Prolactin (PRL) concentrations in sera and tumors of patients with various pituitary tumors were measured by both immunoradiometric assay (IRMA) and radioimmunoassay (RIA) . PRL concentrations in sera and tumor tissues measured by IRMA were well correlated with those measured by RIA. PRL concentrations in sera reflected those of tumors removed. This IRMA is a simple and useful method for PRL determination in serum and tissue.
The efficiencies of contamination source, defined in ISO Report 7506-1, were experimentally determined for such materials as flooring, polyethylene, smear-tested filter paper and stainless steel plate. 5 nuclides of147Pm, 60Co, 137Cs, 204Tl and90Sr-Y were used to study β-ray energy dependence of the efficiency, and241Am as α-ray emitter. The charge-up effect in the measurement by a window-less 2π-proportional counter was evaluated to obtain reliable surface emission rate. The measured efficiencies for non-permeable materials, except for two cases, are more than 0.5 even for147Pm. The ISO recommendations were shown to be conservative enough on the basis of present results.
“Ready Cap”, a small plastic container coated with solid scintillator has recently been introduced (Beckman Instruments, Inc.) . Pulse height spectra and counting efficiencies obtained with a liquid scintillator and Ready Cap using a liquid scintillation counter were compared for 15 different radionuclides. For radionuclides emitting low-energy β-rays or characteristic X-rays, the spectra for Ready Cap shifted toward the higher energy side compared with the spectra for the liquid scintillator. This tendency was reversed for the nuclides emitting higher-energy β-radiations (36Cl and32P) . Generally, counting efficiencies both in Ready Cap and in liquid scintillator increased with increase in the energy of β-or X-rays. For some nuclides, Ready Cap gave higher counting efficiencies and for others it gave lower values than in the liquid scintillator. However, the differences were not large within each nuclide. The use of Ready Cap is recommended for measurements of radionuclides when liquid scintillation cocktails have no means of waste disposal under the present Japanese radioisotope regulation.