Operational Reactor Safety...Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak...

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Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Spring 2008 Lecture 2: Reactor Physics Review Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 1

Transcript of Operational Reactor Safety...Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak...

Page 1: Operational Reactor Safety...Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Spring 2008 Lecture 2: Reactor Physics Review Prof. Andrew

Operational Reactor Safety 22.091/22.903

Professor Andrew C. Kadak Professor of the Practice

Spring 2008

Lecture 2: Reactor Physics Review

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 1

Page 2: Operational Reactor Safety...Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Spring 2008 Lecture 2: Reactor Physics Review Prof. Andrew

Topics to Be Covered – Cross Sections

– Fission Process

– Infinite Reactor Systems

– Finite Reactor Systems

– Four Factor Formula

– Criticality Control

– Diffusion Theory

– Neutron Transport (Boltzman Equation)

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 2

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Nuclear Reactor Physics Review

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 3

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Cross Sections

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 4

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Cross Sections

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 5

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Uranium Cross Sections

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 6

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Fission Chain Reaction

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 7

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Fission Neutron Energy

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 8

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Fission Energy

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 9

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Fission Product Decay Chain

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 10

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Fission Yield by Mass Number

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 11

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Chart of the Nuclides

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 12

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Prof. Andrew C. Kadak, 2008Page 13Department of Nuclear Science & Engineering

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Conversion Chain: Fertile Fissile

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 14

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Reaction Rates* • How do we make power?

• Factors to consider in design

– Changes in fuel material

– Life of reactor core

– Reactivity swing

– Refueling strategies

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 15

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Prof. Andrew C. Kadak, 2008Page 16Department of Nuclear Science & Engineering

Courtesy of Michael W. Golay. Used with permission.

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Prof. Andrew C. Kadak, 2008Page 17Department of Nuclear Science & Engineering

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Neutron Moderation Parameters

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 18

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Infinite & Finite Reactor Systems* • Infinite Systems

– Neutron Multiplication

– Four Factor Formula

• Finite Systems

– Leakage

– Six Factor Formula

• Diffusion Theory

Prof. Andrew C. Kadak, 2008 Department of Nuclear Science & Engineering Page 19

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Courtesy of John A. Bernard. Used with permission.

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Courtesy of John A. Bernard. Used with permission.

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Page 26: Operational Reactor Safety...Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Spring 2008 Lecture 2: Reactor Physics Review Prof. Andrew

Criticality Control

• K should = 1 for 18 to 24 months– How ?

• Fuel excess reactivity (fuel)• Balance with control rods or soluble boron• Burnable poisons in fuel to deplete with time• Leakage• On-line refueling – CANDU – Pebble Beds

Page 27: Operational Reactor Safety...Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Spring 2008 Lecture 2: Reactor Physics Review Prof. Andrew

Diffusion Theory*

• One group– Neutron Balance for critical reactor– Consider production absorption and leakage

• Multi-group– Include different energy groups

Page 28: Operational Reactor Safety...Operational Reactor Safety 22.091/22.903 Professor Andrew C. Kadak Professor of the Practice Spring 2008 Lecture 2: Reactor Physics Review Prof. Andrew

Prof. Andrew C. Kadak, 2008Page 28Department of Nuclear Science & Engineering

Diffusion Theory Fluxes and Bucklings

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Multigroup Calculations

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Prof. Andrew C. Kadak, 2008Page 30Department of Nuclear Science & Engineering

Diffusion Theory Flux Shapes

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Prof. Andrew C. Kadak, 2008Page 31Department of Nuclear Science & Engineering

Fast and Thermal Flux Shapes

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Prof. Andrew C. Kadak, 2008Page 33Department of Nuclear Science & Engineering

Boltzman Equation• Neutron Transport Theory

• Fundamental Equation of neutron interaction

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Prof. Andrew C. Kadak, 2008Page 34Department of Nuclear Science & Engineering

Homework• Knief Chapter 4

– Problems: 4.3, 5, 8, 10, 11, 14, 15

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22.091 Nuclear Reactor SafetySpring 2008

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