Abstract
For a randomly inhomogeneous medium the uncollided neutron flux density is usually calculated using the average properties of the medium. It is shown that this procedure leads to an underestimation of the flux density.
Original language | English |
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Pages (from-to) | 47-48 |
Number of pages | 2 |
Journal | Kerntechnik |
Volume | 56 |
Issue number | 1 |
State | Published - 1 Feb 1991 |
ASJC Scopus subject areas
- Radiation
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- General Materials Science
- Safety, Risk, Reliability and Quality