Recent content by NuclearPhysicist

  1. NuclearPhysicist

    Problem with F5, FT5 and FU5 card in MCNP

    Is there anyone here, who know MCNP very well?
  2. NuclearPhysicist

    Problem with F5, FT5 and FU5 card in MCNP

    Ex-core detector placed from the neutron source (first fuel assembly) in the distance about 1,5 m in concrete physical shielding.
  3. NuclearPhysicist

    Problem with F5, FT5 and FU5 card in MCNP

    Dear colleagues, Could you give advice how to evaluate neutron flux from the part of fuel assemply in the ex-core detector? I'm looking forward for your reply!
  4. NuclearPhysicist

    Problem with F5, FT5 and FU5 card in MCNP

    Dear colleagues, I'm trying to make calculation of flux in ex-core detector. I have to evaluate neutron flux from the part of fuel assembly in full-scale model of PWR. I don't know very well MCNP Code, so I decided to use F5 card with option FT5 ICD and FU5 671 number of cells, where the part...