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Solution of the C5G7MOX benchmark three-dimensional extension problems by the DeCART direct whole core calculation code

  • Published:2006-07 Issue:5 Volume:48 Page:456-466
  • ISSN:0149-1970
  • Container-title:Progress in Nuclear Energy
  • language:en
  • Short-container-title:Progress in Nuclear Energy

Author:

Cho Jin Young,Joo Han Gyu

Publisher

Elsevier BV

Subject

Waste Management and Disposal,Energy Engineering and Power Technology,Safety, Risk, Reliability and Quality,Nuclear Energy and Engineering

Reference15 articles.

1. Three-dimensional heterogeneous whole core transport calculation employing planar MOC solution;Cho;Trans. Am. Nucl. Soc.,2002

2. Cell-based CMFD formulation for acceleration of whole-core method of characteristics calculations;Cho;J. Kor. Nucl. Soc.,2002

3. Fusion of method of characteristics and nodal method for 3-D whole-core transport calculation;Cho;Trans. Am. Nucl. Soc.,2002

4. Interface nodal current techniques for multidimensional reactor calculations;Finnemann;Atomkernenergie,1977

5. CACTUS, A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries;Halsall,1980

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