The Determination of the Thermal Neutron Flux in a Research Reactor

Since a research reactor serves as a neutron source for a large number of experiments, knowledge of the neutron flux, and of its spatial and spectral energy distribution is of great importance, not only for purposes of experimental reactor physics (e.g., determination of specific data with regard to a new reactor), and for reactor operation (e.g., determination of reactor power level) but also for numerous radiation experiments in solid state physics, nuclear physics and radiation chemistry. In addition, surveillance tests on structural materials in nuclear reactors require that all test specimens receive a neutron exposure that is representative of the component they are designed to monitor.

Grantor dc:publisher

Creighton University

Year dc:date.issued

1971

Author dc:creator

• Blotcky, Alan Jay

Advisor dc:contributor.advisor

• Cipolla, Sam J.

Statement dc:rights

• A non-exclusive distribution right is granted to Creighton University and to ProQuest following the publishing model selected above.

Language dc:language.iso

en_US

Handle dc:identifier.uri

http://hdl.handle.net/10504/112596

OAI identifier oai:identifier

oai:cdr.creighton.edu:10504/112596