Adaptive Nodal Transport Methods for Reactor Transient Analysis | Zendy

Thomas Downar | Zendy; E.E. Lewis | Zendy

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Adaptive Nodal Transport Methods for Reactor Transient Analysis

Author(s) -

Thomas Downar,

E.E. Lewis

Publication year - 2005

Publication title -

osti oai (u.s. department of energy office of scientific and technical information)

Language(s) - English

Resource type - Reports

DOI - 10.2172/850366

Subject(s) - transient (computer programming) , neutron transport , nuclear engineering , code (set theory) , flux (metallurgy) , neutron flux , nodal analysis , transient analysis , nodal , neutron , physics , computer science , nuclear physics , transient response , environmental science , materials science , engineering , electrical engineering , programming language , biology , anatomy , set (abstract data type) , quantum mechanics , metallurgy

Develop methods for adaptively treating the angular, spatial, and time dependence of the neutron flux in reactor transient analysis. These methods were demonstrated in the DOE transport nodal code VARIANT and the US NRC spatial kinetics code, PARCS

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