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Hi every body, i'm working and calculating the keff, and total

  1. hi every body, i'm working and calculating the keff, and total

    hi every body, i'm working and calculating the keff, and total fission produced in critical accident in the cylindrical model. If critical mass is roached.
    I calculated variable multiply coefficient (keff) by MCNP 5.
    also total fission produced i don't know how to calculate this variable,
    I really need your help.
    thanks you very much for your help.
     
  2. jcsd
  3. Re: Tokai-mura(jco)

    Well, you could just take the fuel depletion in atoms...
     
  4. Astronuc

    Staff: Mentor

    Re: Tokai-mura(jco)

    Total fission would be the integral of Ʃf and flux ∅(x) over the volume and time. One could reasonably assume a Gaussian pulse and mostly a prompt neutron flux.
     
  5. Re: Tokai-mura(jco)

    thanks for your answer,
    and could you show me about Ʃf clearly, eg i want to calculate with thermal neutron(E < 6.625e-7 MeV), and fission cause of U235. how is Ʃf?
    Thanks you !
     
  6. Astronuc

    Staff: Mentor

    Re: Tokai-mura(jco)

    What is the initial form of the material? Solid metal, ceramic, or a aqueous solution? One can estimate the reactivity from keff-1.

    Ʃf = NU235 * σf

    and N is the atomic density of the material.
     
  7. Re: Tokai-mura(jco)

    Thanks you very much, i have calculate critical model with solution material, one things i don't know that σf, and could you show me how to find it?
    Solution : UO2(NO3)2 . 6 H2O.
     
  8. Astronuc

    Staff: Mentor

    Re: Tokai-mura(jco)

    I would expect it is in a library of cross-sections in MCNP 5.

    Otherwise, http://www.nndc.bnl.gov/sigma/index.jsp?as=235&lib=endfb7.1&nsub=10 - and find (n,total fission).

    There will be no delayed neutrons.
     
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