Rhodium-103 and Indium-115 Inelastic Scattering Reactions for Fission Neutron Dosimetry.
ARMED FORCES RADIOBIOLOGY RESEARCH INST BETHESDA MD
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Neutron activation foil cross sections are calculated for shielded and unshielded configurations of the AFRRI TRIGA reactor. The neutron spectra used in the calculations ranged in average energy from 0.55 MeV to 3.4 MeV, and the total range of activation foil sensitivity factors cross section per unit tissue-kerma was or - 8.5 for 103Rh n,n 13mRh, or - 20 for 115In n,n 115mIn, and or - 75 for 32S n,p32P. These results support the use of 103 Rh and 115 In activation foils as tissue-kerma dosimeters at the AFRRI TRIGA reactor. Author
- Nuclear Physics and Elementary Particle Physics