Results 141 to 150 of about 25,910 (172)
Some of the next articles are maybe not open access.

Structural Aspects of Neutron Survival Probabilities

Journal of Nuclear Engineering
The neutron survival probability (and related quantities including probabilities of extinction and initiation) is a central element of the broader stochastic theory of neutron populations and finds application in fields including reactor start-up ...
Scott D. Ramsey
semanticscholar   +1 more source

The measurement of the thermal neutron absorption cross sections of graphite and carbon by W. Bothe and P. Jensen – a recalculation of the experiments and the graphite problem during the early uranium work

Kerntechnik
The experiments of W. Bothe and P. Jensen from the year 1940 to determine of the thermal neutron absorption cross sections of graphite and carbon were recalculated with current neutron transport codes and latest nuclear data in order to find out the ...
H. Brockmann
semanticscholar   +1 more source

Study on Neutronics Properties of Zirconium Hydride Moderator in Reactor

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
The metal hydride ZrH1.6 has a high hydrogen atom density, equivalent to that of liquid water. Compared to other hydrides (such as H2O and organic compounds), particularly at high temperatures, ZrH1.6 exhibits good strength and stability.
Shixin Lin, Youqi Zheng
semanticscholar   +1 more source

A Nonlocal Meso-Scale Damage Model for Nuclear Graphite

Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
Due to its excellent nuclear physical properties and high-temperature resistance, graphite is widely used in many areas of the nuclear industry.
Yan Ma   +6 more
semanticscholar   +1 more source

Thermal Energy Transport in Oxide Nuclear Fuel

Chemical Reviews, 2022
David H Hurley   +2 more
exaly  

Home - About - Disclaimer - Privacy