Abstract
The concept of the MOL Cavity Fission Spectrum Standard Neutron Field is highlighted. Two applications to neutron dosimetry are treated - Neutron flux determination by distinct fission fragment absolute radiometric measurements on fission foils. - 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.
Original language | English |
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Pages (from-to) | 238-242 |
Number of pages | 5 |
Journal | Proceedings of SPIE - The International Society for Optical Engineering |
Volume | 2339 |
DOIs | |
State | Published - 3 Mar 1995 |
Event | 4th International Conference on Applications of Nuclear Techniques: Neutrons and Their Applications 1994 - Crete Duration: 12 Jun 1994 → … |
ASJC Scopus subject areas
- Electronic, Optical and Magnetic Materials
- Condensed Matter Physics
- Computer Science Applications
- Applied Mathematics
- Electrical and Electronic Engineering