Neutron flux in the context of Neutron scattering


Neutron flux in the context of Neutron scattering

Neutron flux Study page number 1 of 1

Play TriviaQuestions Online!

or

Skip to study material about Neutron flux in the context of "Neutron scattering"


HINT:

👉 Neutron flux in the context of Neutron scattering

Neutron scattering, the irregular dispersal of free neutrons by matter, can refer to either the naturally occurring physical process itself or to the man-made experimental techniques that use the natural process for investigating materials. The natural/physical phenomenon is of elemental importance in nuclear engineering and the nuclear sciences. Regarding the experimental technique, understanding and manipulating neutron scattering is fundamental to the applications used in crystallography, physics, physical chemistry, biophysics, and materials research.

Neutron scattering is practiced at research reactors and spallation neutron sources that provide neutron radiation of varying intensities. Neutron diffraction (elastic scattering) techniques are used for analyzing structures; where inelastic neutron scattering is used in studying atomic vibrations and other excitations.

↓ Explore More Topics
In this Dossier

Neutron flux in the context of Breeding blanket

A breeding blanket is a device used in nuclear engineering to transmute quantities of an element, using the neutron flux from a fission reactor or fusion reactor. In the fission context, breeding blankets have been used since the 1950s in breeder reactors, to manufacture fission fuel from fertile material. In the fusion context, they have been conceptualized for the manufacture of tritium from lithium-6. In both scenarios, neutron radiation is converted into thermal energy in the blanket, leading it to require its own cooling system.

View the full Wikipedia page for Breeding blanket
↑ Return to Menu

Neutron flux in the context of Advanced Test Reactor

The Advanced Test Reactor (ATR) is a research reactor at the Idaho National Laboratory, located east of Arco, Idaho. This reactor was designed and is used to test nuclear fuels and materials to be used in power plants, naval propulsion, research and advanced reactors. It can operate at a maximum thermal power of 250 MW and has a "Four Leaf Clover" core design (similar to the Camunian rose) that allows for a variety of testing locations. The unique design allows for different neutron flux (number of neutrons impacting one square centimeter every second) conditions in various locations. Six of the test locations allow an experiment to be isolated from the primary cooling system, providing its own environment for temperature, pressure, flow and chemistry, replicating the physical environment while accelerating the nuclear conditions.

The ATR is a pressurized light water reactor (LWR), using water as both coolant and moderator. The core is surrounded by a beryllium neutron reflector to concentrate neutrons on experiments, and houses multiple experiment positions as well. It operates at low temperature and pressure 71 °C (160 °F) and up to 2.69 MPa water pressure. The ATR reactor vessel is solid stainless steel, 35 feet (11 m) tall by 12 feet (3.7 m) across. The core is approximately 4 feet (1.2 m) tall by 4 feet (1.2 m) across.

View the full Wikipedia page for Advanced Test Reactor
↑ Return to Menu