Energy spectrum of 68-MeV p-7Li source neutrons for shielding experiment. The flux at monoenergetic peak (60.8-72.5 MeV) is normalized to unity. The absolute peak flux for each experiment can be obtained from Table 1. (Ratio of the peak flux to the total flux above 6.5 MeV is 1:2.61.) All values should be multiplied by the corresponding value of "Peak Flux of Source Neutron" in the table of "Numerical Data for Experimental Geometry and Source Neutrons" --------------------------------- Upper Neutron Error Energy Flux [MeV] [n/MeV] [n/MeV] --------------------------------- 0 2.37E-02 8.50E-04 6.5 2.37E-02 8.50E-04 7.5 2.40E-02 8.55E-04 8.5 2.44E-02 8.67E-04 9.5 2.51E-02 8.86E-04 10.5 2.57E-02 9.07E-04 11.5 2.53E-02 8.98E-04 12.5 2.59E-02 9.21E-04 13.5 2.68E-02 9.46E-04 14.5 2.71E-02 9.60E-04 15.5 2.79E-02 9.83E-04 16.5 2.80E-02 9.89E-04 17.5 2.86E-02 1.01E-03 18.5 2.95E-02 1.04E-03 19.5 3.10E-02 1.09E-03 20.5 3.15E-02 1.10E-03 21.5 3.33E-02 1.45E-03 22.5 3.38E-02 1.46E-03 23.5 3.53E-02 1.52E-03 24.5 3.62E-02 1.56E-03 25.5 3.67E-02 1.57E-03 26.5 3.84E-02 1.64E-03 27.5 3.81E-02 1.62E-03 28.5 3.93E-02 1.67E-03 29.5 3.85E-02 1.64E-03 30.5 3.88E-02 1.65E-03 31.5 3.86E-02 1.64E-03 32.5 3.88E-02 2.39E-03 33.5 3.76E-02 2.33E-03 34.5 3.70E-02 2.28E-03 35.5 3.72E-02 2.30E-03 36.5 3.66E-02 2.26E-03 37.5 3.62E-02 2.23E-03 38.5 3.40E-02 2.10E-03 39.5 3.35E-02 2.07E-03 40.5 3.32E-02 2.05E-03 41.5 3.34E-02 2.07E-03 42.5 3.14E-02 1.94E-03 43.5 3.21E-02 1.98E-03 44.5 3.10E-02 1.92E-03 45.5 3.10E-02 1.92E-03 46.5 3.16E-02 1.95E-03 47.5 3.09E-02 1.90E-03 48.5 3.00E-02 1.85E-03 49.5 2.86E-02 1.77E-03 50.5 2.80E-02 1.73E-03 51.5 2.66E-02 1.64E-03 52.5 2.51E-02 1.56E-03 53.5 2.39E-02 1.48E-03 54.5 2.18E-02 1.36E-03 55.5 1.96E-02 1.22E-03 56.5 1.60E-02 1.01E-03 57.5 1.28E-02 8.38E-04 58.5 1.09E-02 7.42E-04 59.5 9.01E-03 6.27E-04 60.5 7.43E-03 5.27E-04 61.5 8.10E-03 5.62E-04 62.5 4.70E-02 2.90E-03 63.5 2.10E-01 1.27E-02 64.5 3.61E-01 2.18E-02 65.5 2.77E-01 1.67E-02 66.5 8.20E-02 4.99E-03 67.5 8.90E-03 6.05E-04 68.5 1.07E-03 1.12E-04 69.5 4.01E-04 6.17E-05 70.5 4.97E-04 6.87E-05 71.5 1.32E-04 3.24E-05 72.5 ---------------------------------