Neutron distribution influence on the thermal design of a nuclear fuel rod
Author:
Publisher
Elsevier BV
Subject
Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Reference13 articles.
1. Nuclear Engineering;Bonilla,1957
2. Principles of Nuclear Reactor Engineering;Glasstone,1955
3. Nuclear Heat Transport;Wakil,1971
4. Neutron Transport Theory;Davison,1958
5. The Physical Theory of Neutron Chain Reactors;Weinberg,1958
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. STRESSES INDUCED BY AXIAL THERMAL GRADIENTS IN THE CLADDING OF NUCLEAR FUEL RODS;Current Advances in Mechanical Design and Production III;1986
2. Steady axially symmetric three-dimensional thermoelastic stresses in fuel rods;Nuclear Engineering and Design;1984-08
3. RELATIONSHIP BETWEEN NUCLEAR AND THERMOMECHANICAL ASPECTS IN FUEL ROD DESIGN;Journal of Thermal Stresses;1982-07
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