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    Mechanical Power Eng. Dept. Academic year: 2015-2016

    Faculty of Engineering Academic term: 2

    nd

    Term

    Minoufiya University Academic level: 4

    nd

    Mech Power.

    Title: Design and Operation of Thermal Power Plants

    Code Symbol : MPE 423B 

    Lecture Tutorial Laboratory Total

    3 2 1 6

    Dr- Ashraf Amin

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    TopicNo.

    General Topics Weeks

    1st Types of thermal power stations 1st 

    2nd Design of combined gas-steam cycle 2t   to 3t  

    3rd Types of nuclear reactor 4t

     and 5t

     

    4th Types power plants 6th

    , and 7th

     

    5th General layout of a nuclear power plant 8th

     

    6th Steam power plant piping system 9th, and 10th 

    7thEmission of power plants 11

    t, and

    12th

     

    8thOperation of thermal power stations 13

    t, and

    14th

     

    Course Topics.

    Humaniti

    es and

    Social

    Science

    Math.

    and

    Basic

    Sciences

    Basic

    Eng.

    Science

    Applied

    Eng.

    and Design

    Compute

    r

    applicatio

    n and

    ICT

    Projects

    and

    practice

    Discretiona

    ry subjects

    Tota

    l

    0% 0% 15% 75% 0% 10% 0%100

    %

    Course Sub ject Area 

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    - L ist of references: 

    1- Essential books (text books)

    -Murry R.L., " Nuclar Energy", Raleigh, North Carolina, 2000.

    - Alexander Lyzerovich " Wet steam turbines for nuclear power plants",

    2005.

    - Hashemain H. M., " Maintance of process Instrumentatio in Nuclear

    Power Plant", 2006.

    2- Recommended books

    -"Steam: its generation and Use", Babcock& Wilcox Comp., New Yourk,

    1965.

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    - Introduction

    I-Conventional Electrical Thermal Energy Generation

    Over 65 of the world's electrical energy used today is

    generated by steam/gas turbine generators burning fossil

    fuels as their source of energy

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    a Rankine cycle

    b Cas cycle

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    Gas turbine combined cycle (GTCC)

    technology is widely viewed as the way

    forward. In GTCC both the gas turbine and

    the steam turbine generate electricity.

    Initially, the gas turbine generates electricity

    by natural gas combustion. Then, the steam

    turbine generates electricity by using high-

    temperature steam recovered from the heat

    in exhaust gas emitted by the gas turbine.

    c Combined cycle

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    II-Non-Conventional Electrical Thermal Energy Generation

    a Nuclear Power Plants

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    In parabolic trough collector, long, U-curved mirrors focus the rays of the sun into an

    absorber pipe. The mirrors track the sun on one linear axis from north to south during

    the day. The pipe is seated above the mirror in the center along the focal line and has a

    heat-absorbent medium (mineral oil, synthetic oil, molten salt etc.) running in it. The

    sun’s energy heats up the oil, which carries the energy to the water in a boiler heat

    exchanger, reaching a temperature of about 400°C. The heat is transferred into the

    water, producing steam to drive turbine.

    b Solar Thermal Power Plants

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    c Geothermal Power Plants

    The center of the Earth is around 7000  oC easily hot enough to melt rock. In general, the temperature

    rises one degree Celsius for every 30 - 50 meters you go down, but this does vary depending on location.

    Pr ince Piero Ginor i Cont i  tested the first geothermal power generator on 4 July 1904 in Italy. It

    successfully lit four light bulbs. Later, in 1911, the world's first commercial geothermal power plant

    was built there. Italy was the world's only industrial producer of geothermal electricity until 1958. In

    1958, New Zealand became the second major industrial producer of geothermal electricity. In 1960,

    Pacific Gas and Electric began operation of the first successful geothermal electric power plant in the

    United States at The Geysers in California.

    Worldwide, 11,400 megawatts (MW) of geothermal power is online in 24 countries in 2012

    .

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    - Nuclear Power Station

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    Introduction to nuclear power 

    •   Uranium was discovered in 1789 by Martin Klaproth, a German chemist, and

    named after the planet Uranus.

    •   The science of atomic radiation, atomic change and nuclear fission was

    developed from 1895 to 1945, much of it in the last six of those years

    •   Over 1939-45, most development was focused on the atomic bomb

    •   From 1945 attention was given to harnessing this energy in a controlled

    fashion for naval propulsion and for making electricity

    •   Since 1956 the prime focus has been on the technological evolution of reliable

    nuclear power plants.

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    Economic Advantages

    •   The energy in one pound of highly enriched Uranium is comparable to

    that of one million gallons of gasoline.

    •   One million times as much energy in one pound of Uranium as in one

    pound of coal.

    •   Nuclear energy annually prevents 5.1 million tons of sulfur 2.4 million

    tons of nitrogen oxide 164 metric tons of carbon

    •   First commercial power plant, England 1956

    •   17% of  world’s electricity is from nuclear power 

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    Nuclear Reactions

      Nuclear reactions deal with interactions between the nuclei of atomsincluding of nuclear fission and nuclear fusion

    •   Both fission and fusion processes deal with matter and energy

    •   Fission is the process of splitting of a nucleus into two "daughter"

    nuclei leading to energy being released

    •   Fusion is the process of two "parent" nuclei fuse into one daughter 

    nucleus leading to energy being released

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    14

    In nuclear f is sion ,

    a large nucleus is bombarded with a small particle

    the nucleus splits into smaller nuclei and several neutrons large amounts of energy are released

    Nuclear Fission

    an unstable nucleus of U-

    236 forms and

    undergoes fission

    (splits) smaller nuclei

    are produced such asKr-91 and Ba-142

    neutrons are released

    to bombard more 235U

    When a neutron b ombards U-235,

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    15

    Chain Reaction

     A chain reaction occurs

    when a critical mass of

    uranium undergoes

    fission

    releasing a large

    amount of heat and

    energy that produces

    an atomic explosion

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    Fusion Reactions• A classic example of a fusion reaction is that of deuterium(heavy hydrogen) and tritium which is converted to Helium

    and release energy.

    p + p He + n + .42 MeV

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    17

    Nuclear Power Plants

    In nuclear power plants, fission is used to produce energy

    control rods in the reactor absorb neutrons to slow

    and control the chain reactions of fission

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    Energy Released

    The energy released can be calculated using the equation

    E = mc2

    Where:

    E = energy released (J)m = mass difference (gram)

    c = speed of light in a vacuum (3 x 108 ms-1)

    E

    m c2

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    - Nuclear Fission

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    Enrichment is a process that increases the capacity

    of uranium to fuel a nuclear chain reaction, either

    for use in nuclear power plants or for nuclear

    weapons.

    Uranium primarily occurs naturally as two isotopes:

    99.3% is Uranium-238 and 0.7% is Uranium-235.

    Their atoms are identical except for the number of 

    neutrons in the nucleus: Uranium-238 has three

    more and this makes it less able to fission. Uranium

    enrichment is used to increase the percentage of the

    fissile U-235. Nuclear reactors typically require

    uranium fuel enriched to about 3% to 5% U-235.

    Nuclear bombs typically use   ‘Highly   Enriched

    Uranium’,  enriched to 90% U-235, although lower

    levels of enrichment can be used.

    Uranium enrichment

    Gaseous Diffusion

    Gas Centrifuge

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    - Power Reactor 

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    Principle parts of a nuclear reactor: 

    i- Core : the nuclear fission process takes place inside this part,

    ii- Moderator: this reduces the speed of fast moving neutrons.

    Most moderators are graphite, water or heavy water.

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    What is the difference between moderator and control roads ?

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    - Types o f Reactors in

    Thermal Power Stat ions 

    a- Boiling Water

    Reactor 

    b- Pressurized Water

    Reactor 

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    - Boiling Water Reactor (B.W.R)

    http://en.wikipedia.org/wiki/Image:BoilingWaterReactor.gif

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    - Boiling Water Reactor (B.W.R)

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    - Pressurized Water Reactor  (P.W.R)

    http://en.wikipedia.org/wiki/Image:PressurizedWaterReactor.gif

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    - Pressurized Water Reactor (P.W.R)

    The pressur izing tank keeps the  

    water pressure > 80 bar  

    gauge ……….

    Why ? 

    How ? 

    What about the circulating pump?

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    - Nuclear Power Station

    a- Single-circuit b- Two-circuits c- Three-circuits

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    - Types of NPS steam Boi lers 

    - Based on components - Based on position

    a- steam generating plant with steam

    superheater and water economizer 

    b- steam generating plant without steam

    superheater and witout water economizer 

    c- steam generating plant without steam

    superheater and with water economizer 

    a- Vertical

    b- Horizontal

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    - Steam Boiler of Nuclear Power Station (NPS)

    Reactor

    Pump

    t/cool

    t//cool

    tfw

    tshsuperheater 

    evaporator 

    economizer 

    a- steam generating plant with steam superheater

    and water economizer 

    t/cool

    t//

    cool

    tsh

    tsat

    tfw

    tmi

    tmax

    Qecon.   QH.E..   Qs.h.

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    Reactor

    Pump

    t/cool

    t//cool

    tfw

    tsatevaporator 

    b- steam generating plant without steam superheater

    and witout water economizer 

    t/cool

    t//cool

    tsat

    tmax

    tmin

    QH.E..

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    c- steam generating plant without steam superheater

    and with water economizer 

    Reactor

    Pump

    t/cool

    t//cool

    tfw

    tsat

    evaporator 

    economizer 

    t/cool

    t//cool

    tsat

    tfw

    tmax

    tmin

    Qecon.

    QH.E..

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    - Inverted U-tube steam generator (Westinghouse)Vert ical bo i ler 

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    -Horizontal    shell natural-circulation steamgenerator designs used PWRs constructed in

    USSR.

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    Steam-generating Plant of The

    First Unit of The   Beloyarsk

    Nuclear Power Station

    B ili t t (BWR)

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    Boiling water reactor (BWR)Saturated steam

      to turbinem

    g

    mf 

    .

    .

    Chimney

    Feed water

    md.

    Recirculation

      watermi.

    Internal BWR

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    . . . . . ......

    Condenser

    Core

    Water-steam

      mixture

    x  e 

      Steam

    separator

    Saturation steam mg.

    mi.

    md.

    mf .

    Turbine

    Load

    Cooling

    Condensate

      pumpFeedwater

      pump

    Downcomerrecirculation

    water (saturated)

    External BWR

    Saturation s team mg.

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    -   Mass balance:

    igf gge   m/m)mm/(mx    

    e

    if 

    i

    i

    g

    g

    x

    mm

    m

    m*

    m

    m

    m

    mR 

     

    e

    e

    dif 

    x

    x1R mmm

     

    . . . . . ......

    Condenser

    Core

    Water-steam

      mixture

    x  e 

      Steam

    separator

    mi.

    md.

    mf .

    Turbine

    Load

    Cooling

    Condensate

      pumpFeedwater

      pump

    Downcomer

    recirculation

    water (saturated)

    -Recirculation ratio ( R ):

    -Average exit quality

    (dryness fraction)

    H t b l t i i i t f i l t d t

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    Divid ing eqn by m i 

    ddf f ii  hmhmhm    

    def ei

    e

    i

    d

    e

    i

    d

    i

    d

    i

    i

    hxh)x1(h

    xm

    m

    andx1m

    m

    hm

    mh

    m

    mh

     

     

    . . . . . ......

    Condenser

    Core

    Water-steam

      mixture

    x  e 

      Steam

    separator

    Saturation steam mg.

    mi.

    md.

    mf .

    Turbine

    Load

    Coolin

    Condensate

      pumpFeedwater

      pump

    Downcomer

    recirculation

    water (saturated)

    -Heat balance at mixing point of recirculated water

    at constant (core) pressure:

    BWR l i l fl h (j )

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    BWR reactor vessel internal flow path (jet pump)