1. 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 Genova

2. Will touch the following points:
INTRODUCTION
The presentation intend to give an overall status of GIF activities and provide some information about LFR projects/events/news in
Will touch the following points:
Activities and status of the GIF-LFR-PSSC
The three LFR reference concepts
Some recent LFR News

3. Current Status of LFR PSSC
Provisional System Steering Committee (PSSC) was formed in 2005
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
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

4. Current Activities of LFR-PSSC
The new PSSC met in Pisa, Italy in April, 2012
Representatives from EU (Alemberti), Japan (Takahashi) and Russian Federation (Smirnov)
Additional participant from US (Smith) and OECD/NEA (Toyama)
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

5. Current Activities of LFR-PSSC
Working meeting of the PSSC : November, 2012 in Tokyo, Japan
Discussion on position paper and LFR SRP
Preparation of GIF Symposium paper and presentation (Craig Smith)
Russian representative declared two FR line development: LFR and SFR
Korea representative will be invited to the next meeting as observer
Seminar on LFR at Tokyo Institute of Technology
Difficult to proceed to SA signature given the present situation (Japan - Fukushima), decision to continue efforts to enlarge LFR MoU signatures

6. LAST GIF-LFR-PSSC meeting in Paris 7-8 March 2013
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 EURATOM
Minoru TAKAHASHI JAPAN
Valery SMIRNOV, Anton UMANSKIY RUSSIA
Observers:
Craig SMITH, James SIENICKI, Anton MOISSEYTSEV - USA
Il Soon HWANG, Myung Hyun KIM KOREA
Qunying HUANG, Ming JIN, Yican WU, Tao ZHOU  - CHINA
Secretariat:
Shin’ichi TOYAMA OECD/NEA

7. LAST GIF-LFR-PSSC meeting in Paris 7-8 March 2013
Current Activities of LFR-PSSC
LAST GIF-LFR-PSSC meeting in Paris 7-8 March 2013
Summary of main points of discussion:
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

8. The European Lead-cooled Fast Reactor ELFR
Steam Generator
Reactor Vessel
Safety Vessel
DHR dip cooler
Fuel Assemblies
Primary Pumps
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
Key technical attributes include FA extension to cover gas
Passive DHRs: Secondary side isolation condensers + dip coolers

9. The BREST-OD-300 Lead-cooled Reactor1 2 3 4 5
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
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

10. The Small Secure Transportable Autonomous Reactor (SSTAR)
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.

11. LFR Infrastructure in Europe supporting the LFR Road Map
34 Exp. Facilities in Operation or under Construction in 10 European Research Institutions
1 ATHENA (Advanced Thermal Hydraulic Experiment for Nuclear Application)
2 CICLAD (Corrosion Induced by the Circulation of a LeAD alloy)
3 CIRCE (Circolazione Eutettico)
4 COLONRI I & II (Convectional Loop)
5 CALLISTO (Static LM embrittlement)
6 COMPLOT (COMPonent Loop Tests)
7 CORELLA (Corrosion Erosion Test Facility for Liquid Lead Alloy)
8 CORRIDA (Corrosion in Dynamic Alloys)
9 COSTA (Corrosion test stand for stagnant liquid lead alloys)
10 CRAFT (Corrosion Research for Advanced Fast reactor Technologies)
11 CRISLA (Creep-to-Rupture Tests in Stagnant Lead Alloys)
12 ELEFANT (Experimental LEad FAcility for Neutron production Targets)
13 E-SCAPE (European SCAled Pool Experiment)
14 FRETHME (Fretting Tests in Heavy Liquid Metal)
15 HELENA (HLM Loop for small components testing)
16 HELIOS3 (Heavy Liquid Oxygen conditioning System 3 )
17 KALLSTARR (KALLA Steam Generator Tube Ruprture Facility)
18 LECOR (Lead Corrosion)
19 LEVUSE (LBE Vessel for UltraSonic Experiments)
20 LIFUS 5 (Heavy liquid metals interaction with water)
21 LIMETS1 (Liquid Metal Embrittlement Testing Station 1)
22 LIMETS2 (Liquid Metal Embrittlement Testing Station 2)
23 LIMETS 3 (Liquid Metal Test Facility )
24 LINCE (forced convection loop)
25 LISOR Lead-Bismuth Loop
26 NACIE (Natural Circulation Experiment)
27 OSCAR (Oxygen Sensor Calibration Rig)
28 RHAPTER (Remote HAndling Proof of principle Test Experimental Rig)
29 SCC at JRC (Lead loop for SCC testing at JRC-IE, Petten)
30 SLEEVE (Small Lead Bismuth Eutectic Evaporation experiment )
31 STELLA (Standard Technology Loop for Lead Alloy)
32 TALL (Thermal-hydraulic ADS Lead-bismuth Loop)
33 TELEMAT (Test Loop for Lead Material testing)
34 THEADES (Thermal-hydraulics and ADS Design)

12. 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 – 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

13. 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/ – LEADER meets Safety Authorities and TSOs Meeting Organized by JRC

14. 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 expected end 2020

15. 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.

16. 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 lead-bismuth.
4 ESNII projects: ASTRID (SFR), MYRRHA(ADS-LBE), ALFRED (LFR), ALLEGRO (GFR)

17. 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;

18. 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

19. Thank you for your attention