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Overview Reattori IV Generazione
Parte III
Milano , 27 Maggio, 2009
Sergio Orlandi
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The Generation IV International Forum (GIF)
Current Generation II and III nuclear power plant designs provide a secure and
low-cost electricity supply in many markets, but advances in nuclear energy
system design can broaden the opportunities for the use of nuclear energy
U.S. Department of Energy's Office of Nuclear Energy, Science and Technology
engaged governments, industry, and research community worldwide in a wide
ranging discussion on the development of next generation nuclear energy
systems known as "Generation IV"
GIF was established in January 2000 to investigate innovative nuclear energy
system concepts for meeting future energy challenges
GIF members include: Argentina, Brazil,
Canada, China, Euratom, France, Japan,
South Africa, South Korea, Russia,
Switzerland, United Kingdom, and United
States, with the OECD-NEA and the IAEA as
permanent observers
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Goals for Generation IV Nuclear Energy Systems
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Generation IV Roadmap
GIF analyzed and evaluated approximately 100 system concepts for their
potential to meet the goals of the Generation IV
Only 6 systems was selected for cooperative development by GIF based on the
ability to fulfill targeted applications, deployment readiness, and development cost
Technology Roadmap for Generation IV Nuclear Energy Systems, describing the
R&D pathways for establishing technical and commercial viability demonstration
and, potentially, commercialization of the 6 selected systems, was issued in 2002.
The 6 GENERATION IV Systems
ACRONYM
Gas-Cooled Fast Reactor System
GFR
Lead-Cooled Fast Reactor System
LFR
Sodium-Cooled Fast Reactor System
SFR
Very-High-Temperature Reactor System
VHTR
Supercritical-Water-Cooled Reactor System
SCWR
Molten Salt Reactor System
MSR
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ANSALDO and Europe opportunities for the development of
GEN IV Systems
Develop the:
LFR technology
in the frame of the R&D activities on Accelerator Driven
Systems (ADS) (IP-EUROTRANS and CDT Projects)
in the frame of the GEN IV cooperation (ELSY Project and
future LEADER project)
VHTR technology
in the frame of the GEN IV cooperation (RAPHAEL Project)
SFR technology
in the frame of the GEN IV cooperation (ESFR Project)
GFR technology
in the frame of the GEN IV cooperation (future GoFastR
Project)
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Survey of the ADS development in ANSALDO and in Europe
(past activities)
Following a preliminary design developed in 1998, which was based
on the Energy Amplifier concept proposed by CERN, a first
configuration of a Lead-Bismuth Eutectic cooled Experimental ADS
(LBE-XADS) was worked out in the period 1999-2001 by a group of
Italian organizations led by ANSALDO, with the aim of assessing the
feasibility of a small-sized (80 MWth) ADS
The design activities of the Italian organizations (ANSALDO, ENEA,
INFN, CRS4, CIRTEN, SIET and SRS) were carried out under the
aegis of MURST (the former Italian Ministry of University and of the
Scientific-Technological Research)
The design activities continued within the 5th FP of the European
Commission, in the context of the research on Fission Reactors
Safety, that funded a project named PDS-XADS (Preliminary Design
Studies of an Experimental Accelerator Driven System) with a threeyear contract
(2002-2004) involving the participation of 25
European partners (industries, research organizations and
Universities)
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Survey of the ADS development in ANSALDO and in Europe
(past activities)
PDS-XADS Project focused on the comparative assessment of 3 ADS
concepts
A 80 MW Gas-Cooled XADS proposed by AREVA
A 80 MW LBE-Cooled XADS as development of the original Italian
design
A 50 MW LBE-Cooled XADS (MYRRHA) proposed by SCK•CEN
It was the first major step of a joint European effort that, as a keymilestone, did allow the detailed design of an XADS for demonstration
of the transmutation technology by means of a subcritical reactor
PDS-XADS project has demonstrated the feasibility and the safety of
coupling an accelerator with a subcritical reactor and the feasibility of
transmutation of MA and a LLFP’s, this was the anticipated mission of
the subsequent program on ADS development
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The eXperimental Accelerator-Driven Systems (XADS)
in the 5°° FP of the EU
80 MW LBE-cooled XADS
50 MW LBE-cooled XADS
(MYRRHA)
80 MW Gas-cooled XADS
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ADS development in ANSALDO and in Europe (what’s at present)
In the frame of the project IP-EUROTRANS of the 6th FP of the EU, 51
European Organizations (coordinated by FZK) have the strategic R&D
objective to pursue forward an European Transmutation Demonstration
(ETD) in a step-wise manner
The aim of the 5-year lasting EUROTRANS program is twofold:
Develop the conceptual design of an European Facility for Industrial
Transmutation (EFIT) with a pure lead-cooled reactor of several hundreds
MW with MA burning capability and electricity generation at reasonable
cost
EFIT uses as fuel MA (Uranium-free fuel)
Carry out the detailed design of a smaller facility, to be constructed in the
short-term, for eXperimental Transmutation in an ADS (XT-ADS), for
irradiation and for demonstration of key features of EFIT
XT-ADS is an irradiation facility intended to be, as much as possible, a test bench
of EFIT main components and operation scheme, but at lower working
temperatures using LBE as primary coolant and spallation target. XT-ADS uses
standard MOX-fuel, but it is designed also to handle some MA Fuel Assemblies
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EFIT: MA burning features
3000
2900
[ kg ]
2800
Tot Pu
Tot MA
2700
2600
∆MA / MA (BOC) ≅ -13,9%
2500
∆Pu / Pu (BOC) ≅ -0,7%
2400
0
3 years
1
[ years ]
BU = 78,28 MWd / kg (HM)
Total E = 10,0915 TWhth
2
BU
3
-40,17 kg (MA) / TWh
-1,74 kg (Pu) / TWh
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EFIT Reactor Assembly
1 Reactor Core
2 Active Zone
3 Diagrid
4 Primary Pump
5 Cylindrical Inner Vessel
6 Reactor Vessel
7 Reactor Cavity
8 Reactor Roof
9 Reactor Vessel Support
10 Rotating Plug
12 Above Core Structure
13 Target Unit
14 Steam Generator Unit
15 Fuel Handling Machine
16 Filter Unit
17 Core Instrumentation
18 Rotor Lift Machine
19 DHR Dip Cooler
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EFIT Reactor Assembly
1 Reactor Core
2 Active Zone
3 Diagrid
4 Primary Pump
5 Cylindrical Inner Vessel
6 Reactor Vessel
7 Reactor Cavity
8 Reactor Roof
9 Reactor Vessel Support
10 Rotating Plug
12 Above Core Structure
13 Target Unit
14 Steam Generator Unit
15 Fuel Handling Machine
16 Filter Unit
17 Core Instrumentation
18 Rotor Lift Machine
19 DHR Dip Cooler
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The ADS Systems (EFIT and XT-ADS) in the 6°° FP of the EU
EFIT 400 MWth Reactor
XT-ADS 70 MWth Facility
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ADS development in ANSALDO and in Europe (next project)
In the frame of the project CDT of the 7th FP of the EU, 20 European
Organizations (coordinated by SCK•CEN) have the strategic objective to
further develop the design of a FAst Spectrum Transmutation Experimental
Facility (FASTEF) able to demonstrate efficient transmutation and
associated technology through a system working in subcritical and/or
critical mode
The aim of the 3-year lasting CDT program is to:
develop the engineering design of a first-step experimental device
based on the resulting MYRRHA/XT-ADS facility of the FP6 IPEUROTRANS project
define new R&D activities needed to aid the detailed design and the
construction of such a facility
conduct a detailed analysis of the site specifications and regulatory
requirements to host such a facility
FASTEF is proposed to be designed to an advanced level for decision to
embark for its construction at the horizon of 2012
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LFR development in ANSALDO and in Europe
Expertise on Heavy Liquid Metals
Considerable expertise has been gained in the European Union and,
specifically, in ANSALDO NUCLEARE on heavy liquid metal technology
(Lead-Bismuth Eutectic – Lead) in the frame of R&D activities on
transmutation of Long Lived radioactive waste (MA - LLFP) in ADS
Considering the above experience, in the frame of the Management of
Radioactive Waste of the 6th FP of the EU, 21 European Organizations
did take the initiative to promote the design of a competitive and a safe
critical fast reactor cooled by pure Lead
This initiative has been successful in that the EU has awarded the 21
European Organizations with a contract for carrying out, over the time
frame of three years (2006-2009), the specific targeted research and
innovative project ELSY (European Lead SYstem)
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LFR development in ANSALDO and in Europe: ELSY Project
Objectives
Demonstrate the technical feasibility of a LFR
Demonstrate the possibility to design an economically
competitive and safe LFR adopting innovative and
reasonably simple engineered features
Demonstrate the capability to fully comply with the
Generation IV goals
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ELSY Compliance with the Generation IV Goals (1/2)
Goals achievable via
Goal Areas
Goals
Inherent features
Engineering
Resource utilization
• Lead is a low-moderating medium
of low-absorption cross section
• Breeding ratio close to 1
Waste minimization
and management
• Fast-neutron spectrum for
operation as a burner
• homogeneously diluted
Minor Actinides in the fuel.
• No net generation of Pu
Life cycle cost
• Lead does not react with air or
water
• Lead has a very low vapour
pressure
Simplicity
Sustainability
Economics
Risk to capital
(Investment
protection)
• Potential of removable invessel components
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ELSY Compliance with the Generation IV Goals (2/2)
Goal Areas
Safety and
Reliability
Proliferation
Resistance and
Physical
Protection
Goals
Inherent features
Engineering
Operation will excel in
safety and reliability
• very high boiling point
• low vapor pressure
• high shielding capability
• Primary system at atmospheric
pressure
• medium operating range (core
inlet and outlet temperatures)
Low likelihood and
degree of core damage
• high heat transfer, specific heat and
thermal expansion coefficients
• core with inherently negative
reactivity feedback
• Large fuel pin pitch
• decay heat removal by natural
circulation
• primary pumps in the hot collector
No need of off-site
emergency response
• Lead density close to that of fuel
(considerably reduced risk of recriticality in case of core melt)
• lead retains fission products
Unattractive route for
diversion of weaponusable plutonium
• neutronics enables long-life core
• Use of fuel containing MA
Increased phys.
protection against acts
of terrorism
• Lead compatible with air and water
• Independent and redundant DHR
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LFR development in ANSALDO and in Europe
Participants to ELSY Project
•
•
•
•
•
•
INDUSTRY
Ansaldo (as Project Coordinator),
Del Fungo Giera Energia,
Empresarios Agrupados
UTILITIES
EDF
EUROPEAN COMMISSION JOINT
RESEARCH CENTRE
JRC/IE-Petten
NATIONAL RESEARCH
ORGANIZATIONS
CESI RICERCA, CNRS, ENEA,
FZK, INR, NRG, UJV-REZ, PSI,
SCK•CEN
UNIVERSITIES
AGH, CIRTEN, KTH
INTERNATIONAL PARTNERS (not
funded by EU) SNU (Korea),
KESRI (Korea)
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ELSY: Simplicity for Economics
(Initial design)
no intermediate system
simple internals
SPX1
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ELSY (1500 MWth): Revolutionary design
B
C
B
Steam
Generator
Primary Pumps
C
Primary Coolant
Flow Path
Core
Reactor Vessel
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ELSY: Steam Generator & DHR 1
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ELSY: DHR 2
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ELSY: Pump impeller
Outside impeller diameter
1.1 m
Hub diameter
0.43 m
Impeller speed
140 rpm
Number of vanes
Vane profile
3
NACA 23012
Velocity in suction pipe
1.6 m/s
Velocity relative to the vane at
vanes tip
8.7 m/s
Meridian velocity (at impeller
entrance and exit)
3.1 m/s
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Ongoing and future GENERATION IV concepts development
in ANSALDO and in Europe
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LFR development in ANSALDO and in Europe (next project)
Advanced nuclear systems for increased sustainability
FP7-Fission 2009 2.2.1
Conceptual Design for Lead Cooled Fast
Reactor Systems (LEADER)
18 European Organization are preparing a proposal to
answer to the EC call
ANSALDO NUCLEARE is the Project Coordinator
3 year Project (2010-2013)
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LFR development in ANSALDO and in Europe (next project)
LEADER Project Objectives
Deep analysis of the hard points of the ELSY design in
order to identify possible improvements with the goal to
reach a feasible and improved LFR configuration
Definition of a LFR configuration to be used as a
reference plant
Conceptual design of a scaled down facility respect to
the reference plant (the demonstrator) of a size of the
order of 100 MWt (to be representative with limited cost)
Continue the Lead technology development
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GFR development in ANSALDO and in Europe (next project)
Advanced nuclear systems for increased sustainability
FP7-Fission 2009 2.2.1
The European Gas {Cooled} Fast Reactor Project
(GoFastR)
~20 European Organization (coordinated by AMEC) are preparing a
proposal to answer to the EC call
GoFastR project is aimed at progressing the GFR and ETDR (now
ALLEGRO) systems through the viability phase (now to end of 2012)
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SFR development in ANSALDO and in Europe
In the frame of the project ESFR of the 7th FP of the EU, 26 European
Organizations (coordinated by CEA) have the strategic objective to
address key viability and performance issues to support the
development of an ESFR through a four years program (2009-2012)
ESFR project is a complementary of the already underway activities on
SFR in EU and in Generation IV (ESFR represent the European
contribution)
The four years schedule fit with the principle of an industrial
deployment of the ESFR technology around 2040 with the preliminary
deployment of a demonstrator by 2020
Two mains steps are identified in the ESFR program:
A first step of 2 years (2009 – 2010/11) with the objective to assess and
select innovative options susceptible to be introduced into the system
A second step (2010/11 – 2012/13) used to better confirm the
performances of the retained options and to deeply assess their interest
and their aptness toward the requirements
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HTR development in ANSALDO and in Europe
• The HTRs have been developed up to the industrial realization for
30 years
– in USA (Peach Bottom, Fort Saint Vrain)
– In Europe (Dragon in UK, AVR and THTR in Germany)
• These developments were stopped in the 90's mainly because of
– The general drawback in nuclear energy
– The competitiveness of HTRs was impeded by their low power density
• A renewed interest for HTR raises in the world during the last ten
years
– Several projects of industrial prototypes: PBMR, GT-MHR, ANTARES
– Two test reactors started operation: HTTR and HTR-10
– Important R&D programmes for the support of HTR industrial development
have been launched
• The International Generation IV VHTR programme
• In USA, the DOE launched several NERI and I-NERI actions, the NRC has its
own programme
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HTR development in ANSALDO and in Europe
• The interest for HTRs is growing again since the end of the 90's
– The European FP projects:
• In FP4 (1998), one small exploratory project
• In 2000 creation of HTR-TN network of research and industry partners
involved in HTR technology development, which submitted with
success projects in FP5 and FP6:
– In FP5 (2000) - 9 co-ordinated projects with 19 participant Organizations
– In FP6 (2005-2010) - 1 Integrated Project (RAPHAEL) with 35 participant
Organizations (coordinated by AREVA)
– ANSALDO was involved in the FP5 HTR-L (Safety), HTR-E
(Components and Systems) and HTR-N (Core Physics) projects
– ANSALDO is involved in the FP6 RAPHAEL Project (SPComponent Development and SP-Safety)
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Indirect-Cycle VHTR (600 MWth)
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Small-scale Advanced Reactor: IRIS
• The International Reactor Innovative and Secure (IRIS)
is a smaller-scale advanced light water reactor (LWR),
being developed through a strong international
partnership for near-term deployment (within the next
decade), to offer a simple nuclear plant with outstanding
safety, attractive economics and enhanced proliferation
resistance characteristics
• IRIS provides a viable bridge to Generation IV reactors
and has excellent capability to satisfy in the near/midterm timeframe the Global Nuclear Energy Partnership
(GNEP) requirements for small-scale reactors
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IRIS Innovative Design
IRIS is innovative in design employing
an integrated primary system that
incorporates all main primary circuit
components within a single vessel
i.e., the core with control rods and their
drive mechanisms, eight helical coil
steam generators with eight associated
fully-immersed axial flow pumps, and a
pressurizer
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Helical-tube steam generator
A Mock-up of Helical-tube SG was designed,
constructed and successfully tested at SIET
The same SG concept is proposed for IRIS
Advantages
Compactness
Reduced number of tubes
Resistant to thermal loads
Large experience from LMFBRs and LWRs
Disadvantages
Higher primary-side pressure loss than
straight-tube design
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