thec2013 -industrial view on thorium 28 31 october 2013 p. 1...as soon as youintroduce fertile...
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p. 1 ThEC2013 - Industrial View on Thorium - 28-31 October 2013
An industrial view on Thorium: Possibilities, Challenges and Paths forward
Luc Van Den Durpel Vice President Strategic Analysis and Technology Prospective
Corporate R&D
ThEC 2013 Conference
October 28th – October 31st 2013
CERN, Geneva
p. 3
Possibilities for Thorium use in nuclear energy systems
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 4
Why is Thorium that … « modern » again?
« It is neutronically exciting »
As soon as you introduce fertile materials, e.g. Th, you need to balance the neutrons well
233U can act as the « 239Pu » in thermal neutron spectrum reactors
And can provide routes to synergies among thermal neutron spectrum reactors
Provides higher conversion ratio routes in thermal neutron spectrum reactors
Though, some 233Pa-233U management issues in-core
« It can, in the longer term, offer some advantages »
Less MA-production
Higher melting point & cooler fuel
One oxidation state
« It’s not plutonium »
Claims on proliferation risk advantages
Provides an avenue to a « new nuclear »
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 5
There’s a (re)new(ed) « hype » on thorium today
« Generation-IV »
But most proposals today on Th only address one family of strategies, i.e. « Th-dedicated nuclear energy systems »
Many can be classified as « Generation-X » (X ≥ 5) when full account is taken of fuel cycle developments required
Pu and MA-management
During the last two decades, Partitioning and Transmutation (P&T) was a strong driver of advanced fuel cycle R&D worldwide
E.g. Pu/Th-option for Pu-management
Nuclear energy sustainability
E.g. India transitioning towards 233U/Th-cycle
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 6
Socio-political consequences from this hype
« We can accept nuclear energy as solution, as long as it is Th-based »
Increasing debate and ‘flawed’ discussions on the potential of thorium canibalising a true scientific-technological assessment of Th
The debate is mostly or even solely driven by longer-term « Generation-IV/X » projections
Scientifically-technologically correctness is required
There will never be a « Th fuel cycle » without a (starting) complementarity with a U/Pu-cycle
Any Th-use requires a fissile material to start with
Any Th-fuel cycle requires reprocessing and recycling to make true use of 233U and achieve the objectives
The claimed benefits of « Th fuel cycle » will only be gradually achieved and will take a long time as well (>100 yrs)
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 7
Let’s demystify the role of Thorium a little
There are essentially three major families of scenarios envisaged for use of Th/233U
Complementary use of Th/233U in U/Pu nuclear energy systems
Possibility to use Th/233U in LWRs, PHWRs and FRs in view of
- Lengthening the cycle time in LWRs
- Reducing the Unat/TWhe use, and/or
- Providing multiple-recycling option for Pu , and/or
- Replacement of DU in specific cases, and/or
- Breed 233U for future use in other reactor systems
(Transition towards ) « Generation-III(+) » 100% Th/233U-nuclear energy systems
Th provides synergies between thermal spectrum reactors, e.g. LWRs + CANDUs/AHWRs as well as with FRs
Th-dedicated « Generation-IV/X »-systems (X≥5)
« Generation-IV/X » longer-term options considering use of MSRs, ADSs, LFTRs, …
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 8
Th-use in nuclear power demands a (LT) strategy why Th would bring value in a nuclear
programme
Forget the claims that, internationally, « Th-fuel optimised NPPs » would be available ‘tomorrow’, e.g. < 2030
There are today no classic argumentations driving in favour of th instead of Unat/Pu
For an investor in an NPP, the international market offers reliable industrial solutions with international fuel cycle services in the U/Pu-cycle
No additional risks introducing ‘game-changing’ technologies to ensure competitive nuclear energy
Only with a medium- to longer-term strategy, and addressing strategic issues, Th may become a viable option for consideration
Th-fuel development and qualification in Gen-III(+) reactors takes time and transitioning from an initial UOX/MOX-core towards a (partial) Th-OX fueled core takes time as well
Unless a government drives a large Th-fuel and reactor (R&D-)programme with a long-term vision, Th-use in nuclear power will occur
Progressively in Gen-III(+) reactors, potentially preparing Gen-IV and/or Gen-X options
Providing the answer to specific challenges which are primarily of fuel cycle nature
Ensuring that the Th-containing fuel is well complementary with the U/Pu-cycle and offering additional flexibility to NPP-operators and countries
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 9
ALWR
Indicative timeline for U/Pu/Th-use in nuclear energy systems
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
Today 2020 2030 2040 2050
AHWR
ADS / MSR/LTFR
F(B)R
HTR
LWR
PHWR
U
UOX MOX Pu
URT
MOX
Pu
URT
FR-MOX
Pu
Pu
URT
Th-Blanket
Th
UTh-OX 233U
233U / Th
U-Blanket
Pu
p. 10 ThEC2013 - Industrial View on Thorium - 28-31 October 2013
As nuclear will grow … there might be some concerns
Temporary imbalances of supply/demand for front-end services, specifically Unat availability, may lead to higher and more volatile fuel prices during the 2030-2050 period
Perception of temporary ‘scarcity’ due to possible imbalance Unat supply/demand especially in light of rapidly growing regional NPP-parks with additional effect from U-traders in a single-product market
NPP’s trend towards technical lifetimes (well) beyond 60 years
Investors need to be assured that fuel availability is not an issue for their investment over long time horizons
Today’s LWR-designs will be operating well into the 22nd century !!
As such, fuel cycle flexibility is becoming increasingly important
Planning actions towards higher fuel cycle flexibility include
In the short and medium-term fuel delivery contracts (time-period, multiple providers, …)
In the medium- to longer-term technical fuel and fuel cycle flexibility, i.e. having qualified fuels with fissile/fertile content U-Pu, 30%-100% MOX, U-Th, Pu-Th, 233U-Th according to market and technological developments
In addition, new NPPs, i.e. specifically allowing « multi-recycling Pu » in LWRs and ultimately FRs provide better use of natural resources while also potentially reducing amount of ultimate radioactive waste
p. 11
Challenges ahead
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 12
What are the drivers to use Thorium in nuclear power especially, and ideally, at larger scale in due
time?
What are the new ‘market’-conditions for Th-use compared to the past?
Nuclear power is a hugely capital-intensive industry with thus, inherently, technology lock-in behaviour
And do not forget fuel cyccle technlogies development and strategies !
Th/233U involves multiple issues in a ‘100%’ Th/233U fuel cycle, i.e.:
Fissile material balance for start-up
Recycling and especially refabrication issues with 232U
Proliferation risk assessment is not univocally in favour only
If there wouldn’t be new market conditions, one could easily remain with Th on ‘paper-level’ if not driven by a governmental strategy as the switching costs from U/Pu to Th/233U for nuclear industry are very important or even huge
Are there any new drivers today that would facilitate progressive introduction of Th?
And if so, ideally addressing a large part of the nuclear power park worldwide, i.e. addressing LWR fuel cycle?
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 13
‘Conditions’ to consider Th in LWR-based energy systems?
Are there any improvement avenues in U/Pu-cycle where Th provides added value?
Lengthening the cycle time in LWRs
Reducing the Unat/TWhe use, and/or
Providing additional multiple-recycling option for Pu, and/or
Replacement of burnable poisson in specific cases
But
Fuel cycle impacts especially in recycling schemes
Any consideration of Th-use needs to be progressive
Keep as long as possible the « thorified » fuel separate from the U/Pu-cycle
This means
As long as possible, keep both fuel cycles separated
How?
Couple U/Pu and Th/233U neutronically though not physically nor chemically for as long as possible until there might be a market to go towards « Th fuel cycle »
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 14
ALWR
An alternative scheme among many considerable
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
Today 2020 2030 2040 2050
AHWR
F(B)R
LWR
PHWR
U
UOX MOX Pu
URT
MOX
Pu
URT ?
FR-MOX Pu
URT
?
Th-Blanket
Th UTh-OX
233U
233U / Th
U-Blanket
UOX
PuThOX
MOX
Pu
Pu
Pu
p. 15
There are multiple paths before embarking into « Th-cycle »: some provide complementarity with U/Pu-cycle already in medium-term
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
2010 2020 2030 2040 2050
Fraction of Th
in U/Th or
Pu/Th fuel (%)
100
50
10
MSR
LFTR
LWRs / CANDUs
LWRs/CANDUs
AHWR (India)
« Th/233U-cycle » with Th-optimised reactor concepts
Pu/Th options
Th as additive
Objectives:
• Unat/TWhe reduction through in-core 233U breeding and recycling
• Level of Th-content important for potential in reducing Unat/Twhe though demanding MEU for high Th-contents
Objectives:
≈ 5 – 10% Pu/th
• Unat/TWhe reduction through in-core 233U breeding and recycling
• Multi-recycling of Pu (from used MOX) in LWRs
≈ 14 – 20 % Pu/th
• Pu-burning while breeding 233U in transition scenarios
• High BU options with SiC cladding for once-burn-disposal
Objectives:
• BU and cycle length extension
• Reduction/Replacement of Gd as burnable poison
• Core power flattening
U/Th options towards Unat/TWhe reduction
p. 16
Some take-aways from AREVA’s assessment of Th-options in LWRs
Based on EPRTM-design evolutionary fuel options
‘Envelope’ of evolutionary Th-use potential
One can introduce beneficially Th in LWRs while keeping U/Pu and Th/233U-vector as long as possible separated
Some 20 to 50% of energy provided by 233U
Most options require reprocessing to ensure achievement of objectives
Though, given stable 233U, reprocessing may be delayed
Reduction by 25 – 35 % of Unat/TWhe in recycling schemes
An improved Pu-balance in UOX and MOX for multi-recycling of Pu
Reduction in enrichment needs
Reduced MA-production
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 17
AREVA and Thorium: expertise and experience dating from the 1970s
Thorium is not new for AREVA
AREVA holds inventory of 2450 tTh as Th-nitrate in France from former mining operations (Madagascar) and AREVA developed the appropriate technological solutions for its proper management (processing, handling, interim storage)
AREVA researched and (co-)fabricated Th-fuels for PHWRs, HTRs, and LWRs
1970s BWR Lingen irradiation of 2.5%-Pu/Th pellets (20 GWd/tHM)
1980s collaborative program on Th-fuel for PWRs
1990-2000s PWR Obrigheim UPu/Th irradiation (up to 37 GWd/tHM)
- PIE indicated no issues
Sol-gel, powder metallurgy and impregnation fabrication methods were tested and no major issues up to 30% Pu were encountered though demanding modified process parameters
Ceramic lab(s) still available and equipped for Th-fuel R&D-programme(s)
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 18
Paths forward
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 19
Thorium can have its place in a growing nuclear energy future
As nuclear energy is a prime contributor to address climate change and energy sustainability objectives worldwide
A progressive and U/Pu-complementary introduction of Thorium is conditional to any Th-use in the future
Any introduction of Th needs to be assessed industrially to ensure technical-economic effective and efficient paths forward for such Th-use
Given the overall worldwide developments related to thorium, both in the nuclear energy field as in the rare-earth market
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
AREVA and SOLVAY join their know-how to add value to thorium’s entire life cycle
p. 20
AREVA and SOLVAY’s provide holistic Th-management
RE-mining
RE-ore processing
REO separation and purification
REO processing into products
Th-residues
Th-residues
Interim Storage Th-residues
Separation and Purification of Th
LT Interim Storage Th
Valorisation as Th-fuel in nuclear power
Other applications of Th
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 21
AREVA-SOLVAY « Thorium Valorisation » Agreement
AREVA and Solvay embarked since 2013 in a collaborative programme towards Thorium valorisation
Both companies together master the complete set of Thorium valorisation routes in the short- to longer-term with clear synergies ensuring Thorium valorisation services also to be provided to third parties.
The collaborative programme encompasses
Resolving the Th-residues issues arising from certain Rare Earth processing in the past and now
Providing an industrially robust valorisation argumentation focused on Thorium valorisation in nuclear power in the medium-term
Ensuring best-practice interim management options for Thorium awaiting this Thorium valorisation in the medium-term
An R&D-programme focused on medium-term Thorium valorisation in nuclear power is set-up with international R&D-partners geared towards first phase of fuel-development with irradiation by 2020
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 22
Synthesis of AREVA-SOLVAY’s R&D-programme on Th-valorisation in nuclear energy
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
- 2012 2013 2014 2018 2020 2025 2030
Scoping Analysis of Th-options
• Reactor Physics studies (LWR, PHWR, FR)
• PhDs
• Techno and Patent Watch
• International Projects involvement
• Know-How transfer
« There is clear scope for Th-
use in future nuclear power
and R&D-programme to be
strengthened »
Experimental R&D Programme
Phase 0 Phase 1a Phase 1b
Fuel Fab development and testing
NPP Segmented Rod irradiation to high BU and PIE
Phase 2
Downselection of Th fuel
cycle strategies and fuel
fab development focus
Selection of NPP-
irradiation and licensing
of irradiation
2016
Licensed Irradiation in
NPP start Decision on Lead Test FA
irradiation
Phase 3
Lead Test FA Irradiation
Qualified Th-fuel development
Phase 4
Decision on Th-fuel
development
• Detailing fuel cycle strategies
with international partners
• R&D international consortium
• Preparing labs
p. 23
In Summary
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 24
Concluding observations
Please, demistify the « Th fuel cycle » story and claims
Th-dedicated « Generation-IV/X » systems won’t make it:
Without an initial long period of complementarity with U/Pu-cycle in Gen-III(+) and IV systems
Without a government long-term vision spurring their development
Is there a clear market for U/Th and Pu/Th-fuels in the short-term?
In the medium-term: possibly depending on the international nuclear energy systems development and the requirement for fissile/fertile materials management synergistically intra-nuclear and inter-regionally
Transition, if desired to go towards « 100% Th », will take a time, i.e. decades at least
AREVA and SOLVAY are
investigating Th-fuel options as complement to U/Pu-cycle in an international context and
addressing a holistic Thorium management providing industrial solutions to those requiring and considering valorisation of thorium both in Rare Earth as in nuclear energy market
AREVA and Solvay welcome collaboration with R&D-organisations and other companies
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
p. 25
Thank you
ThEC2013 - Industrial View on Thorium - 28-31 October 2013
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