High-Fidelity Light Water Reactor Analysis with the Numerical Nuclear Reactor

Author:

Weber David P.1,Sofu Tanju1,Yang Won Sik1,Downar Thomas J.2,Thomas Justin W.2,Zhong Zhaopeng2,Cho Jin Young3,Kim Kang Seog3,Chun Tae Hyun3,Joo Han Gyu4,Kim Chang Hyo4

Affiliation:

1. Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439

2. Purdue University, 1290 Nuclear Engineering, West Lafayette, Indiana 47907-1290

3. Korea Atomic Energy Research Institute 150 Dukjin-dong, Daejeon 305-600, Korea

4. Seoul National University, San 56-1, Sillim-dong, Seoul 151-742, Korea

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Reference20 articles.

1. M. J. HALSALL, “CACTUS, A Characteristics Solution to the Neutron Transport Equations in Complicated Geometries,” AEEW-R-1291, United Kingdom Atomic Energy Authority, Winfrith (1980).

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

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