History of fast reactors (Alan Waltar)

History of Fast Reactor Development in the World Alan E. Waltar Senior Advisor, Columbia Basin Consulting Group Senior Advisor, Pacific Northwest National Laboratory (Retired) Professor and Head, Department of Nuclear Engineering, Texas A&M University (Retired) Past President and Fellow, American Nuclear Society Fast Reactors School for Young Engineers Central Institute for Continuing Education and Training (CICI&T) Obninsk, Russia June 24, 2013

Outline I. Basic Rationale for Fast Reactors II. Early Experimental Fast Reactors III. Large-Scale Experimental Fast Reactors IV. Demonstration Fast Reactors V. Commercial Fast Reactors VI. Nation by Nation Progress Review VII. Global View VIII. Perspective

Fission 1932 - 1942 1932: Chadwick discovers neutron 1938 : Fermi plays with neutrons & U.

Hahn-Meitner say «fission !»

1939 : Joliot et al. «chain reaction» 1942 : Staggs Field

Compliments of B. Baare

I. Basic Rationale for Fast Reactors Relative World Energy Resources Fossil Fuels and Uranium

Uranium Natural Gas

Oil

Uranium Fast Reactors

Today’s Reactors

Coal

America the Powerless, Alan E. Waltar, Med. Phys. Publ., 1995

200 t U/GWe.y

~1 t U/GWe.y

Source: “A Technology Roadmap for Generation IV Nuclear Energy Systems”, December 2002 F.Carre, World Nuclear University Summer Institute University of Oxford - July 18, 2012

Fast Neutron Spectrum Needed for Breeding and Resource Utilization

High Fission Neutron Yield Necessary for Breeding

Fast Neutrons Needed to Fission Fertile Isotopes

Fast Spectrum Systems Need Relatively High Enrichment (Because of Small Fissile Cross Sections)

Hexagonal Geometry Enhances the Fuel Content Liquid Metal Coolant Also Allows Small Diameter Pins

For Sodium Systems, Intermediate Loop Needed to Ensure Steam Loop Does Not Become Radioactive

Na-23

Na-24 (15-hr hard gamma) Na-22 (2.6-yr)

POOL Configuration 1960s: 1970s: 1980s: 2010s:

EBR-II Phenix; PFR BN-600; Super Phenix CEFR

LOOP Configuration 1940s: Clementine 1950s: EBR-I; BR-10; DFR 1960s: LAMPRE, FERMI; Rapsodie, BOR-60; SEFOR 1970s: KNK-II; BN-350; JOYO 1980s: FFTF; FBTR 1990s: MONJU

Generation IV International Forum: Six Systems for R&D GIF Selection of six Nuclear Systems

Sodium Fast Reactor Lead Fast Reactor Gas Fast Reactor

Very High Temperature Reactor Compliments of F.Carre

Super Critical Water Reactor

Molten Salt Reactor

II. Early Experimental Fast Reactors Reactor Year Critical Clementine 1946 EBR-I 1951 BR-10 1958 LAMPRE 1961 SEFOR 1968

Size (MWth) 0.025 1.2 8 1

Country USA USA Russia USA USA

III. Large Experimental Fast Reactors Reactor

Year Critical

Size MWth

DFR EBR-II FERMI RAPSODIE BOR-60 KNK-II JOYO FFTF FBTR CEFR

1958 1961 1963 1967 1968 1972 1977 1980 1985 2010

55 62.5 200 40 55 58 140 400 40 65

Country MWe

12 20 61 0 12 20 0 0 13 23.4

UK USA USA France Russia Germany Japan USA India China

IV. Demonstration Fast Reactors Reactor

Year Critical

Size MWth

Country MWe

BN-350 1972 750 130 Russia PHENIX 1973 563 255 France PFR 1974 650 250 UK MONJU 1994 714 280 Japan BN-600 1980 1470 600 Russia PFBR 1250 500 India ------------------------------------SNR-300 762 327 Germany CRBRP 975 380 USA KALIMER 150 392 162 Korea

V. Commercial Fast Reactors Reactor Year Critical Size SUPER PHENIX 1985 BN-800 2015 BN-1600 DFBR CDFR SNR-2 EFR ALMR JSFR-1500 BREST-1200

Country

MWth

MWe

2990 2100 4200 1600 3800 3420 3600 840 3530 2800

1242 870 1600 660 1500 1492 1580 303 1500 1200

France Russia Russia Japan UK Germany EU USA Japan Russia

VI. Nation by Nation Progress Review Russia United States United Kingdom France NOTES: Germany 1) All fluxes shown in the following tables are x 10 Japan 2) Some fuel smear densities are reported as 100%. In such cases, the India number more closely represents the theoretical density of the fuel form.

China Korea 15

Russia • • • • • • •

BN-5/10 BOR-60 BN-350 BN-600 BN-800 BN-1600 BREST-1200

BN-5/10

• Russian Fast Reactor Program Launched at Obninsk • Early Studies of UN and UC Fuel

Criticality 1958 Full Power 1959 MWth 8 MWe 0 Coolant Na Coolant Velocity (m/s) 4.0 Configuration Loop Inlet Core Temp.(C) 350 Outlet Core Temp. (C) 470 Fuel UN Enrichment 90 Fuel Form Smear Density (%) 82 Core Diameter (m) 0.21 Active Fuel Height (m) 0.4 # Core Assemblies 90 # Total Assemblies 124 Pins/Assembly 7 Plenum Location Peak Flux (n/cm2 sec) 0.86 Ave. Flux (n/cm2 sec) 0.63 Peak Lin. Power (KW/m) 44 Ave. Lin. Power (KW/m) 32 Clad Material Cr1Ni15Mo3Nb Duct Material Cr1Ni15Mo3Nb Fuel Cycle (days) 100

BOR-60

• • • •

Major Materials Test Facility Located at RIAR in Dmitrovgrad Production of Radioisotopes Only Fast Reactor Test Facility Operating Today

Criticality 1968 Full Power 1970 MWth 55 MWe 12 Coolant Na Coolant Velocity (m/s) 11 Configuration Loop Inlet Core Temp.(C) 330 Outlet Core Temp. (C) 545 Fuel MOX Enrichment 56-90 Fuel Form Annular Smear Density (%) Core Diameter (m) 0.46 Active Fuel Height (m) 0.45 # Core Assemblies 114 # Total Assemblies 252 Pins/Assembly 37 Plenum Location Bottom Peak Flux (n/cm2 sec) 3.7 Ave. Flux (n/cm2 sec) 3.0 Peak Lin. Power (KW/m) 54 Ave. Lin. Power (KW/m) 40 Clad Material Cr15Ni15 Duct Material SS Fuel Cycle (days) 100

BN-350

• Dual Purpose Reactor -- Electricity (130 MWe) -- Desalination (80,000 tonnes of fresh water per day)

• Located on the Caspian Sea (Kazakhstan) • Shut Down in 1099

Criticality 1972 Full Power 1973 MWth 750 MWe 130* Coolant Na Coolant Velocity (m/s) 7.4 Configuration Loop Inlet Core Temp.(C) 280 Outlet Core Temp. (C) 430 Fuel UO2 Enrichment 17/26 Fuel Form Annular Smear Density (%) 100 Core Diameter (m) 1.58 Active Fuel Height (m) 1.0 # Core Assemblies 161 # Total Assemblies 268 Pins/Assembly 127 Plenum Location Top Peak Flux (n/cm2 sec) 5.4 Ave. Flux (n/cm2 sec) 3.5 Peak Lin. Power (KW/m) 40 Ave. Lin. Power (KW/m) 24 Clad Material Cr16Ni15Mo2 Duct Material Cr13MnNb Fuel Cycle (days) 105 * 150 Mwe Desalination

BN-600

• Centerpiece of Russian Fast Reactor Program -- Operated well early in life with considerable failed fuel -- Now best operating record of all Russian Nuclear Power Plants

• Located at Belohyarsk Nuclear Power Station • Life Extension Plans Underway

Criticality 1980 Full Power 1981 MWth 1470 MWe 600 Coolant Na Coolant Velocity (m/s) 8.0 Configuration Pool Inlet Core Temp.(C) 365 Outlet Core Temp. (C) 550 Fuel UO2/MOX Enrichment 17/26 Fuel Form Annular Smear Density (%) 100 Core Diameter (m) 2.05 Active Fuel Height (m) 1.03 # Core Assemblies 275 # Total Assemblies 827 Pins/Assembly 127 Plenum Location Bottom Peak Flux (n/cm2 sec) 6.5 Ave. Flux (n/cm2 sec) 4.3 Peak Lin. Power (KW/m) 47 Ave. Lin. Power (KW/m) 28 Clad Material Cr16Ni15Mo2+MnTiSi Duct Material Cr13MnNb Fuel Cycle (days) 160

BN-600 Turbine Bay with palm trees and a grape vineyard!

BN-800

• Under construction at Beloyarsk NNP • Goals: -- Produce 870 MW of electricity -- Burn up 1/7 tonnes of Pu/year

• In 2009, two BN-800 plants sold to China

Criticality ~2015 Full Power MWth 2100 MWe 870 Coolant Na Coolant Velocity (m/s) 7.3 Configuration Pool Inlet Core Temp.(C) 354 Outlet Core Temp. (C) 544 Fuel MOX/Metal Enrichment 19.5/24.7 Fuel Form Annular Smear Density (%) 100 Core Diameter (m) 2.56 Active Fuel Height (m) 0.88 # Core Assemblies 409 # Total Assemblies 1045 Pins/Assembly 127 Plenum Location Peak Flux (n/cm2 sec) 8.8 Ave. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 48 Ave. Lin. Power (KW/m) 31 Clad Material Cr16Ni15Mo2MnTiSi (CW) Duct Material Fuel Cycle (days) 140

BN-800

BN-1600

• Design for Large Commercial Plant -- Larger than Super Phenix

• Start with MOX • Later switch to Nitride to improve BR

Criticality Full Power MWth 4200 MWe 1600 Coolant Na Coolant Velocity (m/s) 5.7 Configuration Pool Inlet Core Temp.(C) 395 Outlet Core Temp. (C) 550 Fuel MOX/Nitride Enrichment 18.2/21.1 Fuel Form Annular Smear Density (%) 100 Core Diameter (m) 4.45 Active Fuel Height (m) 0.78 # Core Assemblies 474 # Total Assemblies 1645 Pins/Assembly 331 Plenum Location Peak Flux (n/cm2 sec) 5.5 Ave. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 48.7 Ave. Lin. Power (KW/m) 30 Clad Material Cr16Ni15Mo2MnTiSi (CW) Duct Material Fuel Cycle (days) 330

BREST-1200

• Large Lead-Cooled Reactor Design -- Higher boiling Temp. than Na -- No air/water Interactions -- Very low void coefficient

• NIKIT design based on Alfa Class Submarines • Likely Pb/Bi Eutectic to Lower Melting Point • Need Careful Oxygen Control to Prevent Corrosion

Criticality Full Power MWth 2800 MWe 1200 Coolant Pb Coolant Velocity (m/s) <2.0 Configuration Pool Inlet Core Temp.(C) 420 Outlet Core Temp. (C) 540 Fuel PuN-UN-MA Enrichment 13.8 Fuel Form Smear Density (%) 75 Core Diameter (m) 4.74 Active Fuel Height (m) 1.1 # Core Assemblies 256 # Total Assemblies 464 Pins/Assembly 272 Plenum Location Peak Flux (n/cm2 sec) 3.8 Ave. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 42 Ave. Lin. Power (KW/m) Clad Material Ferritic-martensitic SS Duct Material Fuel Cycle (days) 300

United States Clementine • EBR-I • LAMPRE • SEFOR • EBR-II • FERMI • FFTF • CRBRP • ALMR •

Clementine • First Reactor in the World to Operate with Fast Neutrons

• Produced Fast Neutrons for Early Physics Experiments • Used Mercury as a Coolant • Deliberately Destroyed at End of Life to Study Dynamics of Fast Spectrum Systems

Criticality 1946 Full Power 1949 MWth 0.025 MWe 0 Coolant Hg Configuration Loop Coolant Velocity (m/s) Inlet Core Temp.(C) 38 Outlet Core Temp. (C) 121 Fuel Pu Enrichment Fuel Form Rods Smear Density (%) Core Diameter (m) 0.15 Active Fuel Height (m) 0.14 # Core Assemblies # Total Assemblies Pins/Assembly Plenum Location Peak Flux (n/cm2 sec) 0.004 Ave. Flux (n/cm2 sec) Peak Lin. Power (KW/m) Ave. Lin. Power (KW/m) Clad Material Duct Material Fuel Cycle (days)

EBR-I

• First Reactor in

the World to Send Electricity to the Grid

• Melted During an Exercise to Test Structural Feedback Characteristics • Contributed Major Insight on the Design of Core Restraint Systems • Decommissioned in 1964

Criticality 1951 Full Power 1951 MWth 1.2 MWe 0.2 Coolant NaK Configuration Loop Coolant Velocity (m/s) Inlet Core Temp.(C) 230 Outlet Core Temp. (C) 322 Fuel Enrich. U Enrichment Fuel Form Solid Smear Density (%) Core Diameter (m) 0.18 Active Fuel Height (m) 0.22 # Core Assemblies # Total Assemblies Pins/Assembly Plenum Location Peak Flux (n/cm2 sec) 0.11 Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) Ave. Lin. Power (KW/m) Clad Material Duct Material Fuel Cycle (days)

1951 : EBR 1 Lights its Building

LAMPRE, Los Alamos, USA

•

Only Fast Reactor in the World to Operate With Liquid Fuel

• Fueled with Liquid Plutonium

Criticality 1961 Full Power 1961 MWth 1.0 MWe Coolant Na Configuration Loop Coolant Velocity (m/s) Inlet Core Temp.(C) 450 Outlet Core Temp. (C) 560 Fuel Molten Pu Enrichment Fuel Form Smear Density (%) Core Diameter (m) 0.16 Active Fuel Height (m) 0.15 # Core Assemblies # Total Assemblies Pins/Assembly Plenum Location Peak Flux (n/cm2 sec) Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) Ave. Lin. Power (KW/m) Clad Material Duct Material Fuel Cycle (days)

SEFOR, Arkansas, USA

• Built in Arkansas to Study Doppler Feedback in Oxide Fueled Fast Reactors • Results Matched Calculations Exceedingly Well • Shut Down After Mission Completed -- about one year later

Criticality 1969 Full Power 1971 MWth 20 MWe Coolant Na Configuration Loop Coolant Velocity (m/s) Inlet Core Temp.(C) 370 Outlet Core Temp. (C) 430 Fuel MOX Enrichment Fuel Form Solid Smear Density (%) Core Diameter (m) 0.88 Active Fuel Height (m) 0.93 # Core Assemblies # Total Assemblies Pins/Assembly Plenum Location Peak Flux (n/cm2 sec) 0.6 Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) Ave. Lin. Power (KW/m) Clad Material Duct Material Fuel Cycle (days)

EBR-II.

Idaho Falls, USA • Major Fast Reactor Test Facility • Demonstrated Complete SodiumCooled Fast Reactor with Plant On-Site for Reprocessing Metal Fuel

• Qualified Metal Fuel as Viable Fast Reactor

Fuel for High Burnups • Successfully Performed Unprotected Transient Overpower, Loss of Flow, and Loss of Heat Sink Experiments • Prototype for IFR System (up to 19% burnup) • Shut Down in 1994 After Three Decades

Criticality 1961 Full Power 1965 MWth 62.5 MWe 20 Coolant Na Configuration Pool Coolant Velocity (m/s) 8.0 Inlet Core Temp.(C) 371 Outlet Core Temp. (C) 473 Fuel U-Zr Enrichment 67 Fuel Form Fissium Smear Density (%) 75 Core Diameter (m) 0.697 Active Fuel Height (m) 0.343 # Core Assemblies 127 # Total Assemblies 637 Pins/Assembly 91 Plenum Location Top Peak Flux (n/cm2 sec) 2.7 Peak. Flux (n/cm2 sec) 1.6 Peak Lin. Power (KW/m) 34.8 Ave. Lin. Power (KW/m) 23 Clad Material 316 SS Duct Material SS Fuel Cycle (days) 49

EBR-II

1988 Passive Safety Test for Unprotected Loss of Flow Accident (Metal Fuel)

FERMI, Detroit, Michigan

• Suffered Meltdown of Several Assemblies When Cooling Fin from “Core Catcher” Sheered Off and Blocked Coolant Inlet • Initially Fueled with Metal Fuel • Refurbished with Oxide Fuel After Accident but Shut Down Shortly Thereafter in 1972

Criticality 1963 Full Power 1970 MWth 200 MWe 61 Coolant Na Configuration Loop Coolant Velocity (m/s) 4.8 Inlet Core Temp.(C) 288 Outlet Core Temp. (C) 565 Fuel U-10Mo Enrichment 25.6 Fuel Form Fissium Smear Density (%) 100 Core Diameter (m) 0.831 Active Fuel Height (m) 0.775 # Core Assemblies 105 # Total Assemblies 858 Pins/Assembly 140 Plenum Location Peak Flux (n/cm2 sec) 4.5 Peak. Flux (n/cm2 sec) 2.6 Peak Lin. Power (KW/m) 28 Ave. Lin. Power (KW/m) 17 Clad Material Zr Duct Material SS Fuel Cycle (days) 14

FERMI

Metal Fin Forced Against Coolant Inlet, Blocking Flow to Several Assemblies Metal Cooling Fin Sheered Off Near Bottom of Vessel

FFTF (Fast Flux Text Facility), Richland, Washington, USA

• The Largest, Most Heavily Instrumented Fast Reactor Test Facility in the World

• Achieved World-Class Fuel Burnup and Cladding Exposure; Successful passive safety test program • Political Decision to Shut Down in 1993 after just over a Decade of High Success Rate • Liquid Sodium Drained and Backfilled with Inert Gas

Criticality 1980 Full Power 1980 MWth 400 MWe 0 Coolant Na Configuration Loop Coolant Velocity (m/s) 7.4 Inlet Core Temp.(C) 360 Outlet Core Temp. (C) 565 Fuel MOX Enrichment 20.3/24.6 Fuel Form Solid Smear Density (%) 85.5 Core Diameter (m) 1.202 Active Fuel Height (m) 0.914 # Core Assemblies 82 # Total Assemblies 190 Pins/Assembly 217 Plenum Location Top Peak Flux (n/cm2 sec) 7.2 Peak. Flux (n/cm2 sec) 4.2 Peak Lin. Power (KW/m) 40.1 Ave. Lin. Power (KW/m) 27.6 Clad Material 316 SS 20%CW Duct Material SS Fuel Cycle (days) 107

FFTF (Fast Flux Test Facility)

220 MWd/kg

Achieved High Fuel Burnup for MOX Fuel

CRBRP, Designed for Clinch River, Tennessee, USA

• Intended as the Next Step in the U.S. Fast Reactor Program • Completed Preliminary Safety Analysis Report • Accomplished Ground Breaking • Political Decision to Shut Down

Criticality Full Power MWth 975 MWe 380 Coolant Na Configuration Loop Coolant Velocity (m/s) 7.3 Inlet Core Temp.(C) 388 Outlet Core Temp. (C) 535 Fuel MOX Enrichment 32.8 Fuel Form Solid Smear Density (%) 83.2 Core Diameter (m) 2.02 Active Fuel Height (m) 0.914 # Core Assemblies 156 # Total Assemblies 594 Pins/Assembly 217 Plenum Location Top Peak Flux (n/cm2 sec) 5.5 Peak. Flux (n/cm2 sec) 3.6 Peak Lin. Power (KW/m) 48 Ave. Lin. Power (KW/m) 27 Clad Material 316 SS 20%CW Duct Material HT9 Fuel Cycle (days) 275

ALMR

• The First Mid-Sized U.S. Fast Reactor to be Fueled with Metal Fuel • Design Has Become the PRISM Reactor (to be discussed in 2nd Presentation

Criticality Full Power MWth 840 MWe 303 Coolant Na Configuration Loop Coolant Velocity (m/s) 5.3 Inlet Core Temp.(C) 358 Outlet Core Temp. (C) 498 Fuel UPuZr Enrichment 23.2 Fuel Form Smear Density (%) 82.7 Core Diameter (m) 2.164 Active Fuel Height (m) 1.07 # Core Assemblies 92 # Total Assemblies 272 Pins/Assembly 271 Plenum Location Peak Flux (n/cm2 sec) 3.3 Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 31 Ave. Lin. Power (KW/m) 19 Clad Material HT9 Duct Material HT9 Fuel Cycle (days)

United Kingdom • DFR • PFR • CDFR

DFR, Dounrey, UK • The First British Entry Into the Fast Reactor Domain

• Built in the Highlands of Scotland --- Northern Tip of the British Isles • Ran Successfully for Many Years • Mainly Known for the Discovery of Cladding Swelling (a phenomenon that almost stopped fast rector development)

• Shut Down in 1977

Criticality 1959 Full Power 1963 MWth 60 MWe 15 Coolant NaK Configuration Loop Coolant Velocity (m/s) 6.0 Inlet Core Temp.(C) 230 Outlet Core Temp. (C) 350 Fuel U-Mo Enrichment 75 Fuel Form Annular Smear Density (%) 100 Core Diameter (m) 0.530 Active Fuel Height (m) 0.530 # Core Assemblies 342 # Total Assemblies 2214 Pins/Assembly 1 Plenum Location Top Peak Flux (n/cm2 sec) 2.5 Peak. Flux (n/cm2 sec) 1.9 Peak Lin. Power (KW/m) 37 Ave. Lin. Power (KW/m) 25 Clad Material Nb Duct Material Fuel Cycle (days) 55

Dounrey Fast Reactor (DFR), United Kingdom

PFR, Dounrey, UK

• First Demonstration Fast Reactor for the U.K. • Generally Successful Operation; demonstrated cooling by natural convection; some steam generator problems • Shut Down in 1994

Criticality 1974 Full Power 1977 MWth 650 MWe 250 Coolant Na Configuration Pool Coolant Velocity (m/s) 9.0 Inlet Core Temp.(C) 399 Outlet Core Temp. (C) 550 Fuel MOX Enrichment 22.0/28.5 Fuel Form Smear Density (%) 100 Core Diameter (m) 1.47 Active Fuel Height (m) 0.914 # Core Assemblies 72 # Total Assemblies 207 Pins/Assembly 169-325 Plenum Location Bottom Peak Flux (n/cm2 sec) 7.6 Peak. Flux (n/cm2 sec) 5.0 Peak Lin. Power (KW/m) 48 Ave. Lin. Power (KW/m) 27 Clad Material 316 SS Duct Material PE16/FV4-18 Fuel Cycle (days) 90

CDFR, U.K.

•

Intended as the British Commercial Fast Reactor

• Design for Larger than Super Phenix

Criticality Full Power MWth 3800 MWe 1500 Coolant Na Configuration Pool Coolant Velocity (m/s) 7.0 Inlet Core Temp.(C) 370 Outlet Core Temp. (C) 540 Fuel MOX Enrichment 15.0/20.5 Fuel Form Smear Density (%) 100 Core Diameter (m) 3.00 Active Fuel Height (m) 1.15 # Core Assemblies 349 # Total Assemblies 583 Pins/Assembly 325 Plenum Location Peak Flux (n/cm2 sec) 10.0 Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 43 Ave. Lin. Power (KW/m) 28 Clad Material PE16 Duct Material Fuel Cycle (days) 270

France • RAPSODIE

• PHENIX • SUPER-PHENIX • EFR

Rapsodie, Cadarche, France

• The First French Fast Reactor • Generated Valuable Physics and Fuel Data for MOX Type Fuel

• Upgraded from 20 MWth to 40 MWth • Shut Down in 1982

Criticality 1967 Full Power 1967 MWth 40 MWe 0 Coolant Na Configuration Loop Coolant Velocity (m/s) 5.5 Inlet Core Temp.(C) 400 Outlet Core Temp. (C) 510 Fuel MOX Enrichment 30 Fuel Form Solid Smear Density (%) 88 Core Diameter (m) 0.446 Active Fuel Height (m) 0.320 # Core Assemblies 73 # Total Assemblies 560 Pins/Assembly 61 Plenum Location Peak Flux (n/cm2 sec) 3.2 Peak. Flux (n/cm2 sec) 2.3 Peak Lin. Power (KW/m) 43 Ave. Lin. Power (KW/m) 31 Clad Material 316 SS Duct Material SS Fuel Cycle (days) 80

PHENIX, Marcoule, FRANCE

• The Main “Work Horse” for the French Fast Reactor Program • Performed Global Fuel Irradiation Testing • A Reactivity Anomaly Occurred in Mid-Life -- Ran at only 140 MWe after restart -- Transmutation of Nuclear Waste • Ran for about 35 Years (Shut Down in 2010)

Criticality 1973 Full Power 1974 MWth 563* MWe 255 Coolant Na Configuration Pool Coolant Velocity (m/s) 12 Inlet Core Temp.(C) 395 Outlet Core Temp. (C) 560 Fuel MOX Enrichment 18/23 Fuel Form Solid Smear Density (%) 85 Core Diameter (m) 1.39 Active Fuel Height (m) 0.85 # Core Assemblies 103 # Total Assemblies 1510 Pins/Assembly 217 Plenum Location Top & Bottom Peak Flux (n/cm2 sec) 6.8 Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 45 Ave. Lin. Power (KW/m) 27 Clad Material Cr17Ni13Mo2.5Mn1.5TiSi Duct Material 316 SS Fuel Cycle (days) 90

Super-Phenix, Creys-Malville, France

• Billed as the Commercial Fast Reactor of the Future • Reactor Itself Ran Well • Problems were in the Balance of Plant -- collapse of turbine bay roof -- leak in the fuel storage vessel

• Shut Down in 1998 for High Cost and Politics

Criticality 1985 Full Power 1986 MWth 2990 MWe 1242 Coolant Na Configuration Pool Coolant Velocity (m/s) 7.7 Inlet Core Temp.(C) 395 Outlet Core Temp. (C) 542 Fuel MOX Enrichment 16/19.7 Fuel Form Smear Density (%) 82.6 Core Diameter (m) 3.70 Active Fuel Height (m) 1.00 # Core Assemblies 364 # Total Assemblies 1886 Pins/Assembly 271 Plenum Location Peak Flux (n/cm2 sec) 6.1 Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 48 Ave. Lin. Power (KW/m) 30 Clad Material Cr17Ni13Mo2.5Mn1.5TiSi Duct Material Fuel Cycle (days)

SUPER-PHENIX

SUPER-PHENIX TURBINE BAY ROOF COLLAPSE

EFR, European Fast Reactor

• The European Design for a Commercial Fast Reactor • France is the Leading Party • Strong Attention to Safety

Criticality Full Power MWth 3600 MWe 1590 Coolant Na Configuration Pool Coolant Velocity (m/s) 7.8 Inlet Core Temp.(C) 395 Outlet Core Temp. (C) 545 Fuel PuO2-UO2 Enrichment 18.3/26.9 Fuel Form Smear Density (%) 82.7 Core Diameter (m) 4.051 Active Fuel Height (m) 1.00 # Core Assemblies 279 # Total Assemblies 1230 Pins/Assembly 331 Plenum Location Peak Flux (n/cm2 sec) 5.3 Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 52 Ave. Lin. Power (KW/m) 26 Clad Material PE16 Duct Material Euralloy Fuel Cycle (days) 425

Germany • KNK-II • SNR-300 • SNR-2

KNK-II, Karlsruhe, Germany

• A Fast Spectrum Core was Placed into the Center of an Original Thermal Spectrum Reactor

• Valuable Data were Obtained for the German Fast Reactor Program • Shut Down Occurred in 1991

Criticality 1972 Full Power 1978 MWth 58 MWe 20 Coolant Na Configuration Loop Coolant Velocity (m/s) Inlet Core Temp.(C) 360 Outlet Core Temp. (C) 525 Fuel MOX Enrichment 88/95 Fuel Form Annular Smear Density (%) 80 Core Diameter (m) 0.824 Active Fuel Height (m) 0.6 # Core Assemblies 29 # Total Assemblies 436 Pins/Assembly 169/211 Plenum Location Peak Flux (n/cm2 sec) 1.9 Peak. Flux (n/cm2 sec) 1.3 Peak Lin. Power (KW/m) 45 Ave. Lin. Power (KW/m) 24 Clad Material 1.4970 Duct Material SS Fuel Cycle (days)

SNR-300, Kalkar,Germany

• This Demonstration Plant was Completed and Ready for Fuel Loading When Political Pressures Forced Abandonment • The Site is Now Used as an Amusement Park Along the Rhine River

Criticality Full Power MWth 762 MWe 327 Coolant Na Configuration Loop Coolant Velocity (m/s) 5 Inlet Core Temp.(C) 377 Outlet Core Temp. (C) 546 Fuel MOX Enrichment 25/36 Fuel Form Solid Smear Density (%) 80 Core Diameter (m) 1.78 Active Fuel Height (m) 0.95 # Core Assemblies 199 # Total Assemblies 481 Pins/Assembly 127 Plenum Location Peak Flux (n/cm2 sec) 6.7 Peak. Flux (n/cm2 sec) 4.9 Peak Lin. Power (KW/m) 36 Ave. Lin. Power (KW/m) 23 Clad Material X10CrNiMoTiB15 Duct Material SS Fuel Cycle (days) 588

SNR-2, Germany

• Intended to be the German Commercial-Scale Fast Reactor • Efforts Have Ceased Due to the Political Situation in Germany

Criticality Full Power MWth 3420 MWe 1497 Coolant Na Configuration Pool Coolant Velocity (m/s) Inlet Core Temp.(C) 390 Outlet Core Temp. (C) 540 Fuel PuO2-UO2 Enrichment 18/23 Fuel Form Smear Density (%) 87 Core Diameter (m) 4.13 Active Fuel Height (m) 1.00 # Core Assemblies 414 # Total Assemblies 984 Pins/Assembly 271 Plenum Location Peak Flux (n/cm2 sec) 5.4 Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 45 Ave. Lin. Power (KW/m) Clad Material Duct Material Fuel Cycle (days) 365

Japan • JOYO

• MONJU • DFBR • JSFR-1500

JOYO, Tokai, Japan

• A Major Fast Reactor Test Facility • Upgraded from 75 MWth to 140 MWth • Ran Well for Many Years • Suffered a Fuel Loading Accident in 2007 -- Not Clear that the Reactor can be Restarted

Criticality 1977 Full Power 1977 MWth 140 MWe 0 Coolant Na Configuration Loop Coolant Velocity (m/s) 6.1 Inlet Core Temp.(C) 350 Outlet Core Temp. (C) 500 Fuel MOX Enrichment 30/34 Fuel Form Solid Smear Density (%) 87 Core Diameter (m) 0.80 Active Fuel Height (m) 0.50 # Core Assemblies 85 # Total Assemblies 308 Pins/Assembly 127 Plenum Location Top Peak Flux (n/cm2 sec) 5.7 Peak. Flux (n/cm2 sec) 3.5 Peak Lin. Power (KW/m) 42 Ave. Lin. Power (KW/m) Clad Material 316 20%CW Duct Material 316 20%CW Fuel Cycle (days) 60

MONJU, Tsuruga City, Japan • Key Reactor for Japanese Fast Reactor Program • Serious Sodium Leak & Fire in Secondary Loop in December 1995

• Caused by Thermocouple Break • Shortly After Restart (May 2011), an Accident Occurred Due to Design Defect in Grappling Machine • Reactor Remains Shut Down

Criticality 1994 Full Power 1996 MWth 714 MWe 280 Coolant Na Configuration Loop Coolant Velocity (m/s) 6.9 Inlet Core Temp.(C) 397 Outlet Core Temp. (C) 529 Fuel MOX Enrichment 16/21 Fuel Form Solid Smear Density (%) Core Diameter (m) 1.80 Active Fuel Height (m) 0.93 # Core Assemblies 198 # Total Assemblies 694 Pins/Assembly 169 Plenum Location Top Peak Flux (n/cm2 sec) 6.0 Peak. Flux (n/cm2 sec) 3.6 Peak Lin. Power (KW/m) 36 Ave. Lin. Power (KW/m) 21 Clad Material 316 Duct Material 316 Fuel Cycle (days) 148

MONJU SODIUM FIRE

DFBR, Japan

• Intended as the Japanese CommercialScale Fast Rector • Design Work has Slowed -- Fukushima Accident has seriously effected the Japanese program

Criticality Full Power MWth 1600 MWe 660 Coolant Na Configuration Loop Coolant Velocity (m/s) Inlet Core Temp.(C) 395 Outlet Core Temp. (C) 550 Fuel MOX Enrichment Fuel Form Smear Density (%) 83.7 Core Diameter (m) 2.99 Active Fuel Height (m) 1.00 # Core Assemblies 295 # Total Assemblies 1670 Pins/Assembly 217 Plenum Location Peak Flux (n/cm2 sec) Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 41 Ave. Lin. Power (KW/m) 25 Clad Material Adv. Austenitic Duct Material Adv. Austenitic Fuel Cycle (days) 456

JSFR-1500, Japan

• Current Effort in Japan’s Thrust for a Commercial-Scale Fast Reactor

• Substantial Gains Claimed to Reduce Capital Cost for this Loop-Type Plant • One Goal is to Burn Actinides

Criticality Full Power MWth 3530 MWe 1500 Coolant Na Configuration Loop Coolant Velocity (m/s) 4.1 Inlet Core Temp.(C) 395 Outlet Core Temp. (C) 550 Fuel MOX/metal Enrichment Fuel Form Smear Density (%) 82 Core Diameter (m) 6.8 incl. shield Active Fuel Height (m) 1.0 # Core Assemblies 562 # Total Assemblies 658 + Shield Pins/Assembly 255 Plenum Location Peak Flux (n/cm2 sec) Peak. Flux (n/cm2 sec) Peak Lin. Power (KW/m) 43 Ave. Lin. Power (KW/m) Clad Material ODS Duct Material ODS Fuel Cycle (days) 550

India • FBTR

• PFBR

FBTR, IGCAR, INDIA

• India’s First Fast Reactor

• Operates on Carbide Fuel • No Fuel Failures to Date -- 125,000 MWd/kg reached -- But never reached full power

• Program Initially Based on Thorium Cycle (Convert Th-232 into U-233)

Criticality 1985 Full Power MWth 40 MWe 13 Coolant Na Configuration Loop Coolant Velocity (m/s) 6.2 Inlet Core Temp.(C) 380 Outlet Core Temp. (C) 544 Fuel PuC-UC Enrichment 55 Fuel Form Smear Density (%) 78 Core Diameter (m) 0.492 Active Fuel Height (m) 0.32 # Core Assemblies 76 # Total Assemblies 712 Pins/Assembly 61 Plenum Location Peak Flux (n/cm2 sec) 3.4 Peak. Flux (n/cm2 sec) 2.5 Peak Lin. Power (KW/m) 35 Ave. Lin. Power (KW/m) 27 Clad Material 316 20%CW Duct Material 316 20%CW Fuel Cycle (days) 60

PFBR-500 (IGCAR, India

• Very Close to Construction Completion • Switched to Oxide Fuel India now has 1-2-3 agreement with several nations

• Thorium Blanket to Breed U-233

Criticality Full Power MWth 1250 MWe 500 Coolant Na Configuration Pool Coolant Velocity (m/s) 8.0 Inlet Core Temp.(C) 397 Outlet Core Temp. (C) 529 Fuel MOX Enrichment 20.7/27.7 Fuel Form Smear Density (%) 90 Core Diameter (m) 1.97 Active Fuel Height (m) 1.00 # Core Assemblies 181 # Total Assemblies 720 Pins/Assembly 217 Plenum Location Peak Flux (n/cm2 sec) 8.1 Peak. Flux (n/cm2 sec) 4.5 Peak Lin. Power (KW/m) 45 Ave. Lin. Power (KW/m) 28.7 Clad Material 15Cr15NiMoTi(CW) Duct Material 15Cr15NiMoTi(CW) Fuel Cycle (days) 240

PFBR-500 (IGCAR, India)

PFBR in India

Compliments of B. Baare, AREVA

China • CEFR

CEFR, Near Beijing, China

• China’s First Fast Reactor • Achieved Criticality About Two Years Ago • Very Large Building -- sized for significant future efforts

• Next Steps: 1) Start Construction of Two BN800 Reactors 2) Design and Build CDFR (2500 MWe)

Criticality 2010 Full Power 2011 MWth 65 MWe 23.4 Coolant Na Configuration Pool Coolant Velocity (m/s) 4.7 Inlet Core Temp.(C) 360 Outlet Core Temp. (C) 516 Fuel UO2 Enrichment 64.4 Fuel Form Smear Density (%) 77.6 Core Diameter (m) 0.600 Active Fuel Height (m) 0.450 # Core Assemblies 81 # Total Assemblies 703 Pins/Assembly 61 Plenum Location Peak Flux (n/cm2 sec) 3.1 Peak. Flux (n/cm2 sec) 2.1 Peak Lin. Power (KW/m) 40 Ave. Lin. Power (KW/m) 26.1 Clad Material 06Cr16Ni15Mo2Mn2TiVB Duct Material 08Cr16Ni11Mo3Ti1 Fuel Cycle (days) 73

Korea • KALIMAR

KALIMER, Korea

• The Original Korean Fast Reactor Design • Fueled with Metal Fuel • Currently Focusing More on Small Modular Reactor Designs

Criticality Full Power MWth 392 MWe 162 Coolant Na Configuration Pool Coolant Velocity (m/s) 5.1 Inlet Core Temp.(C) 386 Outlet Core Temp. (C) 530 Fuel U-Zr-TRU Enrichment 21.1 Fuel Form Smear Density (%) 75 Core Diameter (m) 1.56 Active Fuel Height (m) 1.00 # Core Assemblies 54 # Total Assemblies 367 Pins/Assembly 271 Plenum Location Peak Flux (n/cm2 sec) 3.01 Peak. Flux (n/cm2 sec) 2.2 Peak Lin. Power (KW/m) 28.7 Ave. Lin. Power (KW/m) 20.1 Clad Material HT9 Duct Material HT9 Fuel Cycle (days) 547

KALIMER 150, KOREA

Main Design Parameters for Large Fast Breeder Reactors BN-350 (Kazakhsta n)

Phènix (France)

PFR (U.K.)

SNR-300 (Germany)

MONJU (Japan)

CRBRP (U.S.)

Electrical Rating. MW

350 (equiv)

250

250

327

280

Thermal Power MW

1000

568

600

770

714

System

loop

pool

pool

loop

6

3

3

cold leg

cold pool

2

2

500 300 450

560 400 527

Number of loops Primary Pump Location Number of IHX’s per loop IHX Temperatures : Reactor Outlet, °C Reactor Inlet, °C Secondary Outlet.°C Secondary Inlet, °C

BN-600 (Russia)

Super Phènix (France)

CDFR (U K.)

SNR-2 (Germany)

BN-l600 (Russia)

EFR

375

600

1200

1320

1300

1600

975

1470

3000

3230

3420

4200

loop

loop

pool

pool

pool

loop

3

3

3

3

4

6

cold pool

hot leg

cold leg

hot leg

cold pool

cold pool

2

3

1

1

2

2

550 400 540

546 377 528 335

529 397 505 325

535 388 502 344

550 377 520

separate: 2-straight I-helical

separate; helical coil

separate: hockey stick

Steam Generator

integral; modular: separate; bayonet “S”-shaped U-tube tube evaporator.

U-tube superheater

Steam Cycle

recirculatin g

Number of Units per Loop: Integral Steam Generators Separate Evaporators Separate Superheaters Steam Drums Moisture Separators Reheaters

Turbine Inlet Pressure, MPa Inlet Temperature. °C Number/Rating, MWe Type

2 1 0 0

once recirculatin through g (Benson)

12 12 1 1 12

1 1 1 1

once through (Sulzer)

3 3 0 1 0

PFBR (India)

KALIMER (Korea)

1470

500

3600

1250

pool

pool

4

4

cold pool

hot leg

2

2

545 395 525 345

540 370 510 335

540 390 510 340

separate: straight tube

integral: helical coil

integral: helical coil

integral, helical coil or straight tube

once recirculatin once through g through (Benson) (Benson)

once through (Benson)

once through

once through

once through

once through

once through

1 0

-

2 -

1 -

4 -

-

18.5 @SG 490 @SG

16.7 490 1/500 Tandem Compound condensing C

1 1 0 1 0

2 1 1 0

1 1 1 1

4.9 16.3 12.8 16.0 12.5 10.0 14.2 18.4 16.0 16.5 435 510 513 495 483 482 505 490 490 495 1 1 1/250 1 1 1/434 K-200-130 2/600 2/660 1/300 K-I00-45 Condensing Tandem Condensing Tandem Tandem Condensing Tandem Single shaft compound compound compound compound

DFBR (Japan)

CEFR (China)

150

660

25

392

1600

65

pool

pool

loop

pool

6

2

2

3

2

cold pool

cold pool

cold pool

cold pool

cold leg

1

1

2

550 350 505 310

545 395 525 340

544 394 525 355

1 530 386 511 340

Integrated Integrated

14.0 500 2/800

550

530 360 495 310

Integrated

15.0 480

16.9 495

VII. Global View

• • • •

Global Nuclear Electricity Fukushima The Slowdown Capital Costs

Reactions to Fukushima all over the World (January 2012) Phaseout Operating NPPs:  Germany Cancel Projects:  Japan, Italy, Taiwan, Switzerland ?

Proceed with Nuclear Programs:  USA, Russia, China, India, UK, Finland, Poland, Czech Republic, Sweden, Slovakia, Hungary, Brazil, South Africa, South Korea, UAE,…

+ Stress Tests in most nuclear countries

Reactors under Construction (June 2012)

Compliments of B. Barre, AREVA

Implications of the Near Halt in Construction of New Nuclear Power Plants in Last Couple Decades • Key Professionals Retired or Lost to Industry • Few Professionals Coming into the Industry • Manufacturing Plants Shut Down • Hence, New Construction Cost Much Higher in the Renaissance that began about 5 years ago • Utilities now strapped to spend ~$5B on new, large plants

Hence, the Principal Drivers for Small Modular Reactors • • • • • • • •

Reduced capital costs per plant Meet electrical growth incrementally Shorter construction schedules (modular construction) Enhanced safety and security (some Fukushima influence) Improved quality (in-factory construction) Replace aging coal plants Create good jobs Serve international markets (with limited electrical infrastructure)

To be discussed in second presentation A Key Market for Fast Spectrum Reactors

VIII. Perspective The First 2/3 Century of Fast Reactors • 21 Fast Reactors Built and Operated -- 18 Sodium Cooled Plants -- 2 NaK Cooled Plants -- 1 Mercury Cooled Plant

~400 Reactor Years of Operation

• Reactor Core Experience Generally Favorable -- EBR-I Meltdown -- Fermi Partial Melt

Only MAJOR Core Problems

• Challenges Mainly with Balance of Plant -- Monju Thermocouple and Fuel Handling -- JOYO Fuel Handling -- Super Phenix Turbine Bay Roof Collapse/Fuel Storage Leak

• Capital Cost Remains Primary Challenge

References • Unless otherwise specified, all technical references and data are taken from Alan E. Waltar, Donald R. Todd, & Pavel V. Tsvetkov, Editors, FAST SPECTRUM REACTORS, Springer, 2012

• Most illustrations for Fast Reactors are taken from IAEA, STATUS OF SMALL AND MEDIUM SIZED REACTOR DESIGNS, A Supplement to the IAEA Advanced Reactors Information System (ARIS), http://aris.iaea.org •Additional material has been taken from Bertrand Barre and Frank Carre (presentations at the 2012 World Nuclear University Summer Institute, Oxford,England • Some materials were derived from the internet.

BACKUP

The 50s : Nuclear Electricity 1956 : Inauguration of Calder Hall

1951 : EBR 1 Lights its Building

1954: Obninsk Connected

Compliments of B. Barre, AREVA

The American Scene History of U.S. operating plants prior to Fukushima

President Obama: U.S. Nuclear Power “We must harness the power of nuclear energy on behalf of our efforts to combat climate change, and to advance peace opportunity for all people.”

President Obama, Prague, April 2009

“ Some folks want wind and solar. Others want nuclear, clean coal and natural gas. To meet this goal, we will need them all -- and I urge Democrats and Republicans to work together to make it happen.”

President Obama, State of the Union, January 25, 2011

AFTER Fukushima…

Administration continues to publicly support nuclear power President Obama at Town Hall Discussion on Energy in Fairless Hills, Pennsylvania (April 6, 2011) “I want us to double the amount of electricity that we draw from clean sources. I want us to double it. And that means by 2035, 80 percent of our electricity will come from renewables like wind and solar, as well as efficient natural gas, clean coal, nuclear power. We can do that.”

BN-800 (Russia) 800 MWe, 2014

CEFR (China) 65 MWth, 20 MWe, PBFR (India) 500 MWe, 2012

July 2010

Layout of ALFRED Prototype Reactor

ALFRED â&#x20AC;&#x201C; Advanced Lead Fast Reactor European Demonstrator (MOX fuelled, 300 MWth) Operating Temperature of 400-480 C to limit corrosion of advanced ferritic & austenitic steels

Fast spectrum reactor designs (Liquid Metal Cooled) Able to provide improved fuel cycles …………….Sodium-Cooled………………………………

PRISM (General Electric) 300 MWe

4S (Toshiba, Japan)

10 MWe

…Lead-Bismuth Cooled…

SVBR-100 (AKME Engineering, Russian Federation)

100 MWe

Compliments of Thomas Fanning, Sodium as a Fast Reactor Coolant, 5-3-2007

Nuclear Power Plant Construction Costs in Korea 100 % Construction Cost (Cost/kW)

80 80

78 69 61

60 40

20 0 1st OPR1000 (YG 3&4)

NthOPR1000 (UC 5&6)

Improved OPR1000 (SK 1&2

1stAPR1400 (SK 3&4)

Nth APR1400

Why? How is Korea Different?

Two Main Reasons: • Top Federal Support for past halfcentury • Stayed the Course after Chernobyl

UAE Nuclear Power contract 

NPP turnkey package contract

Contract worth  $ 20 billion +  Completion schedule 2017 - 2020

But for most other nations, including the United States...

•New Construction Cost Much Higher in the Renaissance that began about 5 years ago • Utilities now “bet the farm” on new, large plants