EERA JPN M Visi on Repport - fp7-matisse.eu · Project A. Mich 06/02/2 ents Coordinator aux, CEA...

C

Combination of Collabora

Sta

EER

FPative project

Grant agart date: 01/1

RA JPN

P7-Fission-20(CP) and Co

greement no1/2013 Dura

D1.21a

NM Visi

013 oordination a

o: 604862 ation: 48 Mon

ion Rep

nd Support A

nths

port

Actions (CSAA)

MatISSE – D.5

MatISSE –

Document

Main Autho

Number of

Document

Work Pack

Document

Issued by

Date of co

Dissemina

Summary

This reports

Approval

Rev. Da

1 14

Distribution

Name

MatISSE G

EERA JPNM

DG-RTD

EERA JPNM

ESNII Task

CEN-WS/64

5.21a – Fina

Contract Nu

t title

or(s)

f pages

t type

kage

t number

mpletion

ation level

s provides th

ate

4/01/2015

n list

eneral Asse

M Steering C

M Stake-hold

k Force

4-Phase-2 P

al version o

mber: 60486

EERA JPN

K-F Nilsso

15

Report

1

1.21a

JRC

15/01/2015

PU Public

e Vision for E

mbly

Committee

der group

PG2

on 19/12/20

62

NM Vision Pa

n, JRC, L. M

5

ly available

EERA JPNM

Lead

K-F N

14/01

Or

14..

/15

aper

Malerba, SCK

M in the timef

d Author

Nilsson, JRC

1/2015

rganisation

K•CEN, A. Jia

frame 2015-2

C,

Comm

anu, KIT

2020

Project

A. Mich

06/02/2

ments

Coordinator

aux, CEA

015

MatISSE – D.5.21a – Final version on 19/12/2014..

/15

ContentsExecutive Summary ........................................................................................................................................... 4

1. Target of this document ............................................................................................................................. 5

2. Nuclear energy in future low-carbon energy systems ............................................................................... 5

3. Materials for future nuclear reactor systems .............................................................................................. 7

4. Grand Challenges for structural and fuel materials for future nuclear reactors ......................................... 9

5. Towards an integrated European Nuclear Materials Programme ........................................................... 12

6. Risks ............................................................................................................................................................ 14

Appendix: milestones and high-level deliverables ........................................................................................... 15

References ...................................................................................................................................................... 15


/15

Executive Summary

Nuclear energy has an important role in implementing the challenge of the Energy Union’s forward-

looking climate change policy, as it provides energy with very limited CO2 footprint at stable and

comparably low prices, as well as a secure and reliable supply of base-load electricity. Nuclear power

today fulfils these requirements but two main issues remain, namely accident risk and long-lived nuclear

waste. Sustainability is not adequate (less than 1% of the energy content of the fuel is actually used), but

can be resolved completely by the deployment of Gen IV fast neutron reactors along with the necessary

fuel cycle facilities (beyond the state of the art) to extract reusable components of the fuel from which

new fresh fuel is generated. Thus, the energy utilization of the fuel is increased and the radiotoxicity of

the waste is dramatically curtailed. In this framework, the performance of nuclear (structural and fuel)

materials is essential for the development of sustainable nuclear energy. Materials in fast reactors will

be exposed to higher temperatures and higher irradiation levels than today's light-water reactors. Fast

reactors also use non-aqueous coolants, for which the full compatibility of materials needs to be

demonstrated. The European Energy Research Alliance (EERA) Joint Programme on Nuclear Materials

(JPNM) was launched in 2010 to provide the R&D for materials needed for the development and

implementation of fast reactors in Europe, as defined by the European Sustainable Nuclear Industrial

Initiative (ESNII).

This report describes the Vision of the EERA JPNM with respect to Grand Challenges that must be

addressed and resolved to take full advantage of the nuclear GenIV technology, with respect to safety,

performance and cost, and to ensure implementation towards 2040.

Grand Challenge 1: Elaboration of design rules, assessment and test procedures for the expected

operating conditions and the structural and fuel materials envisaged. This involves deployment of

infrastructures for relevant ageing phenomena and for testing of materials, data and knowledge,

which is currently limited.

Grand Challenge 2: Development of physical models coupled to advanced microstructural

characterization to achieve high-level understanding and predictive capability: an asset, given the

scarcity of experimental data and the difficulty and cost of obtaining them.

Grand Challenge 3: Development of innovative structural and fuel materials with superior thermo-

mechanical properties and radiation-resistance or, in general, nuclear-relevance, in partnership with

industry. Addressing these Grand Challenges requires a concerted action at European level involving research

community and industrial partners. The EERA JPNM addresses this by proposing a five-step process

towards an integration of relevant nuclear material laboratories in the EU Member States by 2020 with

the overall objective to ensure that nuclear GenIV technology can be implemented, as planned, in

Europe from 2040. The integration of nuclear materials research is necessary to optimise the use of the

available human and financial resources, as well as facilities and expertise, with the goal of solving the

future energy needs, but it requires sufficient support and engagement of the European Commission and

Member States.

MatISSE – D.5

1. Ta

This report

Nuclear Ma

the nee

climate

the key

the Gra

the esta

This report

EERA JPNM

the Strateg

platforms re

especially M

2. Nu

The transitio

by the Stra

looking cl

(http://ec.eu

implementa

industrial s

organisation

In the last

source. Alt

electricity in

significant s

Energy Age

generation

energy syst

Figure 1 - atechnologies

5.21a – Fina

arget of

presents th

terials (JPNM

ed for future

change polic

role of struc

and Challeng

ablishment o

serves as a

M over the c

ic Energy T

epresenting b

Member State

uclear e

on from foss

ategic Energy

limate cha

uropa.eu/prio

ation of the

scale and th

ns, for the ne

decades nu

though the s

n the EU in

share of nuc

ency, which

by 2035 [3]

tems, as stat

a) world enein different sc

al version o

this do

he vision of

M) with respe

nuclear ene

cy;

ctural and fue

es for such m

f an integrate

reference do

oming five-y

Technology P

both industry

es represent

energy i

sil fuel-based

y Technolog

ange policy

orities/energy

SET-plan te

he European

ecessary sup

uclear energ

share of nuc

2013, with a

clear energy

limits globa

. Another tr

ted in the En

rgy related Ccenarios from

on 19/12/20

ocument

the Europea

ect to:

ergy as a co

el materials f

materials tha

ed European

ocument for

ear period.

Plan (SET-P

y and resear

tatives and E

in future

d to low-carbo

gy Plan (SET

y", now a

y-union/index

chnologies a

n Energy R

pporting R&D

gy has been

clear has so

a share of 2

y. Figure 1

al warming

rend is that

ergy Techno

CO2 emission[3].

14..

/15

t

an Energy R

omponent of

for the develo

at need to be

n nuclear (str

the Roadma

It is aimed p

Plan) Workin

rch organizat

Euratom offic

e low-c

on energy sy

T-Plan) [1] a

a key pr

x_en.htm ).

are the Euro

Research Al

D.

n, together w

omewhat dec

27% [2]. Mos

shows that

to 2°C, req

electricity w

ology Perspe

ns by scenar

Research All

a resilient E

opment of su

e addressed;

ructural and

ap and more

rimarily at ou

g Groups, n

tions, as wel

cers.

arbon e

ystems is a m

and the "res

riority of

Two key ins

opean Indus

liance, led

with hydropo

clined, it wa

st future low

the ambitiou

quires a very

will be an inc

ectives 2014

rio b) world e

liance (EERA

Energy Union

ustainable nu

fuel) materia

detailed Des

ur stakeholde

nuclear and

l as manage

energy s

major global

silient Energy

the new

struments fo

strial Initiativ

by Member

ower, the m

s still the la

w-carbon ene

us scenario

y large nuc

creasingly im

(ETP 2014)

electricity gen

RA) Joint Pro

n with a forw

uclear reacto

als research

scriptions of

ers, such as

non-nuclear

ers and decis

systems

challenge a

y Union with

Juncker

or the devel

ves for demo

r State pub

major low-car

argest energy

ergy scenario

450 of the

clear share o

mportant vec

[4].

neration from

ogramme on

ward-looking

or systems;

programme.

f Work of the

members of

r technology

sion-makers,

s

as expressed

h a forward-

Commission

opment and

onstration at

lic research

rbon energy

y source for

os include a

International

of electricity

ctor in future

low-carbon

n

g

e

f

y

,

d

-

n

d

t

h

y

r

a

l

y

e

MatISSE – D.5

In addition

need also t

resources.

in [5]; nucle

renewable s

manner to b

Reliable sup

periods. Nu

today's Gen

or III+, but

addition, su

increased b

facilities, fo

used (conve

recycling fa

Coupled tog

minor actin

2040. Proto

Industrial In

and gas coo

Figure 2 - Th

Figure 2 sh

LFR (ALFR

material tes

5.21a – Fina

to reducing

o provide en

Nuclear ene

ear base-load

sources, alth

balance this

pply is secur

uclear-genera

neration II lig

two issues

ustainability o

by the deplo

r both of wh

ersion ratio g

acilities shou

gether, the lo

ides are rec

otypes and d

nitiative (ESN

oled fast reac

he schedule fo

hows the tim

RED) and G

sting and de

al version o

CO2 emiss

nergy at affo

ergy has pred

d is also a s

hough a large

increased int

red as stable

ated electric

ght-water rea

remain ope

of Gen II an

oyment of sa

hich extensiv

greater than

uld extract r

ong term rad

cycled. It is

demonstrator

NII), with sod

ctors (GFR)

or the design a

e line for the

GFR (ALLEG

emonstration

on 19/12/20

ions and ha

ordable price

dictable and

tabilizing fac

e share of th

termittency i

e countries p

ity in the ne

actors and ne

n today, nam

nd III reacto

afely design

ve R&D is ne

1) and shou

reusable co

diotoxic impa

expected th

rs are being

dium fast rea

as alternativ

and constructio

e different sta

GRO) prototy

of accelera

14..

/15

aving minima

es and ensur

relatively low

ctor in an en

he latter will r

n a future low

provide urani

ext 2-3 deca

ew-build of e

mely the acc

ors is limited

ned Gen IV

eeded. Such

uld reach hig

mponents fr

act of irradia

at the GenIV

developed

actors (SFR)

ves [6,7].

on of the four

ages towards

ypes, as we

ated driven s

al environme

re security of

w prices, as

ergy mix wit

require that n

w-carbon en

um for nucle

ades will mai

evolutionary

cident risk a

. These issu

fast neutron

h reactors cr

gh fuel burn

rom the fue

ted nuclear

V systems c

now in Euro

as the most

demonstrator

s constructio

ell as MYRR

systems (AD

ental impact,

f supply, wh

reported in c

h an increas

nuclear is op

ergy mix.

ear fuel, whic

inly be provi

designs refe

and the long

ues can be

n reactors a

reate more f

ups for grea

l for the pr

fuel can be

can be comm

pe within the

t mature tech

s and prototyp

on of the SFR

RHA, a flexi

DS) for waste

, future ene

hile optimizin

comparative

sing share of

perated in a m

ch can be sto

ided by life-

erred to as G

g-lived nucle

faced and s

along with fu

fissionable m

ater efficienc

reparation o

abated, esp

mercially de

e European

hnology, and

pes in ESNII.

R prototype A

ible research

e minimizati

rgy systems

g the use of

studies, e.g.

f intermittent

more flexible

ored for long

extension of

Generation III

ar waste. In

sustainability

uel recycling

material than

cy, while the

f fresh fuel.

ecially when

eployed from

Sustainable

d lead (LFR)

ASTRID, the

h facility for

on, which is

s

f

.

t

e

g

f

I

n

y

g

n

e

.

n

m

e

)

e

r

s

MatISSE – D.5

strongly rela

2, 10 810 M

financial an

between ind

concerted re

3. Ma

Materials in

by the fuel,

combination

Structur

higher l

These m

for whic

Moreov

reactors

Finally,

stringen

alternat

Consequen

nuclear sys

leading role

this framew

5.21a – Fina

ated with LF

M€ [6], is like

d human res

dustrial partn

esearch actio

aterials

nuclear rea

, cladding a

n with very h

ral and Fuel

evels of irrad

materials als

ch experienc

ver, the desi

s.

the requirem

nt, while the

tive low-carb

Figure 3 concepts

tly, materials

stems. Mater

e, is also a c

work, the ove

al version o

R technology

ely to be an

sources, the

ners and rese

ons on mate

s for futu

ctor compon

nd neutron

igh safety re

Materials fo

diation than i

so need to be

e is limited.

gn life shou

ments to de

overall costs

on energy so

- Range of tes and fusion.

s research,

rials under e

cross-cutting

erall objectiv

on 19/12/20

y. The indica

n underestim

implementa

earch organi

erials for Gen

ure nuc

nents include

absorbent m

equirements.

or Gen IV rea

in today's lig

e compatible

uld be at lea

monstrate sa

s for nuclear

ources.

emperature a

qualification

extreme con

area for diff

ve of the EE

14..

/15

ative cost in 2

mation. Give

ation of the E

izations from

nIV reactors c

clear rea

e the structur

materials. Al

In particular

actors will ge

ht-water reac

e with uncon

ast 60 years

afety in both

r energy nee

and irradiation

and develo

nditions, in w

fferent high-e

ERA JPNM i

2010 for the

n the techno

ESNII plan m

m different EU

constitute an

actor sy

res of the rea

l are expose

r it should be

enerally be e

ctors, as illus

ventional co

s, compared

h normal and

ed to be com

damage for d

opment are c

which the nu

efficiency low

is to provide

ESNII progr

ological chal

must be base

U Member S

n especially c

ystems

actor and the

ed to very d

noted that:

exposed to h

strated in Fig

olants, such

to the typic

d accidental

mpetitive, i.e.

different fissio

crucial for th

uclear sector

w-carbon ene

e the underp

ramme outlin

lenges and

ed on a conc

States. In this

crucial need.

e fuel assem

demanding c

higher tempe

gure 3.

h as liquid me

cal 40 years

conditions w

similar to o

on reactor

he deployme

r traditionally

ergy technol

pinning mate

ned in Figure

the required

certed action

s framework,

blies formed

conditions in

eratures and

etals or gas,

s for today's

will be more

or lower than

ent of GenIV

y has had a

logies [8]. In

erials related

e

d

n

,

d

n

d

,

s

e

n

V

a

n

d

MatISSE – D.5

research, in

support of t

JPNM is the

The develo

research a

component

reactors is

use, initially

safety marg

The EERA

illustrated in

1. Assess

compon

predicti

and qua

2. Develop

behavio

provide

by prov

3. Develop

industri

resistan

aggress

The work is

appropriate

5.21a – Fina

n close colla

he developm

erefore an in

pment of nu

nd feedback

manufacture

a long proce

y and to a lar

gins and reac

JPNM ther

n Figure 4:

ment of cand

nents in oper

on of long-te

alification, as

pment of adv

our, support t

basis for the

viding predict

pment of inn

al use with s

nce to irradia

sive environm

s organized

topics from

al version o

aboration wi

ment, design

tegrated par

uclear mater

k of experie

ers. The qua

ess that typi

rge extent, p

ctor performa

refore follow

didate structu

rational cond

erm behaviou

s well as dev

vanced mode

the elaborati

e improveme

tive capability

ovative struc

superior capa

ation, high-te

ments.

in six sub-pr

basic resear

Figure 5 –

on 19/12/20

th industrial

and constru

rt of ESNII [7

ials and com

ence from re

lification of s

cally has tak

proven techn

ance, innova

ws three pilla

ural and fuel

ditions with re

ur: screening

velopment of

els to rationa

on of design

ent of materia

y;

ctural and fue

abilities in ter

mperatures a

rogrammes

rch to industr

– Subprogra

14..

/15

partners, s

uction of futu

].

mponents ha

reactor desig

structural ma

ken decades

nology and a

ative technolo

ars, which c

materials an

espect to:

g, selection

design rules

alise materia

n rules and

als propertie

el materials f

rms of

and

(SPs) cover

rial applicatio

amme structu

serving EU M

re safe and

as always be

gners and o

aterials, comp

s. To reduce

vailable nuc

ogies and ma

combine mo

nd

s;

als

s,

for

ing structura

ons, as show

ure of the EE

Fi

Member Sta

sustainable

een driven b

operators, a

ponents and

e time and c

lear material

aterials must

odelling and

al materials a

wn in Figure

ERA JPNM

igure 4 - The p

ates and soc

nuclear reac

by a close in

as well as m

fuel materia

costs, future

ls, but to furt

t be develope

experiment

and fuel and

5.

pillars of EERA

ciety, and in

ctors. EERA

ntegration of

material and

als in nuclear

reactors will

ther improve

ed.

tal work, as

d addressing

A JPNM

n

A

f

d

r

l

e

s

g


/15

4. Grand Challenges for structural and fuel materials for

future nuclear reactors

The nuclear energy sector has always been required to deal with demanding material issues and has

responded by finding new engineering solutions. These include nuclear-grade materials and standardized

test procedures, design and construction codes and defect assessment codes. Furthermore, within nuclear

research programmes, state-of-the-art models in fields such as elastic-plastic fracture mechanics and high-

temperature degradation of materials, with and without irradiation, and, more recently, multi-scale models

and physics based models have been developed.

The requirements on structural materials, fuel and components of the prototype and subsequently industrial

scale GenIV nuclear systems present the nuclear community with a number of grand challenges. Some of

these are common for all fast reactor concepts, whereas others are reactor-type specific. The problems to be

addressed concern the degradation of properties of materials: this is a synergistic effect of radiation, high

temperatures, mechanical stresses and aggressive environments, accumulated over a long exposure time.

Moreover, under rare but abnormal conditions (e.g. accidents), the structural materials and the nuclear fuel

will encounter even harsher conditions, which also need to be accounted for in an integrity analysis. These

degradation modes may also interact, thereby further complicating their analysis. One problem that is more

pronounced for nuclear than other sectors is the need to predict, with sufficient confidence, the long-term

behaviour of materials and components under tough conditions, for which there is no or very little operational

experience.

Structural material exposed to irradiation and high temperature become mechanically less performing

(embrittlement, reduction of elongation, …) and change their dimensions (swelling, creep, …). Exposure to

coolants produces general and localised corrosion and erosion and these effects are generally exacerbated

by irradiation. The consequences of all these processes must be harnessed and mitigated via materials

science knowledge and appropriate design.

With respect to novel fuels, important features to be addressed are increased burn-up, tolerance to possible

accident scenarios (margin to melt), good compatibility with the coolant swelling, and cladding, capability to

include minor actinide, neutronic performance, etc. The fuel chemical form and consolidation mode (pellet vs

particle) need to be assessed.

One important objective of the GenIV nuclear systems initiative is the “safety and reliability” of the advanced

reactors, while also considering the overall cost. In order to accomplish this goal, the scientists and

engineers have to address three grand challenges related to structural materials and nuclear fuels:

Grand Challenge 1: Elaboration of design rules, assessment and test procedures suitable for the expected operating conditions and the materials envisaged. This involves deployment of infrastructures for relevant ageing phenomena and for testing of materials, data and knowledge, which is currently limited.

Design codes are crucial for ensuring that nuclear reactor components are designed on well-established

safety procedures and with proven safety margins. Design codes are also central to reducing the costs of

nuclear reactors, for instance facilitating licensing; e.g. the French design codes RCC-MRx will be used for

GenIV ESNII reactors.

MatISSE – D.5

However, s

limited cons

rules, mate

conditions;

both existin

This approa

correct env

robust engi

research fac

expected op

This involve

capabilities,

All these a

components

included in

Together w

guide the e

where expe

design code

reliable des

Grand Chcharacterizscarcity of

evolution, w

microstructu

Figure 6 -

scales

5.21a – Fina

ome rules o

servatism. T

rial design d

and (ii) deve

g and new m

ach will be b

ironment (pr

ineering mod

cilities that a

perational co

es large inv

, as well as t

activities are

s of the reac

subprogram

ith extensive

elaboration o

erimental dat

e) materials,

sign criteria. T

allenge 2: zation to aexperiment

when operatio

ural characte

Models and

al version o

f these code

here are the

data and pro

elop new de

materials, but

based on ext

re-normative

dels. The ke

are suitable t

onditions, es

vestments fo

esting exper

also neces

ctors. The re

me 1 of EER

e testing and

of design cri

ta are scarc

for which un

The next Gra

Developmchieve hightal data and

onal experie

erization of

d processes

on 19/12/20

es may be ov

erefore strong

ocedures for

sign rules, m

t for longer d

tensive quali

research) in

ey for the fu

o expose the

specially in te

r the deploy

rtise under co

ssary in ord

esearch activ

RA JPNM (Fig

characteriza

teria or the

e. This appr

nderstanding

and Challeng

ent of phyh-level undthe difficult

nce is limite

materials th

at different

14..

/15

verly conser

g arguments

existing stru

material desi

design lifetim

ification of th

n order to ob

ulfilment of

e materials t

erms of prolo

yment of su

onditions for

der to plan

vities concer

gure 5).

ation for qua

extrapolatio

roach applie

g of relevant

ge is therefor

ysical modderstanding ty and cost

Si

to

to

nu

le

th

pr

in

th

tu

m

ch

pr

pr

d or does no

hat are subje

length

rvative for Ge

s for improve

uctural and f

ign curves a

e and harshe

he structural

btain the nec

this goal is

o conditions

onged irradia

itable infrast

which often

adequate sa

ning the ES

alification, ph

on of materia

s in particula

phenomena

re:

dels couplepredictive

of obtaining

imultaneous

o the microst

o the extre

uclear reacto

ngth and tim

e macrosco

roperties. F

duces dama

e dynamics

rn, this con

aterials’ ma

hallenge is

redict and v

roperties tha

ot exist at all

ected to spe

enIV, while o

ements to: (

fuel materials

nd assessm

er conditions

and fuel ma

cessary data

the availab

resembling

ation and pre

tructures an

standards d

afety integrit

NII advanced

hysics-based

als’ property

ar to new (o

is necessary

ed to advacapability:

g them.

complex pro

tructure of m

me conditio

ors. These ta

me scales and

opic scale as

For instanc

age at the ato

of dislocatio

trols ductility

acro-level.

therefore

verify the de

at are indu

l. The approa

ecific and co

others may h

(i) revise and

s under curr

ment procedu

s.

aterials of in

a for the dev

bility and acc

as close as

resence of flo

nd correspon

o not exist y

ty assessme

d reactor pro

models may

y data curve

or existing bu

y to define ad

anced micr: an asset,

ocesses cau

materials, wh

ons envisag

take place o

d manifest th

s a change

ce, neutron

omic level, w

ons in structu

y and tough

A fundam

to understa

egradation

uced by mi

ach combine

ontrolled con

have a quite

d modernize

rently known

ures to cover

nterest in the

velopment of

cessibility of

possible the

owing fluids.

nding testing

et.

ents for key

ototypes are

y be used to

s to regions

ut not in the

dequate and

rostructural, given the

use changes

hen exposed

ged in fast

over different

hemselves at

e in material

irradiation

which affects

ural alloys; in

hness at the

mental grand

and, model,

of materials

crostructural

es advanced

nditions (i.e.

e

e

n

r

e

f

f

e

.

g

y

e

o

s

e

d

l e

s

d

t

t

t

l

n

s

n

e

d

,

s

l

d

.


/15

‘separated effects’) with physics-based models at the appropriate length and time scales: these include

electronic structure calculations, molecular dynamics, kinetic Monte Carlo or cluster dynamics, dislocation

dynamics and crystal plasticity. Dedicated experiments, targeting the identification of specific mechanisms

and guided by models, must be used both for calibration and validation. For fuel materials there is a need for

thermochemical models to understand the complex behaviour of the fission products in gaseous, volatile or

solid form and their physical and chemical interaction with the fuels. The final step for prediction requires a

multi-scale approach that bridges models at different scales, allowing appropriate extrapolation, as illustrated

in Figure 6. Physics-based models that incorporate the relevant length scales are also necessary to correctly

interpret data from miniature tests such as nano-indentation and to apply this understanding to structural

components. Investigations along these lines have been initiated in EERA JPNM subprogrammes 4 and 6,

for structural and fuel materials, respectively.

Grand Challenge 3: Development of new materials with superior thermo-mechanical properties and radiation-resistance or, in general, nuclear-relevance, in partnership with industry for a faster industrial upscaling.

Future advanced reactors will rely initially to a large extent on proven technology and commercially available

structural and fuel materials, e.g. austenitic and ferritic-martensitic steels or nickel-based alloys, and MOX

fuels, respectively. Their qualification and codification is already a challenge. However, to safely exploit the

full potential of nuclear reactors by, for instance, achieving higher burn-ups or higher operating temperatures,

or by using these reactors to burn minor actinides, new materials need to be developed. Promising

structural materials, already used in other sectors, also need to be adapted for nuclear applications. Two

classes of structural materials for fuel claddings are included in EERA JPNM: high-temperature resistant

steels, mainly oxide-dispersion strengthened (ODS), but also improved by tuning composition and thermo-

mechanical treatments, which are addressed in subprogramme 2, and silicon-carbide composites (SiC/SiCf),

which are considered in subprogramme 3. Exploratory work on MAX phases ceramic-metallic composites

(cermets), which may have mechanical properties akin to metallic alloys, is also included in subprogramme

3. Besides these three classes, modified surface layers and coatings for the mitigation of structural material

degradation are under evaluation in subprogramme 1 and have shown promising results. However, there is

no overall or globally ideal material and there is always a trade-off between the material properties. Materials

with tailored properties would be an ideal solution, which may come from functionally graded materials. The

potential for future nuclear applications of the newly discovered high-entropy alloys that combine high

ductility and toughness might for example also be considered.

To exploit the features of the fast reactor technology, the ‘driver’ fuels need to be designed through

incremental innovations (geometry, enrichment, etc.) on mixed oxide fuel or more radical innovation based

on carbides or nitrides. Advanced fuels to achieve minor actinide burning represent a high degree of

innovation. These are investigated in the subprogrammes 5 and 6.

There is no established industrial production for the above mentioned structural materials that allows their

manufacturing according to current nuclear specifications and therefore their widespread use; even less is

there an established industrial production of nuclear components made with these materials. In general, to

obtain materials with the desired properties, which are suitable for industrial up-scaling, there is a need for

an advanced "Design and Control" approach. This implies pro-active interaction of the nuclear materials


/15

community, with material producers and the development of advanced models that can reach the required

level of industrial usability and coupling with industrial procedures. For ceramics and composites there is an

existing and large industrial market in the aerospace domain which can be exploited in this context.

In order to allow the introduction of new materials onto the engineering scene, to either reduce the cost or

dramatically increase the performance of components, new and emerging technologies such as 3D-printing

or hot isostatic pressing (HIP) and modification of component design, for instance to achieve minimal

amounts of joining, should be considered. In general, the speed of up-scaling from laboratory to industrial

production needs to be faster for all nuclear materials, both structural and fuel. This is primarily a task for

industry, but a close collaboration between industrial partners and the research community is of mutual

benefit where research could provide supporting models and design, and also perform and evaluate tests.

5. Towards an integrated European Nuclear Materials

Programme

The development, design and construction of sustainable nuclear energy reactors, according to the GenIV

paradigm, is a very challenging endeavour that requires large financial and human resources. However, it is

a necessary undertaking due to the importance of sustainable nuclear energy in guaranteeing a constant,

reliable, abundant and cost-effective production of low-carbon energy. Given the grand challenges described

above, this also applies to materials and components. However materials research is also to a large extent a

cross-cutting issue not only for the different reactor system concepts and generations of nuclear reactors

themselves, but also other high-efficiency low-carbon energy technologies. This is the reason why the EERA

JPNM was formed: to integrate the materials research that is conducted by the national research

organizations, for nuclear energy but not only, into a truly European programme, to form a vital asset to be

exploited. This implies making efficient, coordinated, optimized and wise use of the resources, human and

financial, that the different Member States have and can offer and share. However, it is currently unlikely that

the funding that Member States can provide for nuclear materials research will increase and a careful

analysis of the current situation in terms of financial approaches and realistic opportunities [9] has made it

evident that the JPNM funding for GenIV research and coordination unavoidably requires Euratom support

as well. It is essential to secure the current level of funding and make the best use possible of it by the

combination of two schemes:

1 a co-fund action with consistent Euratom participation, such as a European Joint Programme on

nuclear materials, as a way to at least earmark, and possibly leverage, funds for the EERA JPNM

also from the Member States;

2 a pro-active role on the EERA JPNM side in coordinating research activities and promoting the

efficient use of human resources and facilities throughout Europe, by limiting duplication and

enhancing integration, while remaining in constant dialogue with Member States and European

Commission.

MatISSE – D.5

Since its o

alignment o

still remains

As sketched

The first int

of the Seve

common ro

of common

elaboration

scientific ad

researchers

expertise an

Challenges

developing

establishing

holder grou

schemes as

obviously in

nuclear pla

ranging from

materials p

platforms (e

The ambitio

linked and c

researchers

area in term

5.21a – Fina

official start

of national ac

s one of the m

d in the EER

Fig

tegration step

enth Framew

admaps for

projects via

of joint pilo

dvisory pool.

s in the ident

nd by identif

to be face

mutual trus

g criteria for

ups that are

s a first step

nclude desig

tforms, such

m other EER

platforms suc

e.g. ESTEP f

on is to reac

can be pursu

s working on

ms of their co

al version o

in Novembe

ctivities into

main items o

RA position pa

gure 7 – Step

p has been t

work Program

structural an

monitoring o

ot projects, t

The establis

tification of th

fying gaps a

ed. It is cruc

st in order t

priorities, vi

e to be used

p to effective

gners and n

h as SNETP

RA JPs wher

ch as EMIR

for steel man

ch the final s

ued in parall

similar subje

oordination o

on 19/12/20

er 2010, the

a consistent

on its agenda

aper [10], int

ps towards fu

taken. Sever

mme's MatIS

nd fuel mater

of activities, t

to be interna

shment of co

he content of

nd setting o

cial that res

to learn to

a closer link

d as consult

sharing of f

nuclear comp

P and NUGE

re materials

RI; materials

nufacturers) o

teps of integ

el. The "The

ects at differe

of work and s

14..

/15

e EERA JPN

t joint progra

a.

tegration is a

ull research i

ral intermedi

SSE integrat

rials, the ma

the updating

ally as well

ommon work

f the work, b

bjectives tog

searchers kn

work togeth

ks with the i

tants, while

facilities and

ponent man

ENIA. They

under extre

s manufactu

or by the dire

gration by 20

ematic virtual

rent locations

sharing of da

NM has bee

amme; for th

a stepwise pr

ntegration at

iate steps ar

ted research

apping of exp

of sub-prog

as external

k plans pivot

by taking into

gether, within

now each o

her. The nex

ndustrial cou

exploring a

infrastructur

nufacturers in

also include

me condition

rers need a

ect involveme

020. Steps 4

l research ce

s establish a

ata and comp

en very suc

e reasons a

rocess (see F

t European le

re being take

h project, na

perimental fa

ramme Desc

ly and trans

ts around int

account the

n the framew

other and ea

xt steps will

unterparts, b

and setting u

res. In terms

nvolved in E

e other ene

ns are an iss

also to be i

ent of specifi

4 and 5 (Figu

entre" refers

very close c

putational res

ccessful in t

above, furthe

Figure 7):

evel

en now, with

amely the el

acilities, the

criptions of W

sparently rev

tense involve

eir actual cap

work given b

ach other's

l be in the

by the creati

up training a

s of stake-ho

ESNII, as w

ergy material

sue, to indus

ncluded, eit

fic industries.

ure 7) are in

here to a sy

collaboration

sources, wh

erms of the

er integration

h the support

aboration of

identification

Work and the

viewed by a

ement of the

pabilities and

by the Grand

capabilities,

direction of

on of stake-

and mobility

olders, these

well as other

ls initiatives,

strial energy

ther through

.

n fact closely

ystem where

in a specific

ile utilising a

e

n

t

f

n

e

a

e

d

d

,

f

-

y

e

r

,

y

h

y

e

c

a


/15

delocalised set of accessible and integrated facilities. Necessarily, this occurs via promoting interaction

between researchers to learn how to work together effectively, as outlined above. Moreover, an integrated

approach to the collaborative use of facilities, with the support of the management of the different research

organizations, is a very important step. Ultimately the goal would indeed be that experimental facilities

should be shared in an optimal way, according to a scheme that ensures fair costs and distribution of

intellectual property rights, protecting acquired know-how. Sharing of data respecting intellectual property

rights and according to commonly accepted fair rules is another crucial and very difficult step towards

integration. To start with, data generated in common projects can be shared through a common web-based

database, but for a true integration, mechanisms need to be found to share data generated outside common

projects, while ensuring that the data owner retains the full control of who can access these data. These

steps towards full integration are, however, totally impossible without a strong commitment from the

management of the research organizations, and therefore Member States that actually own and fund

the organizations, as well as from the European Commission. There must be expressed willingness at

Member State level to proceed along this integration, overcoming all potential legal and administrative

difficulties. Crucially, there must also be a commitment to support the process financially and, even more

importantly, the research that the virtual centre would perform. The latter requires, as anticipated, that the

European Commission offers a suitable instrument that should not only promote coordination and integration

involving actively the Member States, but also provide adequate funding for the research work.

6. Risks The path towards integration sketched in the previous section constitute the goal of the EERA JPNM and is

currently the only sensible means to address the Grand Challenges described above, that constitute the

scientific objective of the JPNM. However, even with all the integration effort and after securing available

funding, there remains risks that the Grand Challenges might not be appropriately addressed. First and

foremost, there is a problem in connection with the costly facilities for the exposure of materials to conditions

of relevance for the reactors that are crucial for their qualification of the materials. These facilities are scarce

or do not exist, yet. Despite efforts to develop models and new paradigms that make laboratory data relevant

for real conditions, their scarcity or the need for additional funding for their construction or upgrade may be a

serious hindrance to addressing especially the first of the Grand Challenges. The political will to invest in

nuclear energy and pursue the certainly costly, but equally certainly rewarding in the long-term, goal of Gen

IV nuclear systems, is another unknown. It is clear that, if within the next 10-15 years no prototype reactors

such as Myrrha or Astrid is commissioned, it is unlikely that the goal of GenIV nuclear systems will be

reached on time with respect to current goals for counteracting climate change and ensuring more

sustainable energy production.


/15

Appendix: milestones and high-level deliverables

Milestones towards integration Integration level

Tentative date

Roadmaps for structural materials and fuel 2 2015

EERA JPNM Description of Work for 2016 – 2020 2 2015

Establishment of Scientific Advisory Group and End-Users group 2 2015

Review of EERA JPNM 2011-2015 2 2016

EURATOM projects or co-fund actions based on EERA JPNM DoW 2016-2020

3 2016-2017

Deployment Plan EERA JPNM 3 2017

Collaboration Agreement with other materials networks 2 2017

Establishment of Virtual Centers 3 2018

Collaboration Agreement for sharing of facilities 3 2018

Management of Common projects with funding from Member States and EC. 4 2020

High level Deliverables Qualification of structural and fuel materials suitable for the construction of efficient and safe Gen IV reactor systems, with focus on the ESNII demonstrators and prototypes, in particular Myrrha and Astrid. Pre-normative research recommendations for component design rule modifications in support to ESNII’s demonstrators and prototypes. Standardized test procedures to codify and disseminate results of R&D&I activities on advanced materials. Path towards industrial production scaling of innovative materials for continuously increased safety and efficiency of Gen IV reactor systems Robust understanding of main physical mechanisms determining the response of materials to Gen IV reactor operating conditions and relevant models.

References

1. The European Strategic Energy Technology Plan, SET-Plan, towards a low-carbon future, European Commission, http://ec.europa.eu/energy/publications/doc/2010_setplan_brochure.pdf

2. Eurostat electricity production in the EU http://epp.eurostat.ec.europa.eu/statistics_explained/index.php/Electricity_production_and_supply_statistics

3. World Energy Outlook Special Report 2013, International Energy Agency, Paris, 4. Energy Technology Perspectives 2014 - Harnessing Electricity's Potential, International Energy

Agency, Paris 5. Deliverable D10.2 - RS2b “Final report on sustainability assessment of advanced electricity supply

options”, NEEDS project. http://www.needs-project.org/docs/NEEDS_RS2b_D10-2%20-%20Final%20Report.pdf

6. ESNII Concept Paper – October 2010 http://www.snetp.eu/www/snetp/images/stories/Docs-ESNI/ESNII-Folder-A4-oct.pdf

7. ESNII European Sustainable Nuclear Industrial Initiative Implementation Plan 2013-15 (available on www.snetp.eu for members), March 2013

8. STRATEGIC ENERGY TECHNOLOGY PLAN, Scientific Assessment in support of the Materials Roadmap enabling Low Carbon Energy Technologies: Nuclear Energy, European Commission, EUR 25180-11

9. I. Aho-Mantila, U. Ehrnsten, L. Malerba, "Reflection of the EERA financial approach to IRP/JP on Nuclear Materials", FP7/MatISSE, Deliverable D1.33 (Dec. 2014).

10. EERA position paper, 2014.

EERA JPN M Visi on Repport - fp7-matisse.eu · Project A. Mich 06/02/2 ents Coordinator aux, CEA...

Documents

Transcript of EERA JPN M Visi on Repport - fp7-matisse.eu · Project A. Mich 06/02/2 ents Coordinator aux, CEA...