astrid core design objectives, design approach, and · pdf fileastrid core design objectives,...

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IAEA TECHNICAL MEETING ON INNOVATIVE FAST REACTOR DESIGNS WITH ENHANCED NEGATIVE REACTIVITY FEEDBACK FEATURESVienna - 27-29 February 2012 1

ASTRID core

Design objectives, design approach,

and R&D in support

G. Mignot - ASTRID Project

[email protected]

N. Devictor - SFR R&D Project

[email protected]

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Content

• ASTRID project

• Core design objectives

• R&D program in support to the core design

That talk is completed by the following talk « PRE-CONCEPTUAL DESIGN STUDY OF ASTRID CORE »

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3

Advanced sodium technological reactor for industrial demonstration

� Industrial prototype (step before a First Of A Kind )

� Integrating French and international SFRs feedback

� A Generation IV reactor

� Safety :

� Level at least equivalent to GENIII systems

� + lessons learnt from Fukushima accident

� With significant improvements on sodium specific is sues

� Operability :

� Validate on the long term an ambitious load factor

� Significant improvements concerning ISI&R

� Ultimate waste transmutation :

� Continue experimentation of minor actinides transmut ation, up to large scales if so decided

� An investment cost under control

� Irradiation services and testing of longer term opt ions

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ASTRID design studies�SFR industrial prototype 600 MWe�Irradiation tool

Core fabrication workshop�MOX fuel�A few tons per year

Full scale component testing� Refurbishment/Realization of largetest sodium loops� Refurbishment of zero power reactorMASURCA + R&D

(including fuel cycle)

Feasibility study for minor actinides bearing experimental fuel fabrication

Severe accidents experimentalprogram

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The ASTRID program

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2009 2010 2011 2012 2013 2014 2015 2016 2017

Decision to continue

Preliminary choice of options

Schedule for ASTRID and associated facilities

Decision to build

Pre-conceptualdesign

Conceptualdesign

Basic

design

Fuel loading

Detaileddesign

& Constructi

on

ASTRID

Facilities

Position Report on minor actinides partitioning and transmutation

Core manufacturing

workshop (AFC)

MA bearing fuels fabrication facility

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Pre-conceptual and conceptual design 2010-2014

�Mid of 2010 : preliminary selection of ASTRID charac teristics for launching the pre-conceptual design

�The pre-conceptual design will be delivered by the end of 2012

�The pre-conceptual design will consider some open o ptions. Innovation and technological breakthroughs will be favored, while maintaining risk at an acceptable level.

�During the pre-conceptual design phase, start of th e interactions with the Safety authorities on safety objectives an d orientations.

�The conceptual design will be delivered by the end of 2014

�During the conceptual design phase, the ASTRID desi gn choices will be finalized and the Safety Option File will b e submitted.

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ASTRID : preliminary design choices / open options

� 1500 MWth, ~600 MWe reactor

� Pool type reactor

� With an intermediate sodium circuit

� Preliminary strategy for severe accidents (core catcher…)

� Oxide fuel for starting cores

� Transmutation capability

� High level expectations in terms of safety demonstration

� In sodium fuel handling

� …

Main features Open options

• Energy conversion system– Reference : water/steam– Alternative : N2

• Number of loops• Devices to eliminate severe accidents

(i.e. 3rd shutdown level)• Corium catcher technology• SGs materials and technology• Innovative technologies for Na fires

detection and extinction• I&C• …

• Carbide Fuels• SiC-SiC Materials• …

Many of these options will be decided during the pre-conceptual design up to 2012, some will remain open and be

decided during the conceptual design.

Innovative options

to be tested

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ASTRID core design is mainly guided by safety objectives :

1. Prevention of the core meltdown accident

To prevent meltdown accidents

-by a natural behavior of the core and the reactor (no actuation of the two shutdown systems)

-with adding passive complementary systems if natural behavior is not sufficient for some transient cases

2. Mitigation of the fusion accident

To garantee that core fusion accidents don’t lead to significant mechanical energy release, whatever ini tiator event

-by a natural core behavior

-with adding specific mitigation dispositions in case of natural behavior is not suffficient

Core design approach

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● Natural behavior favorable for transients of unprotected loss of flow and loss of heat sinkTarget criteria : no sodium boiling for a ULOSSP transient

● Sodium void effect minimizedTarget criteria : Na void effect < 0

● Natural behavior favorable for a complete control rod withdrawal (with no detection) Target criteria : no fuel fusion

● Improved performancesTarget criteria : Cycle length ≈ 480 efpd, High fuel burnup, and breeding gain ≈ 0

+ Core design is extrapolable to higher power

Core design objectives

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Feedback experience from SPX and EFR :�To reduce the fuel reactivity loss per cycle�To reduce the sodium void worth

2009 : heterogeneities added to SFRv2 core

�Sodium void worth strongly reduced

�Quantification of the potential benefit from safety point of view is on going

Absorbing protection

Sodium plenumzone

Outer fissilezone

Inner fertile zone

Upper inner fissile zone

Lower inner fissile zone

Fertile blanket

Neutronic protection

Absorbing protection

Sodium plenumzone

Outer fissilezone

Inner fertile zone

Upper inner fissile zone

Lower inner fissile zone

Fertile blanket

Neutronic protection

CFV core

2008 : concept with larger pin and smaller-diameter spacing wire- Increase of the fuel fraction

- Low reactivity loss during cycle

-Decrease of the Na fraction ⇒ lower Na voiding effect

��Improvement on control rod withdrawal

SFRv2 core

Core designs options : SFRv2 and CFV concepts

Fuel rod diameter increased

Spacer diameter reduced

(Patent)

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Information on R&D done in support to

ASTRID core design

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Homogeneous SA

R&D in support to design - Subassembly

Design for « stable boiling » in case of ULOSSP

Heterogeneous SA

Mechanicalbehavior

Thermal gradient

Example of CFV

Plug

VES

Fertile

Fissile

CAI

Plug, etc.

Na

PNS

VEI

Fissile

PlugVES

CAI

Plug, etc.

PNS

Na

Fissile

VEI

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• Materials for first cores– Clad : 15/15Ti / AIM1– Hexcan : EM10 - 9Cr – 1 Mo

CEA ODS tube

• R&D on cladding– Smaller diameter for spacing wrapper

⇒ Need for low swelling materials : R&D on F/M ODS steels

– Improvment of performance of fuel (expertise of irradiated SA in Phenix)

• R&D on thermomechanical behavior of fuel material for high temperatures→ Assessment for the possibility to use a positive effect on reactivity from the “pad flowering”

Enfoncement élastoplastique des plaquettes d'un ass embage CFV V0 à 800°C

0

500

1000

1500

2000

2500

3000

3500

4000

4500

5000

0.00 0.05 0.10 0.15 0.20 0.25 0.30 0.35

Enfoncement plaquette en mm

For

ce m

oyen

ne s

ur p

laqu

ette

s op

posé

es e

n N

assemblage 31-29 calcul élastique

assemblage 31-29 calcul plastique parfait (s0 = 90 MPa)

assemblage 31-29 calcul plastique parfait (s0 = 45 MPa)

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Review of design options for pad and

Foreign options

Objective to detect abnormal movement and to prevent compaction leading to insert almost 1$

R&D on Fluid Structure interactions

+ cooperation with IGCAR

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In case of a beginning of sodium boiling at the top of fissile area, we would like to demonstrate that the sodium boiling could be stabilized ⇒ R&D on SA design, on modeling

+ Experimental support

With sodium ?

Water/gas : SENSAS facility

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R&D in support to design - Absorbers

Development of 3rd

passive system independent of control rods

SEPIA(patent)

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Decay heat removal (CATHARE 2.5 + TrioU_MC2)Neutronics (PARIS/ERANOS currently)

Design of SA and absorbers (PLEIADES)

⇒ Development of coupled simulation ⇒ better understanding of margins⇒transients

Simulation

Mechanical behavior of bundle and hexagonal tube(HARMONIE, CAST3M…)

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CFD

« System code + CFD »(development + validation)

System code: Cathare

Simulation

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Core degradation

Development and Validation of Severe Accidents codes

(CABRI, JAEA EAGLE program…)

Applications in support to SFRv2 – CFV comparison

SAS4A / SAS-SFRSIMMER III/IV

Simulation

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Inlet and outlet core temperature∆T, CRW(TIB ?)

TC, optical fiber, flowmeter

Inlet and outlet core flowrate

TIB, loss of flow

Surveillance ciel de pileGaseous FP Clad failure

Localisation in gazGaseous FPIonisation chamber,

Spectro γ, (CRDS)

Chambre d’ionisation, Spectro γ, (CRDS)

Neutronic monitoringFonctionnement, CRW

High Temperature FissionChambers with largedynamics

Clad Failure Detection

in Na Open CF, BTI

HTFC / IHX

Clad failure Localisation in Na

FP neutronic detection

FC with B

US telemetry under NaCore movment,(Temperature)

Acoustic DetectionAbnormal noise (TIB?)

Active Acoustic Det.Gas rate

SONAR, TUSHT…

CoreCFV

InnovativeLine of Defense A( ) R&D

Surveillance and Protection

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Development of experimental facilities

TH mock-up

CORRONA

CHEOPS - SA qualification

RefurbishmentMASURCA

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� 2 axis are studying :

� Homogeneous recycling → GenIV GACID Program

� Heterogeneous recycling → CCAm

� Prototyping irradiations for acquiring knowledge

on gas behavior (He…), …

→ MARIOS (in HFR reactor from March 2011 to April 2012)

→ DIAMINO in OSIRIOS from mid of 2012

CINNA – GGP R4G 12/10/11

Transmutation

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R&D: co-operations

� EDF and AREVA

� Part of the R&D is supported by several internation al co-operations

� European co-operations

� EC programs as for example EERA, PCRDT (CP-ESFR, ADRIANA, GETMAT, FAIRFUELS, SARGENIV, ASAMPSA2, THINS, MATTER, etc.)

� CEA SRC (Swedish Research Council) agreement

� Rolls-Royce

� KIT, ITU, ENEA, PSI, …

� IAEA

� by contribution of several CRP, as for example on some PHENIX End Of Life Test, passive systems,

� and also INPRO

� GIF (CD&BOP, Safety & Operation, GACID…)

� Co-operations with IGCAR, JAEA, US DOE, CAEA, Russia, KAERI

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Thank you for your attention

1988-1998

1985 - 1998

1973 - 2010

ASTRID

Commercial reactor

1967 - 1983

RAPSODIE

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