^𝟗𝟗mTc Generator Development: Up-to-Date ^𝟗𝟗mTc Recovery Technologies for Increasing the Effectiveness of ^𝟗𝟗𝐌𝐨 Utilisation

Figure 7

Assessment on the ^99mTc-radioactivity (𝐴_Tc) and ^99mTc-concentration (𝐶_Tc) of the eluate eluted from the generators of 5-gram weight column-packing materials of variable Mo-loading capacity 𝐾 (low specific activity ⁹⁹Mo solutions used are produced in the nuclear reactors: (a) thermal neutron flux Φ=2.1013n⋅cm⁻²⋅sec⁻¹; (b) Φ=5.1013n⋅cm⁻²⋅sec⁻¹; (c) Φ=1014n⋅cm⁻²⋅sec⁻¹. The saline eluate volume is 10 mL).