SOME OUTSTANDING PROBLEMS IN NEUTRON TRANSPORT COMPUTATION

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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.
Publisher
KOREAN NUCLEAR SOC
Issue Date
2009-05
Language
English
Article Type
Article
Keywords

CARLO EIGENVALUE CALCULATIONS; RAY-EFFECT MITIGATION; CROSS-SECTION; SYSTEMS; BIASES

Citation

NUCLEAR ENGINEERING AND TECHNOLOGY, v.41, no.4, pp.381 - 390

ISSN
1738-5733
URI
http://hdl.handle.net/10203/97055
Appears in Collection
NE-Journal Papers(저널논문)
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