Transcript PR&PP GIF User Workshop Presentation

Extract from the presentation to GIF/INPRO meeting on
Lead-cooled Fast Reactor (LFR)
Progress and Status
Prepared by
Alessandro Alemberti - EURATOM, Italy
Minoru Takahashi - TITEC, Japan
Valery Smirnov - NIKIET, Russia
Craig Smith NPS, USA (Observer)
+ some recent news
6th LEADER PCC meeting
May 9th 2013 - Genova
INTRODUCTION
The presentation intend to give an overall status of GIF activities
and provide some information about LFR projects/events/news
in 2012-2013
Will touch the following points:
Activities and status of the GIF-LFR-PSSC
The three LFR reference concepts
Some recent LFR News
Slide 2
Current Status of LFR PSSC
• Provisional System Steering Committee (PSSC) was formed in 2005
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Members included EU, US, Japan and Korea
Prepared initial draft LFR System Research Plan (LFR-SRP)
Systems included a large central station design (ELSY) and a small transportable system
(SSTAR)
• In 2010, an MOU was signed between EU and Japan causing a reformulation
of the PSSC
• In 2011, the Russian Federation added its signature to the MOU
• In April, 2012, the reformulated PSSC met in Pisa and began the process of
revising the LFR-SRP
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Members are signatories of the MOU: EU, Japan and Russia
US invited to participate as observer
• The new PSSC envisions various updates to the central station and small
reactor thrusters while adding a mid-size LFR
Slide 3
Current Activities of LFR-PSSC
The new PSSC met in Pisa, Italy in April, 2012
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Representatives from EU (Alemberti), Japan (Takahashi) and Russian Federation
(Smirnov)
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Additional participant from US (Smith) and OECD/NEA (Toyama)
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Actions of the meeting:
Decision to expand the initiative to three thrusts (large, medium and small
LFRs)
Agreement to prepare PSSC position paper describing the basic advantages and
remaining research challenges of the LFR
Invitation to US representative to continue in observer status
Initiation of a significant revision to the SRP to be completed by March 2013
Preparation of LFR GIF Road Map
Slide 4
Current Activities of LFR-PSSC
Working meeting of the PSSC : November, 2012 in Tokyo, Japan
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Discussion on position paper and LFR SRP
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Preparation of GIF Symposium paper and presentation (Craig Smith)
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Russian representative declared two FR line development: LFR and SFR
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Korea representative will be invited to the next meeting as observer
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Seminar on LFR at Tokyo Institute of Technology
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Difficult to proceed to SA signature given the present situation (Japan Fukushima), decision to continue efforts to enlarge LFR MoU signatures
Slide 5
Current Activities of LFR-PSSC
LAST GIF-LFR-PSSC meeting in Paris 7-8 March 2013
Enlarged Participation to the meeting:
Members;
Alessandro ALEMBERTI, Didier HAAS
Minoru TAKAHASHI
Valery SMIRNOV, Anton UMANSKIY
- EURATOM
- JAPAN
- RUSSIA
Observers:
Craig SMITH, James SIENICKI, Anton MOISSEYTSEV
Il Soon HWANG, Myung Hyun KIM
Qunying HUANG, Ming JIN, Yican WU, Tao ZHOU
- USA
- KOREA
- CHINA
Secretariat:
Shin’ichi TOYAMA
- OECD/NEA
Slide 6
Current Activities of LFR-PSSC
LAST GIF-LFR-PSSC meeting in Paris 7-8 March 2013
Summary of main points of discussion:
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Position Paper on LFR up-loaded on GIF web-site
Discussion on new version of System Research Plan – SRP issue 2013
Request by IAEA to open a line of activity on LFR
Request by GIF-RSWG of a white paper on LFR (Alfred ?)
- Presentation of the work performed at MIT of a functionally graded
composite: T91 – Fe-9Cr-1Mo structural + Fe-12Cr-2Si corrosion
resistant layer – co-extruded for cladding and piping.
First results in LBE at 650 °C - corrosion below 5 µm/y.
- Although we are still far from SA signature China and Korea declared
their interest to sign the LFR-MoU.
- Next meeting in Paris November 10-11 2013
Slide 7
The European Lead-cooled Fast Reactor ELFR
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Power: 1500 MW(th), 600 MW(e)
Core diameter, 4.5 m
Core height, 1.4 m
Core fuel MOX (first load)
Coolant temp., 400/480oC
Maximum cladding temp., 550oC
Efficiency: ~42%
Core breeding ratio (CBR) ~ 1
Steam
Generator
DHR dip
cooler
Primary
Pumps
Reactor
Vessel
Safety
Vessel
Fuel
Assemblies
Key technical attributes include FA extension to cover gas
Passive DHRs: Secondary side isolation condensers + dip coolersSlide 8
The BREST-OD-300 Lead-cooled Reactor
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Power: 700 MW(th), 300 MW(e)
Core diameter, 2.6 m
Core height, 1.1 m
Core fuel UN + PuN
Coolant temp., 420/540oC
Maximum cladding temp., 650oC
Efficiency: 42%
Core breeding ratio (CBR) ~ 1
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1
5
1 Core, 2 steam generator, 3 Pump, 4 refueling machine, 5 Reactor Vault
Key technical attributes include concrete Reactor Vault, fuel
reprocessing in dedicated building integrated with the plant
Slide 9
The Small Secure Transportable Autonomous Reactor
(SSTAR)
CLOSURE HEAD
CO2 OUTLET NOZZLE
(1 OF 8)
CO 2 INLET NOZZLE
(1 OF 4)
Pb-TO-CO 2 HEAT
EXCHANGER (1 OF 4)
FLOW SHROUD
RADIAL REFLECTOR
ACTIVE CORE AND
FISSION GAS PLENUM
FLOW DISTRIBUTOR
HEAD
CONTROL
ROD
DRIVES
CONTROL
ROD GUIDE
TUBES AND
DRIVELINES
THERMAL
BAFFLE
GUARD
VESSEL
REACTOR
VESSEL
SSTAR is a small natural
circulation fast reactor of 20
MWe/45 MWt, that can be
scaled up to 180 MWe/400
MWt.
The compact active core is
removed by the supplier as a
single cassette and replaced by
a fresh core.
Key attributes include advanced power conversion system, use of natural
convection cooling and a long-life core in a small, modular system.
Slide 10
LFR Infrastructure in Europe
supporting the LFR Road Map
34 Exp. Facilities in Operation or under Construction in 10 European Research Institutions
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ATHENA (Advanced Thermal Hydraulic Experiment for
Nuclear Application)
CICLAD (Corrosion Induced by the Circulation of a LeAD
alloy)
CIRCE (Circolazione Eutettico)
COLONRI I & II (Convectional Loop)
CALLISTO (Static LM embrittlement)
COMPLOT (COMPonent Loop Tests)
CORELLA (Corrosion Erosion Test Facility for Liquid Lead
Alloy)
CORRIDA (Corrosion in Dynamic Alloys)
COSTA (Corrosion test stand for stagnant liquid lead
alloys)
CRAFT (Corrosion Research for Advanced Fast reactor
Technologies)
CRISLA (Creep-to-Rupture Tests in Stagnant Lead Alloys)
ELEFANT (Experimental LEad FAcility for Neutron
production Targets)
E-SCAPE (European SCAled Pool Experiment)
FRETHME (Fretting Tests in Heavy Liquid Metal)
HELENA (HLM Loop for small components testing)
HELIOS3 (Heavy Liquid Oxygen conditioning System 3 )
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KALLSTARR (KALLA Steam Generator Tube Ruprture
Facility)
LECOR (Lead Corrosion)
LEVUSE (LBE Vessel for UltraSonic Experiments)
LIFUS 5 (Heavy liquid metals interaction with water)
LIMETS1 (Liquid Metal Embrittlement Testing Station 1)
LIMETS2 (Liquid Metal Embrittlement Testing Station 2)
LIMETS 3 (Liquid Metal Test Facility )
LINCE (forced convection loop)
LISOR Lead-Bismuth Loop
NACIE (Natural Circulation Experiment)
OSCAR (Oxygen Sensor Calibration Rig)
RHAPTER (Remote HAndling Proof of principle Test
Experimental Rig)
SCC at JRC (Lead loop for SCC testing at JRC-IE, Petten)
SLEEVE (Small Lead Bismuth Eutectic Evaporation
experiment )
STELLA (Standard Technology Loop for Lead Alloy)
TALL (Thermal-hydraulic ADS Lead-bismuth Loop)
TELEMAT (Test Loop for Lead Material testing)
THEADES (Thermal-hydraulics and ADS Design)
Slide 11
Some LFR NEWS (in a chronological order)
February 2012: MOU between Romania/Italy Organizations
(INR/ANSALDO/ENEA) signed to define the steps and rules to be
followed to form an international consortium for ALFRED.
INR started contacts with Romania Safety Authority
ESNII Conference June 25th 2012 – Bruxelles
Focus on ENSII projects, ASTRID, MYRRHA, ALFRED, ALLEGRO.
Declaration of interest in LFR development by Hungary gov.
representative
INR-ENEA-ANSALDO meeting with DG Regio, June 29th - Bruxelles
A first meeting to identify possibility of access for ALFRED to
infrastructural funds.
ESNII Ex. Board – September 2012
Decision to focus on projects rather then technology.
Decision for prioritization of initiatives, main criteria: availability of
funds + technical considerations
Slide 12
Some LFR NEWS (in a chronological order)
BREST press conference: September 2012, ROSATOM declares
that BREST construction will start soon and the plant will be
operational in 2020 (fuel reprocessing included). Site is in the
TOMSK region where competences on reprocessing is available.
SVBR press release: October 2012, AKME announces the
signature of a MoU for the collaboration of Czech Republic main
companies for SVBR (LBE).
EURATOM-ROSATOM meeting: October 2012 Bruxelles
New BREST Scientific Coordinator – A. Moyssev (IPPE / NIKIET)
ROSATOM confirms commitment for BREST and BN-800
Bi-lateral contacts between LEADER and BREST projects
IRSN report on safety considerations on GenIV reactors available
on Web-site
February 27/28 2013 – LEADER meets Safety Authorities and TSOs
Meeting Organized by JRC
Slide 13
Some LFR NEWS (in a chronological order)
Report on GIF Technology Road map completed (Rev 2013)
will be presented at GIF meeting in Beijing next week
Strong discussion on time frame for demonstration
LFR Road Map updated after specific request of information to
ROSATOM:
SVBR-100 expected operation end of 2018
BREST - OD - 300 expected end 2020
Slide 14
Some LFR NEWS (in a chronological order)
Request from GIF-EG to compile a description of specific
problems related to fuel for the 6 GIF systems.
End date May 15th.
Request from GIF-EG to make comments on IRSN reports on
safety aspect of GENIV reactors.
End of May.
Request from IAEA to include ALFRED into the booklet
description of fast reactors.
Request from IAEA of a description of LFR systems to be
published on IAEA web-site.
Slide 15
The EC Next Step
UPDATE of STRATEGIC EUROPEAN DOCUMENTS
FROM THE DRAFT of the Introduction to “STRATEGIC RESEARCH INITIATIVE
AGENDA” (SRIA) provided to SNE-TP (Sustainable Nuclear Energy –
Technology Platform) by ESNII (European Sustainable Nuclear Industrial
Initiative on Fast Reactors - SFR,LFR,GFR)
With respect to the 2010 technologies evaluation, sodium is still considered as the
reference technology since it has broader technological and reactor operations
feed-back. The Lead Fast Reactor technology has significantly extended its
technological base and can be considered as the shorter-term alternative
technology to sodium.
For the development of the Lead Fast Reactor, maximum synergy of activities will be
sought with the MYRRHA development to optimize resources and planning.
For the LFR demonstrator ALFRED the main focus should be on design activities
typical of a critical reactor connected to the grid, as well as on R&D activities on the
lead coolant, addressing the specific characteristics of lead with respect to leadbismuth.
4 ESNII projects: ASTRID (SFR), MYRRHA(ADS-LBE), ALFRED (LFR), ALLEGRO (GFR)
Slide 16
FROM THE DRAFT of the Introduction to SRIA – ESNII Section
ESNII-systems shall be designed to reach at least the standards of safety,
radiological protection and security put forward by WENRA for new
reactors also targeting the Generation IV goals;
ESNII-systems shall implement a safety approach based on the most recent
standards and best international practices, using experience gained from
past and present nuclear science and engineering
ESNII-systems shall endeavour to minimize radioactive releases to the
environment and doses to the workers in normal and incidental situations
to as low as reasonably achievable;
Societal concerns in relation to nuclear safety and security shall be duly taken
into account in the ESNII-systems design process;
Slide 17
FROM THE DRAFT of the Introduction to SRIA – ESNII Section
ESNII-systems shall be designed to have a high level of implementation of
the concept of Defence in Depth;
ESNII-systems shall be designed to use as much as possible passive
safety systems and inherent safety characteristics.;
ESNII-systems will aim to practically eliminate the likelihood of severe
accidents;
ESNII-systems will be designed to be robust against Fukushima-accident
initiators;
Security shall form an integral part of the ESNII-systems design.
ESNII-systems shall aim at further improving the economic competiveness
and operability of nuclear energy in a future European energy mix
Slide 18
Thank you for your attention
Slide 19