Abstract
The use of 14 MeV neutron generators for radionuclide production is discussed. The 14 MeV neutron generator is described and tables of some short-lived radioisotopes which can be produced by (n, p), (n, α) and (n, 2n) reactions are given. An estimate of the capital costs of a sealed tube 14 MeV generator with output of 1011 neutrons/s and its annual operating costs is compared to those of typical middle-sized cyclotrons currently used for radioisotope production. Simultaneous use of 14 MeV neutrons for radiotherapy and radionuclide production is suggested.
| Original language | English |
|---|---|
| Pages (from-to) | 275-278 |
| Number of pages | 4 |
| Journal | International Journal of Applied Radiation and Isotopes |
| Volume | 30 |
| Issue number | 5 |
| DOIs | |
| State | Published - 1 Jan 1979 |
ASJC Scopus subject areas
- Radiation
- Nuclear Energy and Engineering
- Radiology Nuclear Medicine and imaging
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