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GIF – IAEA interface meeting - March 18-19 2019 Vienna

GIF Lead-cooled Fast Reactor Activities

Alessandro Alemberti (EURATOM / Ansaldo Nucleare)Kamil Tuček (EURATOM / EC JRC)

on behalf of GIF LFR

provisional System Steering Committee

Outline

• The Lead cooled Fast Reactors in GIF

• Activities of the LFR provisional SSC (pSSC)

• Status of LFR R&D activities in MoU Countries

MoU Signatories Observers

The Lead-cooled Fast Reactor in GIF

EURATOM

Japan

Republic of Korea

Russian Federation

United States of America

People's Republic of China

signed on 8 February 2018

GIF LFR provisional System Steering Committee

SSTAR(USA)

Small-sized, battery type reactor with long core life

BREST-OD-300(Russia)

Medium-sized, «pools-in-loop» type reactor with associated closed fuel cycle facilities

(Europe)

Large-sized, integral type reactor for closing of the fuel cycle

Reference systems for the GIF LFR pSSC activities

ELFR

The Lead-cooled Fast Reactor in GIF

• LFR System Safety Assessment (SSA):SSA was thoroughly revised taking into account comments received from RSWGThe updated clean version has been sent to EG by RSWG on March 7, 2019

• LFR Safety Design Criteria (SDC):SDC were thoroughly revised following comments received from RSWG Document was also updated following the IAEA SSR 2/1 (rev. 1) version (2016)Updated version is expected to be transmitted to RSWG before summer

• LFR Safety Design Guidelines (SDG):LFR SDG will be developed after SDC finalization

• Contribution to the 2018 update of the GIF R&D Outlook Report

• White Paper on the LFR PRPP aspects is currently being updated

• LFR pSSC active in the GIF Task Force on Research Infrastructures

pSSC Main activities

Status of LFR R&D activities

in MoU Countries/Entities

Japan

Material compatibility Corrosion-Erosion, Oxidation corrosion, Fretting corrosionDevelopment of corrosion

resistance materialsAl-rich steel, Ceramic materials, Ceramic coatingsDevelopment of oxygen control

systemOxygen sensor, Gas injection system, Mass exchanger, Electrochemical impedance spectroscopy

Severe corrosion-erosionIn flowing Pb-Bi

Oxygen sensor

Fretting corrosion

High-purity Pb alloy

Excellent corrosion resistance of Al-rich steel in flowing Pb-Bi

Japanese activity centered onHeavy liquid metal technology

• Power: 700 MWth, 300 MWe• Core diameter: 2.4 m• Core height: 1.1 m • Core fuel: (U+Pu+МА)N• Fuel inventory: 20.6 t• Coolant temperature

(inlet/outlet): 420ºC/535ºC• Maximum cladding

temperature: 650ºC• Efficiency: 43.5%• Core breeding ratio (CBR): ~ 1

Key technical attributes include multi-layer metal-concrete reactor vessel, and co-located fuel manufacturing and reprocessing

The BREST-OD-300 Lead-cooled Fast Reactor

Main Circulation Pump Steam

GeneratorVessel

Core

Manifold systemsof emergency cooling

Russian Federation

GIF Road Map based on BREST schedule/advancement

BREST-OD-300:Further stages of the technology implementation

Filling with coolant, passivation of the circuit, the running of primary circuit equipment

Physical start. Formation of the core starting load for obtaining equilibrium mode

Creation and testing of prototypes of large equipment

Power start. Achievement of launchers and power modes

Completion of substantiating R&D required for reactor commissioning

Manufacture of reactor equipment and core elements

Experimental and industrial operation

Justification of fuel and core elements

▪ Licensing of the facility construction in the technical supervision

Russian Federation

The detailed design of the BREST-OD-300 reactor facility has been justified using small- and medium-scale test benches and test sections, as well as validated software tools, and the design has met the key parameters specified and the licensing procedure is being carried forward. The next stages include completion of planned R&D in parralel with the construction (justification of fuel and core elements, creation and testing of prototypes of large equipment, additional validation of codes) and operation of a power unit as a part of the pilot and demonstration energy complex.

BREST-OD-300:Further stages of the technology implementation

Filling with coolant, passivation of the circuit, the running of primary circuit equipment

Physical start. Formation of the core starting load for obtaining equilibrium mode

Creation and testing of prototypes of large equipment

Power start. Achievement of launchers and power modes

Completion of substantiating R&D required for reactor commissioning

Manufacture of reactor equipment and core elements

Experimental and industrial operation

Justification of fuel and core elements

▪ Licensing of the facility construction in the technical supervision

Russian Federation

12.10.2018_No203 / News in BriefRussia’s Brest-OD-300 Scheduled For Operation In 202612 Oct (NucNet): The Brest-OD-300 demonstration lead-cooled fast-neutron reactor unit under construction in Russia is scheduled to begin commercial operation in 2026, state nuclear corporation Rosatom said.

Republic of Korea

New Focus • Demonstrate load-following capability for marine propulsion & hybrid power• Materials R&D to eliminate refueling during MMR lifetime (>30 years)

Physical modelestablishment • URANUS load-follow has been modeled by MARS-LBE and TraSSAM

Experimental investigation

Numerical validation and

modeling

Analytical model

development & assessment

• PILLAR, URANUS mock-up, is designed with hydrodynamic scaling law (1/200)• System integral behaviors especially in pool configuration are tested

• MARS-LBE is validated with natural circulation experimental results on PILLAR for steady state and transient conditions

• TraSSAM, a reactor dynamics simulation model for passive SMR has been developed and validated against MARS-LBE

• Transient analysis results show that URANUS, the passive LBE-cooled SMR can follow 50% power increase in 4 minute with full stability

Experimental investigation

Further study on passive SMR

simulation model

• Comparison of very fast transient experiment and model• Ramp rate vs. nuclear fuel and steam generator water-level stability: EdF PWR

power changes 80% in 30% (the worst case limit for URANUS)

• Balance of plant (BOP) design and Fuller Simulation • Al-containing Corrosion-resistant Alloy under Development• Pilgering of Functionally Graded Composite in Progress

Summary

Future work

Republic of Korea

Core

Steam generator

Cold leg(downcomer + lower plenum)

Hot leg(riser + upper

plenum)

MMR: divided into four lumps/calculation nodes

Micro Modular Reactor state-space model : TraSSAM

• Three-region moving boundaryS/G formulation− Flow inside the OTSG − Subcooled feedwater− No axial heat conduction − Secondary pressure

constant− Two-phase region in

thermal equilibrium

• Critical flow assumption on steam outlet− Steam flow rate is

proportional to steam pressure

LWR

SMR-LWR

URANUS

URANUS

SMR-LWR

New Developments

• The SSTAR system remains a legacy system,

little additional work being done since completion

of its conceptual design

• More recent developments include the US industrial involvement

in three LFR initiatives:

– Hydromine AS-200 and LFR-5

– Westinghouse LFR

– Columbia Basin Consulting Group (CBCG) LBE-cooled SMR

• Additionally, an ongoing US-EU INERI project is considering the

possible role of a small LFR in powering an assured microgrid

• Most important, the LFR-SSC MoU was signed in February 2018


The Hydromine AS-200 is a highly compact 200 MWe LFR achieved primarily by elimination of components ~ 4 times more compact than the

Superphénix (SPX-1) SFR ~ 2-3 times more compact than than

the best SFR projects ~ 3-5 times more compact than

previous LFR projects


Hydromine’s AS-200 concept


Hydromine’s LFR-5 microreactor conceptMatrioska-type configuration, in which the upper partof the shroud, which supports the core, contains theSpiral-Tube Steam Generator, that in turn containsthe circulation Pump.

Control and Shut-down rods located outside the core.

LFR-5 compactness enables transportability foremployment and removal to a centralized refuelingfacility,(i) without exacerbating the proliferation issue and(ii) avoiding on-site expensive fuel handling.Thermal Power 15000 kWCore life-time 15 yearsPrimary coolant Pure leadPrimary coolant circulation Forced at power, natural for

DHRCore inlet/outlet temperature 360°C; 420°CFeed water temperature/pressure

330°C/130 bar

Fuel Enriched U (19,75%)Steam Superheated at 400°C and

130 barReactor diameter/height 2 m/3 m

Westinghouse’s Lead Fast Reactor


Aims at economic competitiveness even in the most challenging global markets, through a simple and robust design, passive safety and lifecycle requirements embedded in the design from early design phase

950 MWt (~450 MWe) reactor, to be developed starting with a lower-power prototype unit for technology demonstration

Hybrid, micro-channel type heat exchangers to reduce vessel size/weight

Thermal energy storage system to provide load-following with minimum variations in core thermal power

Oxide fuel and lead T<550°C for prototype unit. Advanced fuel and higher temperatures sought past demonstration phase

Westinghouse’s ongoing collaborations on LFR technology development, grouped by area


Collaboration PartnersAcross the board

Cooperation Agreement for LFR development ENEA (IT), Ansaldo Nucleare (IT)

UK-BEIS Advanced Modular Reactor program, Phase 1

ENEA (IT), Ansaldo Nucleare (IT), CammellLaird (UK), Heatric (UK), NNL (UK), Wood (UK), FNC (UK), NAMRC (UK), Univ. of Manchester (UK), Univ. of Cambridge (UK)

Modeling and simulationDevelopment of a Mechanistic Source Term assessment capability for LFR by coupling the SAS4A safety analysis code and the FATE containment code

Fauske (US), ANL (US)

Development of SAS4A for application to oxide-fueled LFR severe accident analysis ANL (US)

Validation of SAS4A safety analysis code for LFR application ANL (US)

DesignSizing and analysis of S-CO2 power conversion system for the Westinghouse LFR EchoGen (US)

TestingMaterials corrosion testing in liquid lead ENEA (IT)

Measurement of radionuclide retention capability of liquid lead Univ. of New Mexico (US), Brigham Young Univ. (US)

Westinghouse’s key activities on LFR technology development Plant design Cost analysis Plant layout development Safety analysis Materials testing (at ENEA) Soliciting development of new Pb

testing facilities in the US and UK


Small (left) and large (right) experimental capsules for lead corrosion tests of material specimens at ENEA

FATE model of notional containmentSAS4A

vessel model

Columbia Basin Consulting Group (CBCG)Lead Bismuth Fast Reactor w/Grid Scale Battery


CBCG is taking an Integrated Approach to Clean-Energy Production with a Competitive, Nuclear Plant Design and Load-Following via an Integrated Grid-Scale Battery ConceptBoth the Nuclear Plant and the Grid-Battery are New Designs by CBCG – when paired as an integrated facility, demand load-fluctuations are accommodated by the battery, the nuclear plant remains at baseload operations.

The Nuclear Plant is based on a Lead-Bismuth Eutectic Coolant in a Fast Reactor SpectrumCBCG initiated this effort as a teaming initiative with AKME-engineering – world events have frustrated this collaboration and CBCG proceeded with a new design concept based on US experiences with Sodium Reactors

Initial Efforts focused on Regulatory Uncertainties and Licensing of this TechnologyCBCG, with a DOE “GAIN” program Voucher, secured the services of a US National Laboratory to address these questions. The joint study concluded the technology was Licensable under current NRC rules.

Technology Facilitated Cost Reductions

A second DOE “GAIN” Voucher evaluated the Containment Building requirements. The joint study with the National Laboratory, concluded that leak-tightness requirements were reduced with Polonium mitigation.

CBCG is developing of a Polonium mitigation system to reduce containment building requirements and offsite release potentials by eliminating the principal radiological release hazard associated with this technology.

Columbia Basin Consulting Group (CBCG)Lead Bismuth Fast Reactor w/Grid Scale Battery


The Nuclear Plant is based on a Lead-Bismuth Eutectic Coolant in a Fast Reactor SpectrumCBCG’s core expertise is advanced reactor systems development and operations. CBCG has utilized the US experience in the liquid-metal (sodium) fast reactors and the operations advantages of a lead-bismuth coolant to develop a very competitive design concept for a Small Modular, Lead-Bismuth Cooled, Fast Reactor plant.

Development Objectives and Progress CBCG has been awarded a DOE Grant which will focus efforts on the nuclear system configuration and the nuclear island concept design. CBCG’s concept is a scalable design at the 100MWe and 250MWe levels. At these power levels, the primary components are suitable for factory fabrication and shipping. The balance of plant components are offered as pre-engineered systems from several steam-energy system vendors.

CBCG’s is designing the plant for a 60 year life with an extended fuel cycle of 7-10 years using uranium-oxide fuel. The nuclear plant design is suitable for multi-mission objectives, including electricity production, thermal energy production, desalination, etc. CBCG is also exploring alternative power conversion cycles.

CBCG Grid Scale Battery Initially developed as an adjunct to the Small Modular Reactor concept for CBCG’s nuclear plant. The design is suitable for broad application to Solar and Wind systems energy storage requirements for Grid stability.

China Lead-based Reactor Projects by Institute of Nuclear Energy Safety Technology

(INEST/FDS Team)• 1980s~1990s National High-Tech. Project: Fusion-fission

hybrid reactor (lead-based hybrid reactor)• 2000s~ ITER project: fusion reactor (lead-based liquid

blanket)• 2010s~ Strategic Priority Research Program CAS: ADS

system(lead-based subcritical reactor)• Recently: China lead-based Mini-Reactor (CLEAR-M),

Supported by national/local government and industry• Other innovation concepts

– CLEAR-I: ADS system for transmutation– CLEAR-A: Advanced external neutron driven system for multi purpose

0572740631970

R&D Progress for China Lead-based Reactor• Key technologies

– ~30,000h operation of lead-based coolant facilities– 1:1 prototypes of components (pump, HX, FA, CRDM, IV refueling machine, etc.) has

been manufactured and tested under LBE condition• Three Integrated Test Platform

– Engineering validation facility CLEAR-S (pool-type, 240t LBE)– Physical validation reactor (critical/sub-critical dual mode)– Digital simulation reactor CLEAR-V

• CLEAR-S LOF Benchmark was proposed in 51st IAEA TWG-FRmeeting

– The world’s first heavy liquid metal of pool type facility thermal-hydraulics international benchmark

– With 16 members interested in TWG-FR meeting

CLEAR-S Pool-type HLM Platform KYLIN-II facility 1:1 prototype components

Lead & LBE technology development in Europe

There are presently two main projects in EU (with many synergies):

EURATOM

MYRRHA (LBE)Flexible Irradiation Facility

(Demonstrator of ADS)

ALFRED (LFR)Advanced Fast ReactorEuropean Demonstrator

MYRRHA’s implements phased approach

Phas

e 1

–10

0 M

eV

Phas

e 2

–60

0 M

eV

Phas

e 3

–Re

acto

r

Benefits of phased approach:• Phase 1 -

construction of 100 MeV accelerator

• Reducing technical risk

• Spreading investment cost

• Allowing to have the first R&D facility available in Mol end of 2026

Copyright © 2018 SCK•CEN

EURATOM

BELGIUM Government recently funded PHASE 1 of Myrrha with 558 M€

EURATOM

ALFRED SUPPORT:The FALCON* Consortium

FALCON Consortium Agreement was established in 2013 to bring LFR technology to industrial maturity

FALCON recently evolved in the European context. Main objectives are:

• ALFRED as a Major Project in Romania• Finalization of ALFRED feasibility study • Initiation of construction of supporting R&D facilities

New members sharing the objective of a rapid deployment of an LFR demonstrator, interested in the R&D supporting infrastructure and in the ALFRED industrial outcomes are welcome to join.

*FALCON – Fostering ALfred CONstruction

EURATOM

EURATOM

ALFRED DEMONSTRATORto achieve technology maturity

The operation of ALFRED will be based on a stepwise approach: phase 1: operation at low power and low-temperature range

• Using presently existing proven materials working without corrosion protection

phase 2: operation at full power and high-temperature range• Using coated materials fully qualified during phase 1

Commissioning

Phase 1

Phase 2

2040

GIF-LFR-pSSC October 5°2018 - Moscow – hosted by NIKIET

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