Uncertainty quantification in neutron transport with generalized polynomial chaos using the method of characteristics-Reference-Cited by-同舟云学术

Uncertainty quantification in neutron transport with generalized polynomial chaos using the method of characteristics

Published:2012-07 Issue: Volume:45 Page:14-28
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Ayres D.A.F.,Eaton M.D.,Hagues A.W.,Williams M.M.R.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference26 articles.

1. Askew, J.R., 1972. A Characteristics Formulation of the Neutron Transport Equation in Complicated Geometries. Tech. Rep. AEEW-M 1108, United Kingdom Atomic Energy Establishment.

2. Carlson, B.G., Bell, G.I., 1958. Solution to the neutron transport equation by the sn method. In: 2nd U.N. Conf. on Peaceful uses of Atomic Energy, Geneva. p. 2386.

3. Fichtl, E.D., 2009. Stochastic Methods for Uncertainty Quantification in Radiation Transport. Ph.D. Thesis, University of New Mexico.

4. The stochastic collocation method for radiation transport in random media;Fichtl;Journal of Quantitative Spectroscopy and Radiative Transfer,2011

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