Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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SOME OUTSTANDING PROBLEMS IN NEUTRON TRANSPORT COMPUTATION

  • Published : 2009.05.31
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Abstract

This article provides selects of outstanding problems in computational neutron transport, with some suggested approaches thereto, as follows: i) ray effect in discrete ordinates method, ii) diffusion synthetic acceleration in strongly heterogeneous problems, iii) method of characteristics extension to three-dimensional geometry, iv) fission source and $k_{eff}$ convergence in Monte Carlo, v) depletion in Monte Carlo, vi) nuclear data evaluation, and vii) uncertainty estimation, including covariance data.

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References

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