A great improvement of the equipment for the fluorescence measurement of the fluoroglass dosimeter has been performed for a medical internal dose measurement. This apparatus and newly developed fluoroglass FD-6 have made it possible for the I mmq.5×6 mm rod type fluoroglass element to measure the absorbed dose as low as 3 mrads. This was confirmed by the experiment of water phantom using 500 ml beaker. As one of the preliminary tests for the direct measurement of the internal dose of the human organs when the radiopharmaceutical is injected a series of experiments using 13 rats have been carried out. One or two glass rods were burned in their livers. Immediately or about 40 days after the burial of the glass elements an amount of 3-50μCi colloidal gold (198Au) was injected in their veins with disposable injectors. Several glass rods were covered with 0.25 mm thick gold sheaths during the exposure to see the contributions of β and γ rays from198Au separately. The rods were taken out about 3 days after the injection of198Au. The radiophotoluminescence was measured with the equipment after several necessary processes for cleaning up the glass rods. The results were compared with the calculated values based on the MIRD (Medical Internal Radiation Dose) Committee method. In the experiment using 500 ml water phantom the experimental absorbed doses and calculated ones show a good linear correlation, although the latter were 1.4+0-0.2times larger than the former. The ratio of the contribution of β rays to the total absorbed dose was 0.81±0.004 in the experiment and 0.84+0-0.08in the MIRD calculation, showing good agreement with each other. In the experiment using 13 rats, however, the calculated absorbed dose values are 2-60 times as large as the experimental ones. The ratios of the contributions to the absorbed doses from β rays to those from γ rays do not show such large discrepancies between experiment and calculation. Discussions on this problem are given.
A nuclear battery is made which is composed of five silicon p-n junctions, five147Pm beta sources, and a SUS 27 container. Maximum output power and overall efficiency of energy conversion are obtained as 1.2μW and 0.3%, respectively. The effective source activity is 0.1-0.2 Ci for each147Pm source. The small output power is caused by the weak147Pm beta sources. Electrical characteristics of a p-n junction element are measured by using monoenergetic electron beam of which energy was 50, 75, and 100 ke V. The result shows that the maximum output power, P0, and the input power of the electron beam, Pe, has a relation as P0=Pex, where x is equal to 1.2-1.3. Optimum junction depth for beta rays from147Pm to obtain maximum output power is determined as 2 to 4 microns from the surface of the junction. Reduction of the maximum output power of the p-n junction element caused by radiation damage has been measured during 6200 hours. The experimental result shows that the decrease of the maximum output power is only 5% during 6200 hours.