Neutron Moderation 1 (Research Reactor as Neutron Source)
Masaji Arai
Abstract
Open-access reader
Masaji Arai
Abstract
Open-access reader
A thermal neutron reactor produces neutrons of energies in the range of 1-2 MeV, as a result of a nuclear fission reaction of uranium. Neutrons with this high energy range are not suitable for neutron scattering experiments. Therefore, in a research reactor for neutron beam utilization, a thermal moderator is needed to be installed around the primary source to slow down the neutrons to energy levels of 5 meV to 500 meV. Additionally, almost major research reactors equip also at least one cold neutron source, a special moderator operated at cryogenic temperature, which can slow down neutrons to energy levels lower than 5 meV.
A significance statement is not available in the OpenAlex record.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
A thermal neutron reactor produces neutrons of energies in the range of 1-2 MeV, as a result of a nuclear fission reaction of uranium. Neutrons with this high energy range are not suitable for neutron scattering experiments. Therefore, in a research reactor for neutron beam utilization, a thermal moderator is needed to be installed around the primary source to slow down the neutrons to energy levels of 5 meV to 500 meV. Additionally, almost major research reactors equip also at least one cold neutron source, a special moderator operated at cryogenic temperature, which can slow down neutrons to energy levels lower than 5 meV.
Key concepts: Neutron cross section, Neutron, Neutron temperature, Neutron moderator, Neutron source, Nuclear physics, Fast fission, Neutron scattering