Core Barrel

core barrel

The core barrel inside a reactor pressure vessel of LWR. It is only an illustrative example.

In general, reactor internals  are divided into three structural units:

  • the lower core support structure
  • the upper core support structure
  • the in-core instrumentation

The core barrel belongs to the lower core support structure, because it houses a reactor core. Other lower core support structures (lower core plate, core baffle or heavy reflector) are attached to the core barrel, which transmits the weight of the core to the reactor vessel. The barrel is a long, cylindrical, one-piece welded structure. Like most components of the internals, the core barrel is made of low carbon, chromium-nickel stainless steel, because it is situated in a corrosive environment (primary coolant comprises boric acid), and the material should not get oxidized.

The core barrel rests on a ledge machined into the pressure vessel flange and is centered at its upper flange with alignment pins. The lower core plate is welded to the bottom of the core barrel. The lower core plate consist of N holes for fixing fuel assemblies (N is number of fuel assemblies in specific reactor – e.g. 157.

The lower internals and also the core barrel remain in place during refueling, but may be removed for reactor pressure vessel in-service inspections.

The flow path for the reactor coolant through the reactor vessel would be:

  • The coolant enters the reactor vessel at the inlet nozzle and hits against the core barrel.
  • The core barrel forces the water to flow downward in the space between the reactor vessel wall and the core barrel, this space is usually known as the downcomer.
  • From the bottom of the pressure vessel, the flow is reversed up through the core in order to pass through the fuel assemblies, where the coolant temperature increases as it passes through the fuel rods.
  • Finally, the hotter reactor coolant enters the upper internals region, where it is routed out the outlet nozzle into the hot legs of primary circuit and goes on to the steam generators.
Nuclear and Reactor Physics:

  1. J. R. Lamarsh, Introduction to Nuclear Reactor Theory, 2nd ed., Addison-Wesley, Reading, MA (1983).
  2. J. R. Lamarsh, A. J. Baratta, Introduction to Nuclear Engineering, 3d ed., Prentice-Hall, 2001, ISBN: 0-201-82498-1.
  3. W. M. Stacey, Nuclear Reactor Physics, John Wiley & Sons, 2001, ISBN: 0- 471-39127-1.
  4. Glasstone, Sesonske. Nuclear Reactor Engineering: Reactor Systems Engineering, Springer; 4th edition, 1994, ISBN: 978-0412985317
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  6. Kenneth S. Krane. Introductory Nuclear Physics, 3rd Edition, Wiley, 1987, ISBN 978-0471805533
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  8. Robert Reed Burn, Introduction to Nuclear Reactor Operation, 1988.
  9. U.S. Department of Energy, Nuclear Physics and Reactor Theory. DOE Fundamentals Handbook, Volume 1 and 2. January 1993.

Advanced Reactor Physics:

  1. K. O. Ott, W. A. Bezella, Introductory Nuclear Reactor Statics, American Nuclear Society, Revised edition (1989), 1989, ISBN: 0-894-48033-2.
  2. K. O. Ott, R. J. Neuhold, Introductory Nuclear Reactor Dynamics, American Nuclear Society, 1985, ISBN: 0-894-48029-4.
  3. D. L. Hetrick, Dynamics of Nuclear Reactors, American Nuclear Society, 1993, ISBN: 0-894-48453-2. 
  4. E. E. Lewis, W. F. Miller, Computational Methods of Neutron Transport, American Nuclear Society, 1993, ISBN: 0-894-48452-4.