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Have Deliberately Small Reactors Come Of Age? Daniel Ingersoll Oak Ridge National Laboratory American Nuclear Society Annual Meeting June 14-18, 2009 Atlanta, GA Small Nuclear Power Plants Were First Developed for Defense Applications
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Have Deliberately Small Reactors Come Of Age?Daniel IngersollOak Ridge National Laboratory American Nuclear Society Annual Meeting June 14-18, 2009 Atlanta, GA
Small Nuclear Power Plants Were First Developed for Defense Applications • The United States and Russia began developing small nuclear reactors for naval propulsion beginning in the early 1950s • The U.S. Air Force explored nuclear powered aircraft, but discontinued the program in 1961 • The U.S. Army built 7 small stationary power plants and 1 floating power plant for remote operations: ANS Annual Meeting, June 14-18, 2009
1400 Palo Verde 2 U.S. Experience 1200 1000 Watts Bar 1 800 Electrical Output (MWe) 600 400 Shippingport 200 Fort St.Vrain 0 1955 1960 1965 1970 1975 1980 1985 1990 1995 2000 Date of Initial Operation Many Countries Initially Built Smaller Sized Commercial Nuclear Power Plants ANS Annual Meeting, June 14-18, 2009
Some Basic Terminology IAEA definitions: Small: < 300 MWe Medium: 300-700 MWe Large: > 700 MWe } • SMR = < 700 MWe Related but less precise terms: Low-Capacity Nuclear Power Plants (LCNP) Small Modular Reactors (SMR) Deliberately Small Reactors (DSR) ANS Annual Meeting, June 14-18, 2009
Several Countries Have Explored Merits of Smaller, Simpler NPPs • In the United States: • Weinberg study (1985) • Advanced Light Water Reactor program (1985-present) • Advanced Liquid Metal Reactor program (1985-1995) • International Organizations: • Nuclear Energy Agency Expert Group (1991) • The Generation IV International Forum (2000-present) • The International Project on Innovative Nuclear Reactors and Fuel Cycles (2000-present) • Common user considerations • International Atomic Energy Agency Coordinated Research Projects (2003-present) • Passive safety features • Technology options (with or without on-site refueling) • Economic competitiveness ANS Annual Meeting, June 14-18, 2009
Sampling of SMR Concepts Under Development World-Wide • Integral PWR: CAREM (Ar), IMR (Jp), IRIS (US), NuScale (US), mPower (US) SCOR (Fr), SMART (RoK) • Marine derivative PWR: ABV (RF), KLT-40S (RF), NP-300 (Fr), VBER-300 (RF) • BWR/PHWR: AHWR (In), CCR (Jp), MARS (It) • Gas-cooled: GT-HTR-300 (Jp), GT-MHR (US), HTR-PM (Ch), PBMR (SA) • Sodium-cooled: 4S (Jp), BN-GT-300 (RF), KALIMER (RoK), PRISM (US), RAPID (Jp) • Lead/Pb-Bi-cooled: BREST (RF), ENHS (US), LSPR (Jp), STAR/SSTAR (US), SVBR-75/100 (RF) • Non-conventional: AHTR (US), CHTR (In), Hyperion (US), MARS (RF), MSR-FUJI (Jp), TWR (US) ANS Annual Meeting, June 14-18, 2009
Interest in Smaller Sized Reactor Designs Are Beginning To (Re)Emerge • Benefits • Enhanced safety • Improved fabrication and construction logistics • Greater operational flexibilities • Favorable economics • Applications • Countries with small or limited electrical grid infrastructure • Smaller private utilities in large-grid countries • Special power applications such as defense • Non-electrical customers ANS Annual Meeting, June 14-18, 2009
Safety Benefits of DSRs • Elimination of accident initiators (integral designs) • No large pipes in primary circuit means no large-break loss-of-coolant accidents • Increased water inventory means slower system response to power transients • Internal control rod drive mechanisms mean no rod-ejection accidents or David Besse-type events • Reduced source term • Reduced shielding, site radius, emergency planning zone, etc. • Improved decay heat removal • Lower decay heat generated • More efficient passive decay heat removal from reactor vessel (volume-to-surface area ratio effect) ANS Annual Meeting, June 14-18, 2009
Integral Primary System Configuration External Loop PWR (Sizewell B) Integral PWR (SIR*) • Enhances safety by eliminating major classes of accidents. • Simplifies design by eliminating loop piping and external vessels. • Allows for compact containment (small plant footprint) to enhance economics and security. *Safe Integral Reactor, R. Dettmer, IEE Review, 1989 ANS Annual Meeting, June 14-18, 2009
Fabrication and Construction Benefits • Physically smaller components • Eliminate or reduce number of large forgings • More in-factory fabrication; less site-assembly • Reduces schedule uncertainty • Improves safety • Reduces cost • Reduce size and weight for easier transport to site • Access to a greater number of sites • Well suited for remote or undeveloped sites • Smaller plant footprint • Place nuclear system further below grade to improve resistance to external events and sabotage ANS Annual Meeting, June 14-18, 2009
93% of all generating units have capacities < 500 MWe 8000 7000 6000 18,602 Power Plants Globally 5000 Number of Plants 4000 3000 2000 1000 0 < 1 1-50 50-500 500-1000 >1000 Plant Size (MW) Operational Flexibilities • Site selection • Potentially reduced emergency planning zone (EPZ) • Use of seismic isolators • Lower water usage • Load demand • Better match to power needs for many non-electrical applications • Grid stability • Closer match to traditional power generators • Smaller fraction of total grid capacity • Demand growth • Ability to add (and pay for) capacity as demand dictates ANS Annual Meeting, June 14-18, 2009
Economic Benefits • Total project cost • Smaller plants are cheaper • Improves financing options and lowers financing cost • May be the driving consideration in some circumstances • Cost of electricity • Economy-of-scale (EOS) works against smaller plants but can be mitigated by other economic factors • Accelerated learning, shared infrastructure, design simplification, factory replication • Investment risk • Maximum cash outlay is lower and more predictable • Maximum cash outlay can be lower even for the same generating capacity ANS Annual Meeting, June 14-18, 2009
SMR Applications • Baseload electricity generation • Smaller utilities with low demand growth • Regions/countries with small grid capacity • Installations requiring independent power • Non-electrical power needs • Potable water production (desalinations • Advanced oil recovery for tar sands and oil shale • Hydrogen production • Advanced energy conversion such as coal-to-liquids conversion • District heating ANS Annual Meeting, June 14-18, 2009
SMR Challenges – Technical • All designs have some degree of innovation in components, systems, and engineering • Integral primary system configuration • Internal control rod drive mechanisms and pumps • Multiplexed control systems/interface • A prototype unit may or may not be needed • Many LWR designs plan to go directly to first-of-a-kind • Most non-LWR designs will need a prototype • Sensors, instrumentation and controls development are likely needed for all designs • Power and flow monitoring in integral systems • Advance prognostics and diagnostics • Control systems for co-generation plants ANS Annual Meeting, June 14-18, 2009
SMR Challenges – Institutional • Too many competing designs • Mindset for large, centralized plants • Fixation on economy-of-scale • Economy-of-hassle drivers • Perceived risk factors for nuclear plants • Traditional focus of regulators on large, LWR plants • Standard 10-mile radius EPZ (in the U.S.) • Staffing and security force size • Plant vs module licensing • Fear of first-of-a-kind • New business model as well as new design must be compelling ANS Annual Meeting, June 14-18, 2009
Summary • Most countries using nuclear power started with smaller sized plants • To gain experience with new technology and designs • For special applications such as propulsion or defense • After initial experience with small plants, plant size and complexity grew rapidly • New SMRs offer many potential benefits • Enhanced safety • Improved fabrication and construction flexibility • Greater operational flexibility • Favorable economics (affordability) • Deployment schedules will differ significantly among spectrum of SMR designs ANS Annual Meeting, June 14-18, 2009
THINK SMALL ! “Deliberately Small Reactors and the Second Nuclear Era,” Progress in Nuclear Energy, 51, p 589-603, 2009. ANS Annual Meeting, June 14-18, 2009