Use of Sn-method for computing space-energy distributions of fast neutron fluxes in reactor screen-Reference-Cited by-同舟云学术

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Use of Sn-method for computing space-energy distributions of fast neutron fluxes in reactor screen

Published:1974-05 Issue:5 Volume:36 Page:493-495
ISSN:0038-531X
Container-title:Soviet Atomic Energy
language:en
Short-container-title:At Energy

Author:

Broder D. L.,Popkov K. K.,Trofimov I. N.,Tsvetkova S. A.

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering,General Engineering,Nuclear Energy and Engineering

Link

http://link.springer.com/content/pdf/10.1007/BF01170152.pdf

Reference11 articles.

1. G. I. Marchuk, Methods of Computing Nuclear Reactors [in Russian], Gosatomizdat, Moscow (1961).

2. B. Carlson, Solution of the Transport Equation, Sn-Approximation, USAEC Document LA 1891 (1955).

3. D. L. Broder et al., Kernenergie,13, No. 12, 380 (1970).

4. L. P. Abagyan et al., Group Constants for Computation of Nuclear Reactors [in Russian], Atomizdat, Moscow (1964).

5. T. A. Germogenova et al., Transport of Fast Neutrons in Plane Screens [in Russian], Atomizdat, Moscow (1971).

Cited by 1 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Combined use of Sn and integral-equations methods to calculate angular characteristics of a radiation field;Soviet Atomic Energy;1982-02

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