrices and
Characterization of Waste Forms (2013-
2015).
7
International Atomic Energy Agency
Pe
er
Re
vie
ws
International Peer Review of UK Magnox
Decommissioning Programme (2008-2011)
– final report handed over to Magnox
representatives at the IAEA in February 2012.
Korea: Geological disposal programme with
emphasis on suitability for pyro- processed waste
(2012);
UK, NDA: Peer Review of Interim Storage of Higher
Activity Waste Packages-Industry Guidance (2012);
Russia: International Peer Review on the application
of international safety standards to the liquid RWM
practices in the Russian Federation (2013);
The Follow-up International Mission on remediation
of large contaminated areas off-site the Fukushima
Daiichi NPP (2 EM’s 2013).
Review of Hungarian waste management
framework is in preparation.
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International Atomic Energy Agency
AR
TE
MIS
The Review Service for managing radioactive waste and
spent fuel, control of discharges, decommissioning and
remediation is a cross-cutting coordinated activity of NEFW
and NSRW.
Objective: to provide independent expert opinion and advice
on :
o radioactive waste and spent fuel management,
o assessment of radiological impacts to people and the environment,
o management of residues arising from uranium production,
o decommissioning and
o remediation issues.
Based upon the IAEA safety standards and technical
guidance, as well as international good practice. 9
International Atomic Energy Agency 10
International Atomic Energy Agency 11
Sources of information
• IAEA TECDOC-1527 “Application of Thermal Technologies for Processing of Radioactive
Waste”
• IAEA TECDOC-draft “Treatment of radioactive gaseous waste”*
• IAEA TECDOC-draft “Mobile processing systems for radioactive waste management”
• IAEA TECDOC-draft “Modular design of processing and storage facilities for small volumes of
low and intermediate level radioactive waste including disused radioactive sources”
• IAEA TECDOC-draft “Treatment of Irradiated Graphite to Meet Acceptance Criteria for Waste
Disposal”*
• IAEA IMMONET web site: http://nucleus.iaea.org/sites/nefw-
projects/IMMONET/SitePages/Home.aspx
• M.I. Ojovan, W.E. Lee. An Introduction to Nuclear Waste Immobilisation, 2nd Edition, Elsevier,
Amsterdam, 362 p. (2014).
• W. E. Lee, M.I. Ojovan, C.M. Jantzen. Radioactive waste management and contaminated site
clean-up: Processes, technologies and international experience, Woodhead, Cambridge, 924
p. (2013).
• J. Deckers. Incineration and plasma processes and technology for treatment and conditioning
of radioactive waste. Chapter 3 in: M.I. Ojovan. Handbook of advanced radioactive waste
conditioning technologies. Woodhead, Cambridge, 512 p. (2011).
* available on IMMONET
International Atomic Energy Agency 12
Gaseous radioactive waste
http://nucleus.iaea.org/sites/nefw-
projects/IMMONET/SitePages/Home.aspx
International Atomic Energy Agency 13
International Atomic Energy Agency 14
Mobile off-gas treatment system
International Atomic Energy Agency 15
International Atomic Energy Agency
"Aqua-Express" FGUP RADON
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Aqueous radioactive waste
International Atomic Energy Agency 17
International Atomic Energy Agency 18
International Atomic Energy Agency 19
NUclide REmoval System (NURES), Fortum
NS
International Atomic Energy Agency 20
International Atomic Energy Agency 21
Oil decontamination system: Kinectrics, Canada
180-200oC
International Atomic Energy Agency 22
International Atomic Energy Agency 23
Solid radioactive waste
Non-Thermal
Thermal
International Atomic Energy Agency 24
Solid radioactive waste: non-thermal
Usage as a pre-treatment unit. Up to 500 kN force.
International Atomic Energy Agency 25
Skid mounted supercompactor: GNS
Mobile supercompactors
NUCLECO supercompactor
International Atomic Energy Agency 26
International Atomic Energy Agency 27
International Atomic Energy Agency 28
Floor decontamination system: BARC, India
International Atomic Energy Agency 29
International Atomic Energy Agency 30
Cable insulation separation system: GNS, Germany
International Atomic Energy Agency 31
International Atomic Energy Agency 32
Increasing demands for
enhanced efficiency and
safety of waste
processing technologies
has focused attention on
thermal technologies, as
they provide advantages
regarding stabilization of
the output waste form
and high volume
reduction efficiencies.
Solid radioactive waste: thermal
International Atomic Energy Agency 33
Waste Metal Melting
The final product (ingot, shielding
block, centrifugated steel cylinder,
etc.) is homogeneous, stable, and
has the remaining activity content
bound in the metal. Melting can
produce a conditioned waste form
suitable for direct disposal.
Normally, the amount of secondary
waste is in the range of 2 to 5 wt.%.
International Atomic Energy Agency 34
Plasma Treatment
Plasma sources provide deep
thermal conversion of organic
materials and produce an end
product in the melted state.
Plasma torches use the energy
of an electric discharge
(electric arc) for heating
working gases transmitted
through it.
International Atomic Energy Agency 35
Volume
reduction
factors range
from 6 (typical
ZWILAG
results) for
waste
containing
mostly metals
and debris to 10
for treatment of
mixed waste
(typical RADON
results) and to
more than 100
for primarily
organic waste.
Advantages
⎯ One single process can treat the un-sorted waste.
⎯ The final waste form is durable and suitable for long term storage and disposal.
⎯ Less production of certain flue gasses and the greenhouse gas CO2.
International Atomic Energy Agency 36
1 – loading unit, 2 – shaft, 3 – hearth, 4 –
slag receiver, 5 – plasma torch, 6 – stopper,
7 – off gas outlet.
Plasma shaft furnace 1
2
3 4
5
6
7
International Atomic Energy Agency
Parameter “Pyrolysis” “Pluton”
Capacity to solid waste, kg/h 40-50 200-250 Dimensions, m 8 8 10 12 18 12 Quantity of plasma torches in a furnace 1 2 Electric power of plasma torches, kW 70-120 100-150 Response time, h 8-12 16-24 Specific energy consumption, kW*h/kg 2-4 1-3
Views of control board, shaft furnace and SRW loading unit of the “Pluton” plant
International Atomic Energy Agency 38
Component Content, wt.%
Paper 11 - 90
Wood (scobs) 1 - 5
Wood (fuelwood) 2 - 20
Textile (rag) 4 - 7
Plastic (polyethylene, polycarbonate, PVC) 4 - 8
Glass (domestic and laboratory) 2 - 8
Rubber (hoses, tires) 2 - 5
Electric boards, radio components 1 - 5
Construction waste 4 - 15
Heat insulating materials 1 - 5
Metal 3 - 10
Ion-exchange resins 0.3 - 2
Vegetable materials and berries 2 - 5
Overall ash content of the waste 7 - 40
Overall humidity of the waste 5 - 35
Specific activity to -emitters, within limit of 2.2·105 Bq/kg
Specific activity to -emitters, within limit of 3.7·106 Bq/kg
Component Na+ 137Cs 239Pu
Leaching rate, g/cm2*day
(2-3) *10-6
(0.3-5)*10-6
(0,8-2)*10-7
International Atomic Energy Agency
Non-standardized Not detected Polychlorinated biphenyls (PCB)
Non-standardized From 0.02 to 1.12 μg/m3 Cancerogenic polycyclic aromatic hydrocarbons (benzapyrene)
50 μg/m3 500 μg/m3
50 μg/m3
9 μg/m3
394 μg/m3 1.02 μg/m3
Heavy metals: cadmium lead mercury
0.1 ng/m3 0.014 ÷ 0.02 ng/m3 Polychlorinated dibenzo-p-dioxines and dibenzofurans in terms of toxic equivalent
The European standard for the discharge of pollutants into the
atmosphere
Concentration in off-gas
Component
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Significant reduction (1.5 – 2 times) of the off gas volume as a result of
plasma torches usage instead of combustion type heaters…
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The ZWILAG plant,
serves to process
combustible solid and
liquid wastes, as well as
metals and mineral
substances (concrete,
gravel, etc.).
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The maximum capacity of
the facility is 200 kg/h of
combustible waste and 300
kg/h of fusible waste.
Throughput is approximately
50 000 to 60 000 kg/yr.
International Atomic Energy Agency 42
Plasma Melting Facility at Kozloduy NPP: Belgoprocess
• Ordered to JV IBERDROLA –BELGOPROCESS
• Funded by EBRD (70%) and Bulgaria (30%)
• Testing beginning 2014
International Atomic Energy Agency 43
Plasma Melting Facility at Kozloduy NPP: Belgoprocess
International Atomic Energy Agency 44
Mobile plasma waste treatment facility: Necsa, SA
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International Atomic Energy Agency 46
France: i-Graphite Waste-Management Scenario
More details on: http://nucleus.iaea.org/sites/
nefw-
projects/IMMONET/graphite-
crp/SitePages/Home.aspx
Problematic radioactive waste: i-graphite and DSRS
International Atomic Energy Agency 47
UK: i-Graphite-Management Process proposed by Bradtec,
Hyder, Studsvik UK and Costain
Deta
ils o
n:
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p:/
/nu
cle
us.iaea.o
rg/s
ite
s/
ne
fw-
pro
jects
/IM
MO
NE
T/g
rap
hite
-
crp
/Site
Pa
ge
s/H
om
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spx
International Atomic Energy Agency 48
IAEA Mobile Hot Cell for highly radioactive sources
International Atomic Energy Agency 49
International Atomic Energy Agency 50
International Atomic Energy Agency 51
Disused Sealed Radioactive Sources Immobilisation: FGUP
RADON
International Atomic Energy Agency 52
International Atomic Energy Agency
• Safe and efficient RWM is an important component of
prosperous and peaceful use of nuclear energy and
radioactive materials;
• Technologies for RWM are available and being further
developed;
• IAEA plays an active role in developing and maintaining
high standards of RWM in Member States;
• IAEA is also strongly promoting international cooperation
and exchange of information.
53
Conclusions
International Atomic Energy Agency 54
• Registration via: http://www-
pub.iaea.org/iaeameetings/46
089/Scientific-Forum
20
14
IA
EA
Genera
l C
onfe
rence S
cie
ntific
Foru
m
• The General Conference is the highest policymaking body of the IAEA. It is
composed of representatives of all Member States of the Agency. The 57th
IAEA General Conference held on 16-20 September 2013 involved more
than 3 000 delegates from 159 IAEA MSs and international organizations.
• The 2014 GC-58 will be held at IAEA on 23-25 September 2014. At the
58th General Conference, the theme of the Scientific Forum will be
“Radioactive Waste: Meeting the Challenge”.
Scientific Forum