thec2013 -industrial view on thorium 28 31 october 2013 p. 1...as soon as youintroduce fertile...

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 »


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


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)


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, …


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


p. 9

ALWR

Indicative timeline for U/Pu/Th-use in nuclear energy systems


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


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?


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 »


p. 14

ALWR

An alternative scheme among many considerable


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


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


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)


p. 18

Paths forward


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


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


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


p. 22

Synthesis of AREVA-SOLVAY’s R&D-programme on Th-valorisation in nuclear energy


- 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


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


p. 25

Thank you


thec2013 -industrial view on thorium 28 31 october 2013 p. 1...as soon as youintroduce fertile...

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