Appendix A Neutron Flux Dose Equivalents | ||
Neutron Energy (MeV) | Number of Neutrons per Square Centimeter for a Dose Equivalent of 1 Rem (neutrons/cm 2 ) (10 millisieverts) | Average Flux Density to Deliver 100 millirem (1 millisievert) in 40 Hours (neutrons/cm 2 per second) |
Thermal | 970 x 106 | 670 |
0.0001 | 720 x 106 | 500 |
0.005 | 820 x 106 | 570 |
0.02 | 400 x 106 | 280 |
0.1 | 120 x 106 | 80 |
0.5 | 43 x 106 | 30 |
1.0 | 26 x 106 | 18 |
2.5 | 29 x 106 | 20 |
5.0 | 26 x 106 | 18 |
7.5 | 24 x 106 | 17 |
10.0 | 24 x 106 | 17 |
10 to 30 | 14 x 106 | 10 |
La. Admin. Code tit. 33, § XV-199