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Prof. Andrew C. Kadak, 2008Page 1Department of Nuclear Science & Engineering
Operational Reactor Safety22.091/22.903
Professor Andrew C. KadakProfessor of the Practice
Spring 2008
Overview
Prof. Andrew C. Kadak, 2008Page 2Department of Nuclear Science & Engineering
Course Learning Objectives
The course will focus on understanding the complete nuclear reactor system including the balance of plant, support systems and resulting interdependencies affecting the overall safety of the plant and regulatory oversight.
• Reactor Physics• Power Conversion• Safety Functions and Systems• Risk Assessment• Simulator Exercises• Technical Specifications• Safety Culture
Prof. Andrew C. Kadak, 2008Page 3Department of Nuclear Science & Engineering
Course Overview
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Prof. Andrew C. Kadak, 2008Page 4Department of Nuclear Science & Engineering
Course Overview Cont’d
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Prof. Andrew C. Kadak, 2008Page 5Department of Nuclear Science & Engineering
Grading Components
Homework 15%Quiz #1 20%Quiz #2 20%Quiz # 3 20%
Final Exam 25%
Late Homework will receive up to 1/2 full credit
Prof. Andrew C. Kadak, 2008Page 6Department of Nuclear Science & Engineering
Lecture 1: Overview of Nuclear Reactors
Learning Objectives:
Gain broad understanding of PWRs, BWRs, HTGRs
Prof. Andrew C. Kadak, 2008Page 7Department of Nuclear Science & Engineering
Nuclear Fuel Cycle
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Prof. Andrew C. Kadak, 2008Page 8Department of Nuclear Science & Engineering
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Prof. Andrew C. Kadak, 2008Page 9Department of Nuclear Science & Engineering
Calvert Cliffs - MD
Diablo Canyon
Prairie Island - MN
Indian Point - NY
Prairie Island site - MN
Robinson - SC
Surry - VA
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Prof. Andrew C. Kadak, 2008Page 10Department of Nuclear Science & Engineering
Objectives to Make Electricity
1. Make heat2. Remove heat using a fluid or gas3. Pass the fluid or gas through a turbine4. Turning an electric generator to make
Electricity
Prof. Andrew C. Kadak, 2008Page 11Department of Nuclear Science & Engineering
Removing Heat• Fluid (water or liquid metal) or gas is pumped through the
core to remove heat generated in fuel due to fissioning.
• Pumps needed to circulate coolant
• Transfer directly to turbines or to steam generators (PWRs)
• Condense steam to recirculate back to the core to provide cooling
Prof. Andrew C. Kadak, 2008Page 12Department of Nuclear Science & Engineering
Basics of Power Conversion
Boiling Water Reactor
Just like a coaloil or natural gas plant
ReplacesfossilBoilerbut nosmokestack
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Prof. Andrew C. Kadak, 2008Page 13Department of Nuclear Science & Engineering
Power Reactor Types
– Pressurized Water Reactor
– Boiling Water Reactor
– Natural Uranium Heavy Water Cooled Reactor (CANDU)
– RBMK - Russian Chernobyl Like - Water Cooled
– Fast Reactors - Liquid Metal (Sodium)
– Gas Reactors (CO2 or Helium Cooled)
– Molten Salt Cooled Reactors (Organic Coolants)
Prof. Andrew C. Kadak, 2008Page 14Department of Nuclear Science & Engineering
Making Heat
• Use the fissioning of uranium atoms (or plutonium) to release 200 Million electron volts per fission.
• Need to enrich natural uranium to 3 to 4 weight percent U-235 (from 0.7% found in nature.
• Need to fabricate uranium into pellets clad in zironium fuel assemblies which are placed into the reactor core.
Prof. Andrew C. Kadak, 2008Page 15Department of Nuclear Science & Engineering
Fission Event
Release of excess neutrons creates the potential for chain reaction.
The energy (mostly as kinetic energy of the fission fragments) is substantial.
n U-235 nn
FF2n
FF1
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Prof. Andrew C. Kadak, 2008Page 16Department of Nuclear Science & Engineering
Energy Release
1 fission = 200 Mev
1 gram U-235 fissioned = 8.6x1010 joules = 24,000 kwh
(Equivalent to lighting a small city for overnight)
24,000 kwh requires 3.2 tons of coal
12.6 bbls oil
Energy Density (energy / mass)
Energy Density of U-235 = 28,000 times energy density of coal
Prof. Andrew C. Kadak, 2008Page 17Department of Nuclear Science & Engineering
Pellets
Fuel Pins
Insertingpelletsinto pins
Fuel Assembly
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Prof. Andrew C. Kadak, 2008Page 18Department of Nuclear Science & Engineering
Creating the Reactor Core
• Need to model uranium fuel
• Reactor internals
• Coolant flow
• Apply Reactor Physics
• Develop neutron flux solutions
• Yields power distributions
• Creates heat that must be removedReactor Core
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Prof. Andrew C. Kadak, 2008Page 19Department of Nuclear Science & Engineering
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Prof. Andrew C. Kadak, 2008Page 20Department of Nuclear Science & Engineering
Important Factors in Design• Reactor Core Design
– Fuel Design
• Reactor Physics - Core Power Distribution• Reactivity Control - Ability to shutdown plant• Safety Analysis - no fuel failure or melting
• Core Heat Removal
– Coolant - Heat Transfer
– Safety Systems (Emergency)
• Confinement of Radioactivity
• Electricity Production
Prof. Andrew C. Kadak, 2008Page 21Department of Nuclear Science & Engineering
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Prof. Andrew C. Kadak, 2008Page 22Department of Nuclear Science & Engineering
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Prof. Andrew C. Kadak, 2008Page 23Department of Nuclear Science & Engineering
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Prof. Andrew C. Kadak, 2008Page 24Department of Nuclear Science & Engineering
Boiling Water Reactors
Prof. Andrew C. Kadak, 2008Page 25Department of Nuclear Science & Engineering
BWR Power Cycle
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Prof. Andrew C. Kadak, 2008Page 26Department of Nuclear Science & Engineering
Schematic Arrangement of a BWR
A.V. Nero, Jr., A Guidebook to Nuclear Reactors, 1979Source unknown. All rights reserved. This content is excluded from our Creative Commons license. For more information, see http://ocw.mit.edu/fairuse.
Prof. Andrew C. Kadak, 2008Page 27Department of Nuclear Science & Engineering
BWR Fuel Assembly
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Prof. Andrew C. Kadak, 2008Page 28Department of Nuclear Science & Engineering
BWR Core Lattice
“BWR/6: General Description of a BWR,” GE, 1980.Source unknown. All rights reserved. This content is excluded from our Creative Commons license. For more information, see http://ocw.mit.edu/fairuse.
Prof. Andrew C. Kadak, 2008Page 29Department of Nuclear Science & Engineering
Pilgrim Nuclear Plant
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Prof. Andrew C. Kadak, 2008Page 30Department of Nuclear Science & Engineering
Pressurized Water Reactors
Prof. Andrew C. Kadak, 2008Page 31Department of Nuclear Science & Engineering
Schematic of Pressurized Water Reactor
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Prof. Andrew C. Kadak, 2008Page 32Department of Nuclear Science & Engineering
PrimaryCoolant Pump
PrimaryVessel
ControlRods
ReactorCore
292ÞC
PrimaryConcrete
Shield15.5 MPa
Pressurizer
324ÞC
SteamGenerator
Concrete and SteelContainment
Primary Side Secondary Side
Steam to Turbine6.9 MPa285ÞC
High-PressureHeaters
Low-PressureHeaters
FeedPump
CondensatePump
Turbine
Turbine Bypass
ElectricGenerator
Grid
Condenser
CoolingTower
-40ÞC-15ÞC
Pressurized Water Reactor Schematic
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Prof. Andrew C. Kadak, 2008Page 33Department of Nuclear Science & Engineering
Typical Four-Loop Reactor Core
ParametersTotal heat output ~3250-3411 MWTHeat generated in fuel 97.4% Nominal system pressure 2250 psia Total coolant flow rate ~138.4 x 106 lb/hr Coolant Temperature
Nominal inlet Average rise in vessel Outlet from vessel
557.5˚F61.0˚F618.5˚F
Equivalent core diameter 11.06 ft Core length, between fuel ends 12.0 ft Fuel weight, uranium (first core) 86,270 kg Number of fuel assemblies 193
Cross Section (193 Fuel Assemblies)
Masche, G., Systems Summary: W PWR NPP, 1971Source unknown. All rights reserved. This content is excluded from our Creative Commons license. For more information, see http://ocw.mit.edu/fairuse.
Prof. Andrew C. Kadak, 2008Page 34Department of Nuclear Science & Engineering
PWR Fuel Assembly
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Prof. Andrew C. Kadak, 2008Page 35Department of Nuclear Science & Engineering
The Byron plant (photo courtesy Commonwealth Edison) is typical of a large US Pressurized Water Reactor plant. Each reactor is 1105 MWe and they came into commercial service in 1985 and 1987 respectively.
Prof. Andrew C. Kadak, 2008Page 36Department of Nuclear Science & Engineering
Gas Cooled Reactors
Fort St. Vrain - 330 MWe
Prof. Andrew C. Kadak, 2008Page 37Department of Nuclear Science & Engineering
Power Cycle - Brayton
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Prof. Andrew C. Kadak, 2008Page 38Department of Nuclear Science & Engineering
Ceramic Fuel
L-029(5)4-14-94
Uranium OxycarbidePorous Carbon BufferSilicon CarbidePyrolytic Carbon
PARTICLES COMPACTS FUEL ELEMENTS
TRISO Coated fuel particles (left) are formed into fuel rods (center) and inserted into graphite fuel elements (right).
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Prof. Andrew C. Kadak, 2008Page 39Department of Nuclear Science & Engineering
Modular Pebble Bed Reactor
Thermal Power 250 MW
Core Height 10.0 m
Core Diameter 3.5 m
Fuel UO2
Number of Fuel Pebbles 360,000
Microspheres/Fuel Pebble 11,000
Fuel Pebble Diameter 60 mm
Microsphere Diameter ~ 1mm
Coolant Helium
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Prof. Andrew C. Kadak, 2008Page 40Department of Nuclear Science & Engineering
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Prof. Andrew C. Kadak, 2008Page 41Department of Nuclear Science & Engineering
Reading and Homework Assignment
1. Read Knief Chapter 1
Problems: 1.9, 1.10, 1.12
2. Read Knief Chapter 2
Problems: 2.7, 2.12
3. Read Knief Chapter 4
MIT OpenCourseWarehttp://ocw.mit.edu
22.091 Nuclear Reactor SafetySpring 2008
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