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1
Future Power Production System
  • Presentation by
  • M. I. Al-Jarallah
  • Department of Physics
  • King Fahd University of Petroleum Minerals
  • Dhahran-Saudi Arabia
  • Contact 009 663 860 2281
  • Email mibrahim_at_kfupm.edu.sa
  • Homepage
  • http//faculty.kfupm.edu.sa/phys/mibrahim

2
Future Power Production System
  • Introduction
  • Advantages Disadvantages
  • Available ADSs and Those in The Design Stages
  • Diagrams of the Facilities
  • Target, Fuel, Coolant and Accelerator Types
  • The Physics of Spallation
  • Applications of ADSs
  • Conclusion

3
1. Introduction
  • Neutrons resulting from interaction of
    relativistic projectiles with extended targets
    e.g. protons on lead, can be used for energy
    production and nuclear waste transmutation, in
    sub-critical nuclear assemblies. These systems
    are known as Accelerator Driven Systems ADS,
    and are also called AD Sub-critical Reactors
    ADSR. They are designed to replace or
    supplement conventional nuclear reactors as
    neutron sources.
  • In such system, an accelerator produces an
    energetic and intense proton beam several
    hundred MeV to a few GeV, 5 100 mA, which is
    made interact with a cooled target consisting of
    lead or other high mass nuclei to produce fast
    neutrons through Spallation Process. Spallation
    Process is the nuclear reaction of high energy
    protons with nuclei.
  • These neutrons can then be moderated and used for
    some of the same purposes as the neutrons that
    are produced in a reactor through the fission
    process. Similar ideas were first proposed more
    than fifty years ago !

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2. Advantages and Disadvantages of ADS
  • A) Advantages of an ADS over conventional
    reactors
  • Greater efficiency in neutron production
  • Greater safety in operation
  • Less production of unwanted radioactive materials
    in particular, Pu or other transuranium actinides
    by using thorium fuel. Thorium is more abundant
    than Uranium, it generates much less transuranic
    actinides among the radioactive waste and the
    risk of nuclear proliferation is negligible.
    Thorium based thermal reactor cannot operate in a
    satisfactory way on a self sufficient 232Th
    233U cycle. Evidently an external supply of
    neutrons remove the above mentioned limitations.

6
  • B) Disadvantages of ADS compared with existing
    reactors
  • The need to construct accelerators that are
    considerably more powerful than existing one.
  • The need to accurately determine many as yet
    unknown or poorly known nuclear data for the
    target and other material used in the system
  • The need to develop chemical separation and
    partitioning methods that are specific to the
    process in an ADS.

7
3. Available ADS and those in the Design Stage
  • Because of the mentioned problems, only a few ADS
    are in use or have been designed to some degree
    of details at the present time.
  • These are
  • The SING facility at the Paul Scherror Institute
    PSI in Villigen, Switzerland, makes uses of the
    590 MeV, 1.5 mA proton beam from PSI cyclotron
    (nth 1013 cm-2 s-1,)
  • Russian facility in the Joint Institute for
    Nuclear Research, Dubna, Russia (GeV).
  • MYRRHA A multipurpose ADS being developed
    jointly by Belgian Nuclear Research Center and
    Ion Beam Applications 350 MeV, 5 mA proton
    beam.
  • The Spallation neutron facility to be built at
    Oakridge National Laboratory ORNL in
    cooperation with several other U.S. national
    laboratories, will have about twice the neutron
    flux in, SING facility
  • the European Spallation Neutron Source ESS and
    a Japanese facility with similar design features,
    will have an order of magnitude higher thermal
    neutron flux of SING facility.

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Fig. 1 Schematic View of the Target System
9
Fig. 2 Schematic Diagram of a Separate High
Energy Target
10
Fig. 3 Scheme of the Target and Fuel Spheres
11
Fig. 4 Diagram of a Beam Driven Liquid Cooled
ADS Without Separate Target.
12
Fig. 5 Diagram of the Fuel Assembly
13
Fig. 6 Diagram of Spherical Fuel Pellets in a
Fluidized Bed Configuration
14
Fig. 7 Global view of the present design of MYRRHA
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Fig. 8 MYRRHA in a confinement building that is
inaccessible during operation
16
5. Target, Fuel, Coolant and Accelerator Types
  • A) Target Types
  • Solids or liquids can be used as fuel. The
    requirement for both is high neutron yields and
    for solids they should have high fusion
    temperature
  • Lead fusion 327o heavy target is considered
    practical
  • Solid Tungsten
  • Solid metallic, oxides, nitrides, carbides,
    etc.
  • Lead Bismulth liquid targets

17
The advantages of liquid metal targets over
volume cooled solid targets
  • Higher heat removal capability due to the fact
    that the heated material is transported rather
    than the heat.
  • Higher spallation material density in the volume
    due to absence of cooling channels which tend to
    dilute the target the more the higher the power
    density.
  • No or minimum amount of water with its associated
    problems in the proton beam.
  • No life time limit caused by radiation damage in
    the target material.
  • Significantly lower specific radioactivity in the
    target material due to the target mass used and
    perfect mixing, making an emergency cooling
    system unnecessary.
  • The inside pressure in the target can be
    significantly lower than in water cooled system,
    putting less stringent requirements on the
    casing wall.

18
  • B) Fuel Types
  • Solids metallic, oxides, nitrides, carbides,
    etc.
  • Molten Salt Fluorides or Chlorides
  • C) Cooling Agent
  • Gas
  • Molten Metal Sodium, Lead, or Lead, Bismulth
  • Molten Salts Transparent to visible light, and
    thus allow visual inspection
  • D) The Accelerator System
  • Cyclotron more compact and thus require less
    space and more economical. However there is
    current limitation 5 10 mA.
  • LINACS Current ? 100 mA

19
  • 6. The Physics of Spallation
  • The physics of spallation is in fact rather
    complex because of the large range of energies
    involved, and efforts are still going on in
    various locations to develop models that
    reproduce all the pertinent experimental
    observations.
  • During the spallation process not only ns but
    also protons and other light nuclei are emitted
    from the excited nuclei. As a consequence, the
    residual nuclei are not only neutronpoor
    isotopes of the parent nucleus that decay, mainly
    by internal p ? n conversion and ? emission,
    into lower Z elements, but these elements are
    also created directly in the spallation process.

20
  • About 90 of the ns released from thick targets
    in a spallation
  • reaction can be described by characteristic
    energies around
  • 1 2 MeV and are emitted more or less
    isotopically. Their
  • spectral and angular distributions thus resemble
    closely to those
  • of fission ns Figure 9 .
  • The small fraction cascade ns whose energy can
    reach up to
  • that of the primary particles driving the
    reaction, are emitted
  • mainly in the forward hemisphere relative to the
    proton beam.
  • They are difficult to moderate and thus
    constitute the main
  • problem in shielding and activation in a
    spallation neutron
  • source.

21
Fig. 9 Calculated neutron spectra for fission
and for spallation in a tungsten target
22
Fig. 10 Chain of Possible Reactions Starting from
Initial 232Th fuel. Cross Sections are for
Thermal Neutrons in Barns.
23
Fig. 11 Time Evolution of the Composition of an
Initial, Thin Thorium Slab Exposed to a Constant
Thermal Neutron Flux of 1.0 x1014 cm-2 s-1.
24
Fig. 12 Chain of Possible Reactions Starting from
initial 238U fuel.
25
Fig. 13 The Evolution of the Composition of an
Initially Slightly Depleted Uranium Fuel.
26
7. Applications of ADSs
  • Production of Energy a credible alternative to
    fast breeder and fusion reactors. They give a
    unique opportunity to improve the social
    acceptability of fission energy.
  • Nuclear Waste Processing
  • Transmutation, which by neutron capture,
    transforms a radioactive nucleus into a stable
    one.
  • Incineration which amount to nuclear fission
    following neutron capture transuranic elements
    such as Pu and minor actinides Np, Am, Cn. They
    have high radiotoxicities due to this dominant ?
    decay. They have long lifetimes, up to 25000
    years for 239Pu. At least one incineration
    reactor for four PWRs would be needed if one
    wants to incinerate completely plutonium and
    minor actinides.
  • Production of radioisotopes for medical and
    industrial purposes.
  • Production of tritium

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8. Conclusion
  • It is evident that ADS are now accepted by
    sponsoring agencies and by members of the nuclear
    community as valuable new tools in basic research
    and in applications.
  • This will require new technologies of immediate
    relevance for ADS development. A first
    demonstration prototype of several tense of MW
    could be build within 5 7 years.
  • An industrial realization would probably require
    at lest 15 years.

30
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