FAST-NEUTRON AND GAMMA SPECTRA FOR BSR

Shielding calculations for back-of-the-envelope were made from gamma and fast-neutron dose rate and thermalneutron flux studies at the centerline of the Bulk Shielding Reactor. Complete calculated values for gamma and fastneutron spectra are presented which should increase the usefulness of BSR centerline data. The validity of these calculations are shown by their agreement with measured data. The gamma and fast-neutron spectra are especially useful in determining the penetration through or heating of materials placed in water near a BSR-type reactor. For gamma rays, the use of the continuous energy spectrum rather than of an average or effective gamma energy gives results of considerably greater accuracy. (B.O.G.)