A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Calculation in Curvilinear Geometries-Reference-Cited by-同舟云学术

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A Discrete Ordinates Nodal Method for One-Dimensional Neutron Transport Calculation in Curvilinear Geometries

Published:1999-11 Issue:3 Volume:133 Page:350-357
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Wu Yican¹,Xie Zhongsheng²,Fischer Ulrich³

Affiliation:

1. Chinese Academy of Sciences, Institute of Plasma Physics P.O. Box 1126, Hefei, Anhui, 230031, China

2. Xi’an Jiaotong University, Nuclear Reactor Division Energy & Power Engineering Department Xi’an, Sha’anxi, 710049, China

3. Forschungszentrum Karlsruhe, Institute of Neutron Physics and Reactor Technology P.O. 3640, D-76021, Karlsruhe, Germany

Publisher

Informa UK Limited

Subject

Nuclear Energy and Engineering

Link

https://www.tandfonline.com/doi/pdf/10.13182/NSE99-A2095

Reference10 articles.

1. H. GREENSPAN, C. N. KELBER, and D. OKRENT, Computing Method in Reactor Physics, pp. 171–226, Gordon and Breach Science Publishers (1968).

2. W. W. ENGLE, “A User’s Manual for ANISN,” USAEC Report K-1693, U.S. Atomic Energy Commission (1967)

3. “ANISN-ORNL, A One-Dimensional Discrete Ordinates Transport Code,” CCC-254, Oak Ridge National Laboratory (1973).

4. R. E. PEVEY, “Development of a New Two-Dimensional Cartesian Geometry Nodal Multigroup Discrete Ordinates Method,” ORNL/CSD/TM-182, U.S. Atomic Energy Commission (1982).

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