Reactor Fundamentals Ray Ganthner Sr. Vice President AREVA NP “Role of Nuclear Power” 2007...

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Reactor Fundamentals Ray Ganthner Sr. Vice President AREVA NP “Role of Nuclear Power” 2007 Summer Workshop Washington and Lee University and the Council on Foreign Relations

Transcript of Reactor Fundamentals Ray Ganthner Sr. Vice President AREVA NP “Role of Nuclear Power” 2007...

Reactor Fundamentals

Ray Ganthner

Sr. Vice President

AREVA NP

“Role of Nuclear Power”2007 Summer Workshop

Washington and Lee University and the Council on Foreign Relations

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Outline

> Uranium Fuel and Usage> Fundamental Electricity Generation Cycle> Technology Options/Choices> The Commercial Nuclear Power Generation

Industry Today

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Uranium as FuelMining, Conversion, Generation

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Uranium Ore Exploration

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Uranium Global Resources

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World Uranium Reserves

> Australia 24%> Kazakhstan 17> Canada 13> South Africa 9> Russia 6> Nambia 6> US 4> Niger 3> Uzbekistan 3

Most Uranium currently comes from Canada, followed by Australia and

Niger

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World Uranium Production

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Uranium Mine in Niger (Sahara Desert)

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Conversion of Uranium Ore to “Yellow Cake”

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COMURHEX – Malvesi U3O8 → UF4

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COMURHEX – PierrelatteUF4 → UF6

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Centrifuge Enrichment

FeedEnriched

exit

Depleted exit

U235 is lighter and collects in the center (Enriched)

U238 is heavier and

collects on the outside walls

(Depleted/Tails)

Feed to

Next Stage

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Centrifuge Cascade

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UF6 to UO2 Powder to Pellets

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Fuel Pellets

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Uranium Is Encased in Solid Ceramic Pellets after Enrichment

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Nuclear Fuel Assembly

Fuel Pellet

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Fuel Assembly for Light Water Reactor

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Fuel Assemblies are Inserted in Reactor Vessel

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PWR Reactor Vessel

• 41 feet tall

• 14 feet ID

• 8.5 inch thick walls

• 665 tons

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Typical PWR Reactor Pressure Vessel

DescriptionTechnical

Data

Life time 60 years

Coolant pressure at reactor pressure vessel outlet during power operation

2250 psia

Coolant temperature at reactor pressure vessel inlet at full load

563 F

Coolant temperature at reactor pressure vessel outlet at full load

624 F

Design pressure 2550 psia

Design temperature 664 F

CL HL

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Pressurized Water Reactor

PWR

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Pressurized Water Reactor Plant

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Pressurized Water Reactor Plant

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Boiling Water Reactor

BWR

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Selection of Technology Options

> Key Decisions Fuel Moderator Cooling

> US Path Based on government prototypes Navy Influence

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A New Age Begins: 1950s

> By 1950, several countries had operating nuclear reactors. Most were dedicated to research and “proof-of-principal.”

> During the 1950s and early-1960s, many experimental and proto-type reactor designs were developed: Liquid Metal Cooled (EBR-1) Boiling Water (BORAX III, Dresden 1) Pressurized Water (Shippingport, Yankee Rowe) Gas Cooled (Calder Hall, Marcoule) Heavy-Water Moderated (Zoe, NRX, NRU) Liquid Metal Cooled, Graphite Moderated

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Shippingport-195760 MWe

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Technologies Emerge Based on National Resources and Government Policies

> Light Water Reactors emerged as the dominant technology in the US. Factors were: US navy reactors, which were of LWR design

(predominantly PWR), were driving commercial designs.

LWR prototypes performed well, with the right mix of features that appealed to utilities.• Compact reactor designs

• Inherent safety characteristics (negative power coefficient, negative void coefficient)

• Good economics

• Trained workers and lessons-learned from US Navy

U enrichment technology available at low cost.

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> Successful CANDU design capitalizes on abundant uranium supplies and complete separation from weapons technology.

> France and England adopted gas cooled natural U reactors due to lack of indigenous U separation technology. France adopted PWR technology only after a national commitment to U enrichment/separation facilities.

Technologies Emerge Based on National Resources And Government Policies

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Indian Point-1969250 MWe Oyster Creek-1969

619MWe

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Generation II Reactors

> Based on the successes of prototype reactors, the next generation of high power LWRs were designed. 400 MWe to 600 MWe LWRs came on line in the late 1960s 800 MWe to 1000 MWe LWRs came on line in the 1970s 1000 MWe to 1450 MWe LWRs on line in 1980’s & 1990s

> Each design was based on experience with the one before.

> While standard designs were promoted in Canada, England and France, there was a lack of standardization in the US: Babcock & Wilcox: 2-Loop PWRs with OTSGs Combustion Engineering: 2-Loop PWRs with RSGs General Electric: BWR/2, BWR/4, BWR/6 Westinghouse Electric: 2- 4 Loop

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Current Situation

> Worldwide 441 nuclear generation plants 104 operating in US (providing 20% of US electricity) Predominantly Light Water Reactors (LWR)

> Worldwide 27 reactors under construction None in US

> New reactor designs available (Generation III) Improved safety Improved economics

> Generation IV reactors being developed Gas or sodium cooled Assist in “closing” the fuel cycle

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Near-TermGeneration III+ Designs For US

> US EPR by AREVA

> ESBWR and ABWR by General Electric

> AP1000 by Westinghouse/Toshiba

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Generation III Reactor Design Goals

> Reduced construction time and cost.

> Simplified to reduce operational cost.

> Fleet-wide standard design and equipment.

> Improved man-machine interface. Reduced operator burden.

> Increased safety.

Reactor Fundamentals

Ray Ganthner

Sr. Vice President

AREVA NP

“Role of Nuclear Power”2007 Summer Workshop

Washington and Lee University and the Council on Foreign Relations

Backups for possible discussion.

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Possible Locations for New Nuclear Plants

Possible Locations for New Nuclear Plants

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Source: Bjorn Lomborg – The Skeptical Environmentalist

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Nuclear has very low life-cycle CO2 emissions

If we assume that nuclear electricity is used for uranium enrichment, rather than coal electricity, nuclear life-cycle emissions drop further

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The COGEMA-La Hague plant

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AREVA steps up the pace of its mining developmentProduction and Exploration set to grow

Kazakhstan

Production start in 2006, set to increase sharply in 2007

Exploration program continues

Canada

Cigar Lake - 2010

Encouraging results in exploration (Shea Creek, Millenium, Midwest,…)

Niger

Increase in production capacity

Exploration program continues

Finland

Permits to be issued

Exploration

Production

Production (metric tons of U)

~ 6,000

12,000

Production2005

Production2010

~ 6,000

12,000

Production2005

Production2010

2003 2004 2005 2006 2007

Exploration budget (M€)Base 100 in 2003

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Recirculating Steam Generator

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A Typical Steam Generator