introduction to generation iv nuclear energy systems iv isu... · 3 • nuclear is a major...
Post on 04-Oct-2020
0 Views
Preview:
TRANSCRIPT
Introduction to Generation IV Nuclear Energy Systems
Dr. Ralph Bennett, Technical Director, Generation IV International Forum, andDirector, International and Regional Partnerships, Idaho National Laboratory
16 Mar 2009
2
The Problem of Climate Change• Global greenhouse gas (GHG) emissions have grown since
pre-industrial times, increasing 70% between 1970 and 2004• With current climate change mitigation policies and practices,
global GHG emissions will continue to grow• The Earth is about to undergo long lasting changes in its
climate, seas and land cover, including– Temperature– Precipitation– Sea level– Ocean circulation– Ice/snow cover– Storm frequency– Storm intensity– Desertification
Global Warming (deg C) by 2100 (IPCC prediction)
http://www.aip.org/history/climate/summary.htm http://www.grida.no/climate/ipcc_tar/
3
• Nuclear is a major contributor in the WEO 2008 450 Policy Scenario— about 250 GWe more generation by 2030 (an 80% increase from today)
• Nuclear energy systems must continue their advances in order to unlock a potential on this scale
The Challenge for Nuclear Energy
http://www.iea.org/weo/2008.asp
4
Generations of Nuclear Energy
Early Prototypes
Generation I
- Shippingport- Dresden- Magnox
1950 1960 1970 1980 1990 2000 2010 2020 2030
Gen I Gen II Gen III Gen III+ Gen IV
Commercial Power
Generation II
- PWRs- BWRs- CANDU
Advanced LWRs
Generation III
- CANDU 6 - System 80+- AP600
Generation III+
Evolutionary Designs
- ABWR- ACR1000- AP1000- APWR- EPR- ESBWR
- Safe- Sustainable- Economical- Proliferation
Resistant and Physically Secure
Generation IV
RevolutionaryDesigns
http://www.gen-4.org/Technology/evolution.htm
5
Creation of the International Forum• Started in Jan 2000 by nine countries and established Jul 2001• Agreed that nuclear energy is needed to meet future needs• Defined four goal areas to advance nuclear energy into its
next, ‘fourth’ generation:– Sustainability– Safety & reliability– Economics– Proliferation resistance and physical protection
• Will collaborate to make ‘Generation IV’ systems deployable in large numbers by 2030, or earlier
http://www.gen-4.org/GIF/About/origins.htm
6
Today’s Membership
7
SystemNeutron Spectrum
FuelCycle
Size (MWe) Missions R&D Needed
Sodium Cooled Fast Reactor (SFR)
Fast Closed 300-1500 Electricity, Actinide Management
Advanced recycle options, Fuels
Very-High- Temperature Reactor (VHTR)
Thermal Open 250 Electricity, Hydrogen, Process Heat
Fuels, Materials,H2 production
Gas-Cooled FastReactor (GFR)
Fast Closed 1200 Electricity, Hydrogen,Actinide Management
Fuels, Materials,Thermal-hydraulics
Supercritical-Water Reactor (SCWR)
Thermal,Fast
Open,Closed
1500 Electricity Materials, Thermal- hydraulics
Lead-Cooled Fast Reactor (LFR)
Fast Closed 50-150300-6001200
Electricity,Hydrogen Production
Fuels, Materials
Molten Salt Reactor(MSR)
Epithermal or Fast
Closed 1000 Electricity, Hydrogen Production, Actinide Management
Fuel treatment, Materials, Reliability
Overview of the Generation IV Systems
http://www.gen-4.org/Technology/systems/index.htm
8
Sodium-Cooled Fast Reactor (SFR)Characteristics
• Sodium coolant, pool or loop type• 550C outlet temperature• 600-1500 MWe large size, or• 300-600 MWe intermediate size• 50 MWe small module option• Metal fuel with pyroprocessing or
MOX fuel with advanced aqueous separation
Benefits• High thermal efficiency• Consumption of LWR actinides• Efficient fissile material
generation
http://www.gen-4.org/Technology/systems/index.htm
9
Primary Pump/IHX
Reactor Vessel
SG
Secondary Pump
IHXDHXPHTS pump
Reactor core
Steam Generator
AHX Chimney
PDRC piping
In-vessel core catcher
IHTS piping
IHTS pump
IHXDHXPHTS pump
Reactor core
Steam Generator
AHX Chimney
PDRC piping
In-vessel core catcher
IHTS piping
IHTS pump
12.03 m3,186 gal.
PLAN VIEW OF THE CORE
PRIMARYCONTROL RODS
1m TRAVEL DISTANCEOF THE CONTROL RODS
(10'-8")
THERMALSHIELD
(29.5")0.75m
3.25m
Na-COHEAT EXCHANGER
7m
IHXX-SECTION (FLATTENED FOR CLARITY)
(23')
(Ø 7.5' x 12.6' LONG)
IHX
2
SECTION A - A
Normal sodium level
Normal sodium level
Sodium faulted level
Pump offSodium Level
SODIUM DUMP TANKØ 2.5 m x 3.8 m LONG
CORE BARREL Ø266 / 268 cm(104.7" / 105.5")
SECONDARYCONTROL RODS
CONTROLRODS (7)
PUMPS (2)ON Ø 142.5" B.C.
PLAN VIEW OFIHX AND PUMPS IHX (2)
1.7m EACH2
DRACS (2)0.4m EACH2
Primary Vessel I.D.
Guard Vessel I.D.
Hot Pool
Cold Pool
PRIMARY VESSEL(2" THICK)
3.5m(11'-8")
GUARD VESSEL(1" THICK)
1m(39.4")
3
TURBINE/GENERATORBUILDING
ELEVATOR
(Ø 25.5')Ø 7.7m
Na-AirHEAT EXCHANGER (2)
CONTROLBUILDING
0 1 2 3 10METERS4 5
5.08m [16.7FT]
4.57m [15FT]
7m [23FT]
1.89m [6.2FT]
12.72m [41.7FT]
14.76m [48.4FT]
1.93m [6.3FT]
.61m [2FT]
2.29m [7.5FT]
EXHAUST TO VENT STACK
Large-scale Loop
Intermediate-scale Pool
Small-scale Modular
SFR Reactor Options
10
• Minor actinide bearing fuel technology (fabrication, irradiation)– Metal and oxide fuel performance– Carbide fuel performance– Nitride/Carbide fuel performance
• Inspection & repair technologies– Ultrasonic and alternative techniques– Replace/repair experience
• High temperature leak-before-break assessment technologies– Creep-fatigue crack initiation and growth test results
• Advanced energy conversion concepts– Basic design concept of supercritical CO2 Brayton cycle system – Compact supercritical CO2-to-CO2 heat exchangers
SFR Technology Interests
11
Very-High-Temperature Reactor (VHTR)Characteristics
• He coolant• >900C outlet temperature• 250 MWe• Coated particle fuel in either
pebble bed or prismatic fuel
Benefits• Hydrogen production• Process heat applications• High degree of passive safety• High thermal efficiency option
http://www.gen-4.org/Technology/systems/index.htm
12
VHTR Reactor OptionsPebble bed core Prismatic-fuel core
13
VHTR Hydrogen Options
Porous Anode, Strontium -doped Lanthanum Manganite
Gastight Electrolyte, Yttria-Stabilized Zirconia
Porous Cathode, Nickel -Zirconia cermet
2 H20 + 4 e- 2 H2 + 2 O=
2 O= O2 + 4 e-
2 O=
H2O
H2
O2
4 e-
Interconnection
H2O + H2
Next Nickel-Zirconia Cermet CathodeH2O
H2
Porous Anode, Strontium -doped Lanthanum Manganite
Gastight Electrolyte, Yttria-Stabilized Zirconia
Porous Cathode, Nickel -Zirconia cermet
2 H20 + 4 e- 2 H2 + 2 O=
2 O= O2 + 4 e-
2 O=
H2O
H2
O2
4 e-
2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 10 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H2
Interconnection
H2O + H2
Next Nickel-Zirconia Cermet CathodeH2O
H2
Porous Anode, Strontium -doped Lanthanum Manganite
Gastight Electrolyte, Yttria-Stabilized Zirconia
Porous Cathode, Nickel -Zirconia cermet
2 H20 + 4 e- 2 H2 + 2 O=
2 O= O2 + 4 e-
2 O=
H2O
H2
O2
4 e-
Interconnection
H2O + H2
Next Nickel-Zirconia Cermet CathodeH2O
H2
Porous Anode, Strontium -doped Lanthanum Manganite
Gastight Electrolyte, Yttria-Stabilized Zirconia
Porous Cathode, Nickel -Zirconia cermet
2 H20 + 4 e- 2 H2 + 2 O=
2 O= O2 + 4 e-
2 O=
H2O
H2
O2
4 e-
2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 2 2 290 v/o H O + 10 v/o H90 v/o H O + 10 v/o H90 v/o H O + 10 v/o H90 v/o H O + 10 v/o H2 10 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H210 v/o H2O + 90 v/o H2
Interconnection
H2O + H2
Next Nickel-Zirconia Cermet CathodeH2O
H2
Sulfur-iodine cycle
High temperature electrolysis
14
• Fuel and fuel cycle– Particle fuel irradiations and fission product monitoring
• Materials– Codes and standards extension– Materials database extension– Graphite dust behavior
• Hydrogen production– Sulfur-iodine cycle– High temperature electrolysis– Coupling of H2 production process and reactor heat transport system– Tritium transport
• Computational Methods• Components and helium turbine
– Intermediate heat exchanger
VHTR Technology Interests
15
Lead-Cooled Fast Reactor (LFR)Characteristics
• Pb or Pb/Bi coolant• 550C to 800C outlet temperature• Small transportable system 50-
150 MWe, and• Larger station 300-1200 MWe• 15–30 year core life option
Benefits• Distributed electricity generation• Hydrogen and potable water• Replaceable core for regional
fuel processing• High degree of passive safety• Proliferation resistance through
long-life core
http://www.gen-4.org/Technology/systems/index.htm
16
LFR Reactor Options
Small, transportable module
CLOSURE HEAD
CO2 INLET NOZZLE (1 OF 4)
CO2 OUTLET NOZZLE (1 OF 8)
Pb-TO-CO2 HEAT EXCHANGER (1 OF 4)
ACTIVE CORE AND FISSION GAS PLENUM
RADIAL REFLECTOR
FLOW DISTRIBUTOR HEAD
FLOW SHROUDGUARD VESSEL
REACTOR VESSEL
CONTROL ROD DRIVES
CONTROL ROD GUIDE TUBES AND DRIVELINES
THERMAL BAFFLE
Large, stationary plant
• Pb coolant (both)• No intermediate loops
17
• Collaborations based on ELSY and SSTAR – No formal agreement yet
• Conceptual design and safety – Innovative components and design
– Compact, in-vessel steam generators– Decay heat removal by air and water– Refueling ‘out-of-Pb’ coolant
– Innovative structural design– Buoyant fuel element support– Seismic isolation of reactor building
• Fuel and core materials– Many options
LFR Technology Interests
ELSY: European Lead-cooled System; SSTAR: Small Secure Transportable Autonomous Reactor
18
Supercritical-Water-Cooled Reactor (SCWR)Characteristics
• Water coolant above supercritical conditions (374C, 22.1 MPa)
• 510-625C outlet temperature• 1500 MWe• Pressure tube or pressure
vessel options• Simplified balance of plant
Benefits• Efficiency near 45% with
excellent economics• Leverages the current
experience in operating fossil- fueled supercritical steam plants
• Configurable as a fast- or thermal-spectrum core
http://www.gen-4.org/Technology/systems/index.htm
19
Gas-Cooled Fast Reactor (GFR)Characteristics
• He coolant• 850C outlet temperature• Direct gas-turbine cycle or
supercritical CO2 cycle with optional combined cycles
• 2400 MWth / 1100 MWe• Several fuel options
– Carbide in plates or pins– Nitride– Oxide
Benefits• High efficiency• Waste minimization and
efficient use of uranium resources
http://www.gen-4.org/Technology/systems/index.htm
20
Molten Salt Reactor (MSR)Characteristics
• Fuel is liquid fluorides of U or Th with Li, Be, Na and other fluorides
• 700–800C outlet temperature• 1000 MWe• Low pressure (<0.5 MPa)
Benefits• Waste minimization• Avoids fuel development• Proliferation resistance through
low fissile material inventory
http://www.gen-4.org/Technology/systems/index.htm
21
OrganizationPolicy Group
Chair (France)
Chair
System Steering Committees
Co-Chairs
Project Management Boards
(multiple R&D projects)
Methodology Working Groups
Proliferation Resistance and Physical Protection,
Risk & Safety, Economics
Policy Secretariat
Policy TechnicalDirector Director
NEA, Paris
Technical Secretariat
Experts Group
Senior IndustryAdvisory Panel
http://www.gen-4.org/GIF/Governance/index.htm
22
System Partners
VHTR – Very-High-Temperature ReactorGFR – Gas-Cooled Fast ReactorSFR – Sodium-Cooled Fast ReactorSCWR – Supercritical Water-Cooled ReactorLFR – Lead-Cooled Fast ReactorMSR – Molten Salt Reactor
Mar 2009
ANRE – Agency for Natural Resources and Energy (JP)CAEA – China Atomic Energy Authority (CN)CEA – Commissariat à l’Énergie Atomique (FR)DME – Department of Minerals and Energy (ZA)DOE – Department of Energy (US)JAEA – Japan Atomic Energy Agency (JP)JRC – Joint Research Centre (EU)KOSEF – Korean Science and Engineering Foundation (KR)MEST – Ministry of Education, Science and Technology (KR)MOST – Ministry of Science and Technology (CN)NRCan – Natural Resources Canada (CA)PSI – Paul Scherrer Institute (CH)
http://www.gen-4.org/GIF/Governance/system.htm
Partners: NRCan JRC CEA JAEA, MEST, PSI DOE CAEA, DME ANRE KOSEF MOST
VHTR
GFR
SFR
LFR
MSR
SCWR
23
Generation IV Annual Report• Captures key information and accomplishments
from System Steering Committee annual reports into one widely distributed report
• Captures brief summaries of working groups’ accomplishments, and background on the Forum
• Audience includes:– World-wide Research and Development
Community– Governments sponsoring Generation IV R&D– GIF committees, boards and working groups
• The 2008 Report has just issued
http://www.gen-4.org/PDFs/GIF_2008_Annual_Report.pdf
24
Working Toward the FutureThe GIF joined together to help assure a sustainable energy future• Underscored by the advance of global climate change• Based on advanced nuclear energy systems that are sustainable,
safe, economical, proliferation resistant and physically secure• Accelerated by the collaboration of the GIF members, industry,
academia and non-member nations and institutions
25
Bibliography• The web links provided on most slides lead to source
documents, background materials or updates• The full Generation IV Roadmap and all supporting documents
are available at: http://gif.inel.gov/roadmap/• Some technical papers are listed on the OECD NEA website (GIF
website) at www.gen-4.org within each system• Recent outlook articles on nuclear deployment:
– IEA http://www.iea.org/weo/2008.asp (subscription)– NEA http://www.nea.fr/neo/ (subscription)– IAEA http://www-pub.iaea.org/MTCD/publications/PDF/RDS1-28_web.pdf– WNA http://www.world-nuclear.org/outlook/clean_energy_need.html– EPRI (US R&D strategy and deployment outlook, respectively)
http://my.epri.com/portal/server.pt?Product_id=000000000001018514.pdf– http://my.epri.com/portal/server.pt?Product_id=000000000001018431.pdf
• My contact information:– ralph.bennett@inl.gov
top related