Neutron transport in a reactor system with temperature feedback-Reference-Cited by-同舟云学术

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Neutron transport in a reactor system with temperature feedback

Published:1981-01 Issue:2-3 Volume:8 Page:191-202
ISSN:0149-1970
Container-title:Progress in Nuclear Energy
language:en
Short-container-title:Progress in Nuclear Energy

Author:

Pao C.V.

Publisher

Elsevier BV

Subject

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

Reference8 articles.

1. Nuclear Reactor Theory;Bell,1970

2. Neutron transport with temperature feedback;Belleni-Morante;Nucl. Sci. Eng.,1976

3. Global solution for a problem of neutron transport with temperature feedback;Busoni,1977

4. Faster Reactor Safety;Graham,1971

5. Stability of nuclear reactors with changes in eigenvalue;Nguyen;Nucl. Sci. Eng.,1973

Cited by 3 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. Nonlinear reactor multigroup neutron transport system: Existence and stability problems;Journal of Mathematical Physics;1991-04

2. A nonlinear study in a reactor with delayed temperature feedback;Progress in Nuclear Energy;1990-01

3. The time-dependent multigroup transport equations in reactor kinetics;Annals of Nuclear Energy;1989-01

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