[en] The neutron spectrum parameters of the miniature neutron source reactor (MNSR) in China Institute of Atomic Energy were measured by bare monitor method using Au, Zr and Fe as monitors. The measured values of a (a parameter accounting for the non-ideality of the 1/E epithermal neutron fluence rate distribution), f (thermal / epithermal neutron fluence rate) and f_F (thermal/fast neutron fluence rate) in the inner irradiation site are -0.007±0.003, 20.8±0.4, and 5.5±0.2, respectively. The value of φ_th measured by this method is agreed with that measured by 4πβ-γ method within 2%. Compared with SLOWPOKE, MNSR had higher values of a and f_F. The comparison with the previous measurements indicates that MNSR has a quite constant neutron spectrum. The fluence rate monitors are not needed when k₀-NAA is performed by using MNSR as neutron source, and with occasional check, the comparator data from one measurement may be used as a standard for subsequent analyses over a period of time. (authors)

[en] ⁶⁸Ge calibration source used for positron emission tomography (PET) attenuation correction was prepared by soluble gels method, mixed radioactive ⁶⁸Ge solutions and the commercial epoxy, eliminating water by heating, then encapsulated and sealed in stainless steel tube. Quality examination of ⁶⁸Ge calibration source was performed. The results show that the ⁶⁸Ge calibration source is sealed well, the surface is pollution-free, and the active distribute of the ⁶⁸Ge calibration source is evenly with an activity uniformity not more than ±5%. The various technical indexes of the source have achieved the level of similar products abroad. (authors)

[en] The adsorption and elution properties of platinum-coated copper (PCC) for radioactive iodine have been revealed and the effects of platinum on the performance of PCC were explored. In sulfuric acid medium containing sodium sulfite, the adsorption capacity, elution efficiency of PCC and the effect of platinum on PCC were determined by column chromatography. The results showed that the adsorption capacity of PCC prepared with 2 mL chloroplatinic acid or more for I^- was up to 0.224 mg/g with the adsorption efficiency of more than 99% while the elution efficiency was more than 95% by 15 mL 0.1 mol/L sodium hydroxide solution. (authors)

[en] It is deduced that the time interval of timely random signals obeys exponential Distribution. Table looking-up method is used to accelerate the generation of exponentially distributed random numbers. With the single chip computer 8031, a frequency programmable pulse generator is developed. It works in either periodic or random mode. The frequency ranges are: 100 Hz-9.999 MHz for periodic mode and 2 Hz-10 kHz for random mode

[en] The distribution coefficient of ⁹⁹Mo is determinated in NH₄OH, NaOH, HNO₃ solution at different temperature. The effect of temperature and alkali concentration is studied. The amount of ⁹⁹Mo eluted by NaOH and HNO₃ elution is determinated. The results show that ⁹⁹Mo does not break-through the column as the loading solution passes through the 717 column; and more than 90.6% of ⁹⁹Mo can be eluted by 200 mL 3 mol/L HNO₃, and 99.8% by 0.5 mol/L NaOH-0.5 mol/L NaNO₃ elution. (authors)

[en] For preparing the absorbent of ⁶⁸Ge-⁶⁸Ga generator, SnO₂ was prepared with metal tin and hot HNO₃. The process and characters of SnO₂ were studied. The features of adsorption and elution of ⁶⁸Ge-⁶⁸Ga generator with SnO₂ as the absorbent were also studied. The results indicate that SnO₂ after heated at 600 ℃ is suitable as absorbent for ⁶⁸Ge-⁶⁸Ga generator, and it has good selective adsorption to ⁶⁸Ge. The ⁶⁸Ga yield is 60%-80% with 8 mL of 1 mol/L HCl as the eluent, and the ⁶⁸Ge breakthrough is most a magnitude of 10^-3%. (authors)

[en] To ensure the application and development of nuclear medicine, the supply of fission ⁹⁹Mo is very important. It is simply introduced that the project of producing fission ⁹⁹Mo using a solution reactor and its development prospect, which includes the solution reactor, extraction and purification of ⁹⁹Mo. (authors)

[en] This paper describes a simulation software developed to provide baseline for the design of BESIII trigger system. This program can be used to produce hit patterns for Track Segment Finding (TSF) and Track Finding (TF). Being fed with detector response data, it checks for the calculates number of a long and short tracks in Drift Chamber (MDC), calculates number of hits and looks for back to back hits in TOF, and also calculates the isolated clusters from continuous trigger cells formed by of 16 crystals and total energy and energy balance in Electromagnetic Calorimeter (EMC). Global Trigger (GLT) define trigger table of types with trigger conditions, and if a predefined type is satisfied, a trigger output of L1 will be produced for statistics. This software is proved working well in the preliminary design of BESIII trigger system, and will be improved further. (authors)

[en] Twenty one autopsy liver samples were collected from normal adult men died accidentally in 4 areas of Hebei, Shanxi, Jiangxi and Sichuan in China with different dietary types, and the contents of 8 trace elements essential to human, including Co, Cr, Cu, Fe, Mn, Mo, Se and Zn, were determined with neutron activation analysis. The experimental results showed that the contents for each of the 8 elements were significantly different for different individuals, however all of them in the same sequence of Fe>Zn>Cu>Mn>Mo> Se>Cr>Co. The regional differences in average values of some elements were indicated, for example, the average values of Co content in Shanxi, Cr content in Sichuan, and Fe content in Hebei were 1.7-2.0, 2.5-5.2, and 1.5-2.4 times of those in other areas, respectively. The Cr content were significantly higher than the newly estimated value of ICRP reference man, and Fe, Cu and Mo content were also slightly higher. Three kinds of certified reference materials were analyzed for quality control, and the analytical results of the 8 elements were in good agreement with certified values within uncertainty limits. (authors)

[en] Germanium 68 is mainly used for preparation of the ⁶⁸Ge-⁶⁸Ga generator and the calibration of positron emission computed tomography. The low melting point of the target material in the production reaction ⁶⁹Ga (p, 2n) ⁶⁸Ge has limited the availability of Ge-68. In order to use the existing industrial cyclotron hardware to produce Germanium 68, the method of electrodepositing gallium-nickel alloy was set up in this study. Acidic requirements were met through the preparation of the gallium-nickel alloy targets and by optimizing the plating bath composition and electrodepositing conditions, finally confirmed by adjustment of the electro-deposition process, and preparation of the gallium-nickel alloy targets with a gallium content of 75 %. After three time irradiation tests, the process was certified to produce targets of Germanium 68. This process is user-friendly, the preparation of the targets is of stable quality, and it can be applied to the cyclotron production of Germanium 68. (authors)