Research Article
Design, Construction, and Modeling of a 252Cf Neutron Irradiator
Table 1
Comparison of neutron sources.
| | Neutron source | Production mode | Neutron yield (n/s) | Flux | Average neutron energies (MeV) | Spectrum | Cost ($) |
| | 241AmBe | () [19] | 7.0 × 10−5
(per Bq) | Low | 3.3, 4.3, 4.9, 6.8, 7.7, 9.5 | Continuous | 104 | | 241AmF | 4.0 × 10−6
(per Bq) | 1.8, 2.1 | | 241AmB | 1.4 × 10−5
(per Bq) | 2.6 | | 239PuBe [2] | 3.8 × 10−5
(per Bq) | ~3.3 |
| | D-D generator [20] | | 106–1011 | Moderate | 2.45 | Monoenergetic | 105 | | D-T generator [20] | | 108–5 × 1013 | 14.1 |
| | 252Cf [21] | Spontaneous fission | 1.2 × 10−1
(per Bq) | Low | 2.0 | Fission | 104 | | Research reactor [12] | Fission | >1016 | High | >108 [7] |
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