Standard neutron fields at the BR1 reactor and their application to neutron dosimetry

Pierre J. D'hondt; H. A´t Abderrahim; A. Fabry

doi:10.1117/12.204161

3 March 1995 Standard neutron fields at the BR1 reactor and their application to neutron dosimetry

Pierre J. D'hondt, H. A´t Abderrahim, A. Fabry

Proceedings Volume 2339, International Conference on Neutrons and Their Applications; (1995) https://doi.org/10.1117/12.204161
Event: 4th International Conference on Applications of Nuclear Techniques: Neutrons and their Applications, 1994, Crete, Greece

Abstract

The concept of the MOL cavity fission spectrum standard neutron field is highlighted. Two applications to neutron dosimetry are treated: (1) Neutron flux determination by distinct fission fragment absolute radiometric measurements on fission foils. (2) Neutron flux determination by detection of the delayed neutrons emitted by a fissile sample. For both applications the measuring technique, the calibration procedure, the application domain, the advantages of the method, as well as the restrictions in absolute neutron flux determination are considered.

Citation Download Citation

Pierre J. D'hondt, H. A´t Abderrahim, and A. Fabry "Standard neutron fields at the BR1 reactor and their application to neutron dosimetry", Proc. SPIE 2339, International Conference on Neutrons and Their Applications, (3 March 1995); https://doi.org/10.1117/12.204161

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