In the first part of the paper, we had presented data on simulated conditions favorable for the separation of molybdenum from uranium under conditions existing in irradiated uranium. As mentioned, the aim of this study is the adoption of a method for the routine extr action of 99Mo (fission molybdenum) from the large bulk of uranium and host of radionuclides, additional parameters need to be evaluated to ar rive at an effective procedure. This paper deals with the further purification of 99Mo obtained using differential volatility of their chlorides to a quality meeting the requirements of pharmaceutical standards