progress report on the italian national program on fast ... · progress report on the italian...

Progress report on the Italian national program on fast reactors

P.Agostini; G.Grasso; M.Angiolini – ENEA L.Cinotti - Hydromine

Vienna, May 2017

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Initiatives and collaborations to support LFR

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FALCON consortium

• In december 2013 the FALCON (Fostering ALfred CONstruction) Consortium was signed among ANSALDO, ENEA and ICN (Romania): • to support the contruction of ALFRED through EU structural funds

• to optimize the cooperation among the PARTIES through strategic, management, governance, financial and technical work

• In 2014 also CVRez (Czech Republic) adhered the FALCON consortium

• Several contacts were taken with Romania Government representatives to coordinate the access to European regional funds dedicated to South Muntenia Region

• In August 2014 the ALFRED Project was included in the draft of Smart Specialization Platform of South Muntenia region

• The FALCON agreement has been re-newed in June 2016

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FALCON consortium

Recent updates within Falcon Consortium

• The political situation in Romania is in favor of ALFRED reactor

• In 2017 Romanian Ministry of Research has announced progressive funds availability for:

• Construction of Lead technology based preparatory infrastructures and laboratories

(minor project) 90M€

• Construction of ALFRED (major project) 700 M€

• ENEA and ANSALDO assured all the support, by in-kind contribution, to write the technical specifications to launch the orders

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Hydromine LFR concept

Hydromine is an U.S. based company, very active in the business of energy and mining.

It has recently hired a small group of Italian LFR specialists acquiring the rights on their LFR concept.

The chief engineer is Luciano Cinotti, formerly ANSALDO, who based his concept mainly on ENEA technology

Hydromine officially presented its concept in July 2016 at Imperial College, London.

The Hydromine concept is reported in this presentation

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Other LFR collaborations

• ENEA and Italian companies continue to collaborate with Chinese INEST Institute to CLEAR-S erection

• ENEA started further collaborations on LFR technology with EU and outside EU companies

• In 2017 a new 4 Meuro EU project, aiming at Gen IV materials, was approved for funding. The project name is GEMMA (GEneration IV Materials Maturity), the coordinator is ENEA. The partnership includes 22 European Institutes + KAERI

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GEMMA

LFR-AS-200

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The Hydromine LFR-AS-200

LFR stands for Lead-cooled Fast Reactor,

AS stands for Amphora-Shaped, referring to the shape of the Inner Vessel

200 is the rated electrical power of the reactor in MW.

The LFR-AS-200 is based on innovative solutions conceived by the Hydromine

team in the last ten years and presented for the first time on July 2016 in London

at the Imperial College. Core power (MWth) 480

Electrical power (MWe) 200

Core inlet/outlet T (°C) 420/530

Primary loop pressure loss (bar) 1,3

Secondary cycle Superheated steam

Turbine inlet pressure (bar) 180

Feed water /steam temperature (°C) 340/500

Table1: Main design

parameters of LFR-AS-

200

L. Cinotti, Hydromine Nuclear Energy Limited - Novelty of the LFR-AS-200 project

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LFR-AS-200, 10 years work for achieving a simple, consistent design

LFR-AS-200 is predictably economic

Volume of the primary system

< 1m3/MWe !! ~ 4 times less than SPX1 ~ 2-3 times less than the best SFR projects ~ 3-5 time less than previous LFR projects

LFR-AS-200 is feasible Height of the reactor vessel

6,2m!!


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The SG of LFR-AS-200 differs from current technology

From:

long SG deeply immersed in the melt with

top inlet window and bottom outlet window.

To:

short Spiral-tube SG partially raised with

respect to the cold collector free level with

bottom inlet and top outlet.

Advantages: - No risk of steam release deep in the melt and large lead displacements. - No risk of cover gas

entrance into the core.

- Short, compact SG,

reduced RV height.

- No “Deversoir”,

reduced RV diameter.


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From:

Pumps in the cold collector,

in-between the SGs, with long shafts and

in-melt bearings.

To:

Pump in the hot collector,

integrated in each SG to feed the SG, with

large hollow shaft filled with lead, and no

in-melt bearings.

Advantages:

- Use of available space inside the SG,


- No bearings in lead.

- High mechanical inertia for mild

transients from forced to natural

circulation.

- Core fed by the hydrostatic head Δh

between cold and hot collector,

no “LIPOSO”


The Pump assembly differs from current technology

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The issue of refueling the LFR.

Refueling is difficult in sodium:

- Both Jōyō and Monju in Japan are at shutdown because of handling accidents. - Need of a complicate in-vessel refueling machine.

- Need of complicate preparatory interventions.

In-lead refueling is even more difficult:

- Higher refueling temperature.

- Large buoyance effect. Above Core Structure to be moved for refueling


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The Fuel Assembly of LFR-AS-200 differs from current technology

From:

Fuel Assemblies immersed in the melt

handled by an in-vessel + ex-vessel

Refueling Machine.

To:

Fuel Assemblies with stem extended above the

lead free level handled by an ex-vessel

Refueling Machine.

Advantages:

- No in-vessel Refueling Machine,


- No Above Core Structure,


- Buoyance compensated by the

emerged portion of the stem.

- Increased reliability.

A cold handle allows easy handling in hot oil.


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The issue of ISI of the core support system

The classical core support structures, Diagrid and Strongback, are critical components

subjected to thermal transients and neutron damage. Their collapse could bring about

effects of control rod extraction.

Their ISI is difficult in sodium because of deep location and complexity.

Their ISI in lead would be even more difficult.


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The Core of the FR-AS-200 is self-sustaining

From:

Fuel Assemblies (FA) supported in lead

at the bottom by Diagrid

and Strongback.

To:

Core anchored at the top to a barrel in gas

space.

Advantages:

- No Diagrid.

- No Strongback. - No support system subject to thermal

transients and neutron damage

(only disc cams integral part of the FAs).

- No need of disconnecting all FAs

instrumentation at refueling.

- Increased availability. Cams


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The Amphora-Shaped Inner Vessel

From:

Inner Vessel, large at top and smaller at

bottom, containing Shielding Assemblies

(and Breeding Assemblies).

To:

Amphora-Shaped Inner Vessel, no Shielding

Assemblies (and no Breeding Assemblies).

Advantages:

- No need of Shielding

Assemblies,

reduced RV diameter,

increased availability,

reduced waste inventory.


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The ex-core control rods

From:

In-core control and shut down rods.

To:

Ex-core control and shut down rods.

Advantages:

- Reduced core dimensions.

- No disconnection of rod

drives for refueling.


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Resistance to cyber attacks

Logics and operators backed up by passively actuated systems to shut down the reactor.

In a LFR there is a margin of hundreds K between the operating temperature and the safety limit, hence, e.g., thermal expansion can be used to open the core and shut down the reactor in case of failure of logics or of operator intervention.

Bi-metallic expansors

open and shut down

the core when

temperature exceeds

normal operating

limits.


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Resistance to cyber attacks 2/2

Thermal expansion of the cold leg

of the lead loop opens the louvers

of the air coolers when lead

temperature exceeds 400 °C. Lead-water, double-wall

bayonet-tube bundle heat

exchanger at Brasimone site.

dLead loop

ChimneyAir cooler

Louvers

Passive shut down is complemented by two

independent, passive, diverse, redundant DHR

systems to face the Unprotected Loss Of Offsite

Power (ULOOP).

DHR1:Three water-steam

loops passively operated

with water as heat sink.

DHR2: Three lead

loops passively

actuated and operated

with air as heat sink.


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Conclusion 1– LFR-AS-200 enhances safety while dispensing of hitherto classical critical components

Components/systems no more needed

Rationale for elimination

Impact

Intermediate loop Lead properties. Compact Reactor Building, easy

operation, cost reduction (about 30% of the cost of NSSS in a SFR).

Above core structure Use of FAs with extended stem.

Reduced diameter of the RV, no need of its displacement for refuelling.

In-vessel refuelling machine Use of FAs with extended stem.

Elimination of a mechanically critical component to be operated in opaque medium.

“Deversoir “ or equivalent component

SG-outlet window at top of the SG.

Reduced diameter of the RV, reduced vibration risk.

Diagrid Self-sustaining core. No need of a component difficult to inspect.

Strongback Core supported by the roof via the barrel.

No need of a component difficult to inspect. No structure fixed to the RV

“LIPOSO” , hydraulic connection pump to diagrid

Pumps in the hot collector. Elimination of a mechanically critical component.

Pump bearings in lead Low required NPSH for the pumps.

Elimination of a mechanically critical component.

Flywheel on the pump system Use of rotating lead inertia. Smaller footprint on the reactor roof.

Core shielding assemblies Use of the ASIV. Reduced diameter of the RV, simplicity.

Blanket assemblies No net Pu generation. Reduced diameter of the RV, simplicity, increased proliferation resistance.


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Materials studies

GEMMA Project

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GEMMA

Challenge: resolving the key remaining issues regarding structural (and fuel materials) to be used in Generation-IV reactor concepts under consideration in the EU

Keywords: materials and joints under neutron irradiation, high temperature, compatibility with coolants (and advanced fuels), physical models and/or modelling-oriented experiments, microstructural change and effects on material properties, advanced micro-structural characterisation techniques, mitigation strategies surface engineering concepts

Impact: predictive capability, design codes, overcome bottlenecks of certification of materials, contribute to safety improvements also in other nuclear systems

WP3-Irradiation effects: modelling and experiments

WP1-Surface engineering & its basic characterisation

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Proposed structure focus on 316L(N) & 15/15Ti

Proposed structure focus on 316L(N) & 15/15Ti

WP4-Compatibility with high T coolant: Corrosion/erosion

testing & modelling

WP2-Welding & its relevant characterisation

WP5-Coordination and dissemination (communication & exploitation of results)

Base material selection and procurement

SFR (LFR, GFR)

LFR, GFR

LFR, GFR SFR, LFR (GFR)

DESIGN RULES

DESIGN RULES MITIGATION

MODELLING &

µSTRUCTURE

MODELLING &

µSTRUCTURE K.Tucek M.Nastar

E. Stergar

A.Weisenburgerr

P. Agostini

GEMMA

Lead-Bismuth

coolant

Support to MYRRHA

• Corrosion tests in LBE of AISI 316L, AISI316LN and 15-15Ti MYRRHA,

• Corrosion of: welded joints of above steels by TIG &

SAW,

AFA steels and

coated steels.

• Mechanical qualifications in LBE of the above steels by: SSRT,

fracture toughness,

creep rupture

• Corrosion modeling in HLM

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GEMMA

Support to ALFRED

• Corrosion tests in Pb of AISI 316L, AISI316LN and 15-15Ti ALFRED,

• Corrosion of: welded joints of above steels by TIG &

SAW,

AFA steels and

coated steels.

• Mechanical qualifications in Lead of the above steels by: SSRT,

fracture toughness,

creep rupture

• Corrosion modeling in HLM

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GEMMA

Support to ASTRID

• Theoretical studies, models and tests of diffusion aging by annealing and ion irradiation in Fe-Ni-Cr systems.

• Detailed qualification of large thickness AISI 316LN welds through measurement of residual stresses by neutron diffraction and modelling

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GEMMA

Support to ALLEGRO

• Mechanical qualification at 550C of AISI 316L welded joints by TIG and SAW: SSRT

Fracture toughness

Creep rupture

• Mechanical qualification at 550C of AISI 316L Al2O3 coated SSRT

Creep Rupture

• Swelling qualification under ion irradiation of coated AISI 316L

• Low damage qualification under neutron irradiation of coated AISI 316L

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GEMMA

Conclusions Recent changes in the Romanian political situation offered important chances to fund the

ALFRED initiative In the frame of FALCON consortium.

This new fact is boosting the LFR activities by ENEA and ANSALDO as well.

Hydromine US based company has recently acquired rights for an innovative LFR by an Italian group of engineers and designers formerly in ANSALDO.

The Hydromine project LFR-AS-200 presents innovative design features and relies on technologies developed by ENEA

ENEA coordinates a new EU project focused on structural materials for GEN IV reactors. The project includes 22 research institutes and industries from: Italy, Belgium, Germany, France, Finland, U.K., Spain, Czech Republic, Sweden, Poland, Romania and Korea.

The ongoing international collaborations by ENEA and ANSALDO are: • in the European frame with Romanian ICN and Czech CVRez

• with Chinese Academy of Sciences

• with US companies

• with Russian institutes

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