A theoretical and experimental investigation of the source-sample-detector geometry for an annular type radioisotope excited XRF spectrometer

In this study, the dependence of the characteristic X-ray intensities on the counting geometry has been investigated for a radioisotope excited XRF spectrometer. The collimation factor for the source-sample-detector geometry, which was prepared for an annular type¹⁰⁹Cd radioisotope source, has been determined both theoretically and experimentally. The discrepancy between the theoretical and experimental results is discussed in terms of possible sources of errors.     

A substoichiometric radioisotope dilution study using210Pb

A radioisotope dilution procedure has been developed which permits the determination of lead over a concentration range of 0.1 to 10 ppm. Samples in an ammoniacal cyanide/sulfite medium are labelled with²¹⁰Pb, followed by addition of substoichiometric amount of dithizone. The Pb/HDz/₂ formed is extracted into CH₂Cl₂, and aliquot portions are taken for liquid scintillation counting. Count rate is plotted vs. the reciprocal of the lead concentration, yielding a straight line. An average error of ±3.5% is estimated, based on a linear least squares fit.     

An integrated control system for radioisotope facilities

The authors developed an integrated system for managing the safe use of radioisotope laboratory facilities, users' access to controlled areas, and the control of air-conditioners. This system consisted of a personal computer, an access controller, an eye retinal verifier, magnetic card readers, hand foot cloth monitors, video tape recorders and a fire alarm system. The access controller was set as the central unit to operate the whole system including 13 gates and air-conditioners. Under this program, only registered persons were permitted to enter the laboratories; the exact records on access were easily obtained; and electricity and fuel expenses were largely reduced. We expect that the system would facilitate the safe use of radioisotopes and the utilization of laboratory facilities.     

Improved synchronized accumulating radioisotope detector for gas chromatography

A synchronized accumulating radioisotope detector for radio gas chromatography was developed. It comprised seven gas-flow proportional counters each with an inner volume of 10 ml. Every counter tube was connected by a mutual anti-coincidence circuit to reduce the background. The transit time of gas particles in one counter tube could be set to an optimal value between 1 and 4 s by regulating the flow-rate of the counting gas, according to analytical requirements. The improved detector maintained high chromatographic resolution, which suggested the applicability of the apparatus to capillary gas chromatography.     

Radon concentration of outdoor air: measured by an ionization chamber for radioisotope monitoring system at radioisotope institute

Gas-flow ionization chambers for radioisotope (RI) monitoring systems at RI institutes throughout Japan are commonly used to measure RIs which leak from the RI institutes. Before the Japan’s 2011 Tohoku earthquake [11 March 2011, moment magnitude (M _w) 9.0], ionization current data measured with a gas-flow ionization chamber at the RI institute of Fukushima Medical University were found to change. The question we must raise is whether the variation ionization current can be considered to the variation of outdoor radon concentration. The conversion factors (from ionization current to radon concentration in air) of the gas-flow ionization chamber can be obtained by measuring four levels of radon concentration (outdoor air, indoor air, high level and radon-free gas) with an AlphaGUARD monitor and the chamber itself. The two gas-flow ionization chambers consist of the air intake and terminal exhaust duct of the RI institute. It was found that the radon concentration in the exhaust air was the same as that in the air intake. This study provided evidence that variations of outdoor radon concentration could be determined using gas-flow ionization chambers for RI monitoring systems.     

A new approach to absorption effects using radioisotope X-ray spectrometry

The quantitative interpretation of X-ray fluorescence /XRF/ data is often difficult because of matrix effects. The intensity of fluorescence measurement for a given element is not only dependent on the concentration of the element, but also on the mass absorption coefficients of the sample for both excitation and fluorescent radiation. In this paper, a new approach for the determination of absorption and transmission correction factors is described.     

Use of radioisotope induced X-ray fluorescence for environmental studies

The rapid assay of the trace multi-element content of environmental samples (lake sediment) is described. The method utilized X-ray fluorescence induced by a¹⁰⁹Cd radioisotopic source with energy dispersive quantitative detection of the characteristic X-rays of nine elements, ranging from Ti to Zr using Si(Li) semiconductor detector. The method precludes pre-digestion or chemical treatment of the samples, and compairs favorably with the results of atomic absorption assay methods.     

Computerized control system for administration of the radioisotope use

An on-line computer system for administration of the radioisotope use has been developed. This system consists of a multi-job type host computer and two sets of personal computers with identification card-readers. The personal computers are employed as terminal devices for radioisotope users. By the use of an identification card, entrance and leaving times are recorded automatically. Furthermore, an easy operation of the personal computer permits users to access to the information of their registered radioisotopes, such as nuclides, chemical forms, updated activities, storage locations, and history of usage. A recording sheet on which those data are printed is provided from the personal computer. After the use of radioisotopes, users can record their data on the recording sheets. These records are used as the input data to this system to update the data of the used radioisotopes. Owing to the concise format of the recording sheet and various sorting programs developed in present work, this system enables us to grasp the exact flow of the radioisotopes from purchase to disposal. Out-put data from high-speed kanji printer can provide many important books which are legally requested to be kept for administration of the radioisotope use.     

New system for a pulsed slow-positron beam using a radioisotope

To analyze the surface of polymers using positron-annihilation lifetime spectroscopy (PALS), a pulsed slow-positron beam system having both a high pulsing efficiency and a good time resolution is now under development. The time resolution, which is defined by the full width at half maximum (FWHM), and the pulsing efficiency of this system were achieved to be 0.54 ns and 50%, respectively. The lifetime of ortho-positronium (o-Ps) in low-density polyethylene (LDPE), obtained by PALS using our new pulsing system, agreed with that obtained by a conventional PALS.     

Facile preparation of 177Lu-microspheres for hepatocellular carcinoma radioisotope therapy

As one of the most common cancers in the world, hepatocellular carcinoma (HCC) has become a major threat to human health. Radioembolization is a first-line option for the treatment of HCC, especially when other conventional treatments fail or there exist some relative contraindications. Herein, we developed a facile and efficient method for preparing ¹⁷⁷Lu-microspheres potentially useful for precise radioembolization therapy of HCC. The radiolabeling efficiency of ¹⁷⁷Lu-microspheres was as high as 96.8% ± 0.5%, and the radiolabeling process did not alter the morphology of the mother microspheres. The SPECT/CT studies enabled by the unique emissions of ¹⁷⁷Lu suggested that almost no ¹⁷⁷Lu ion loaded by the microspheres was released over more than 32 d in vivo, which led to remarkable inhibition effect on the growth of HepG2 tumors subcutaneously transplanted in mice. The current approach may thus offer promising ¹⁷⁷Lu-microspheres for clinical radioembolization of HCC.     

A simple radioisotope X-ray fluorescence method for provenance studies of archaeological ceramics employing principal component analysis

A simple radioisotope X-ray fluorescence method of 1000 s irradiation of the samples by a ¹⁰⁹Cd source combined with principal component analysis is described for determining the relative mass fractions of trace elements in majolica ceramics for provenance classification. Six provenances from Europe using 29 samples as standards and 12 unknown samples were investigated and characterized using selected trace elements as the variables. The unknown samples were previously assigned, but not definitively, by stylistic analysis and/or thermoluminescence measurements to the provenances of Teruel (Spain) and Holland. Because of a moderate fluorescence time, only the four net peak intensities of Pb, Rb, Sr and Zr could be used as variables. We have also studied the effect of not including the Pb variable, since the clay matrixes could have been contaminated in the glazing process or when the Pb-Sn enamel was removed. It is shown in both cases that the results were more consistent with the stylistic analysis and thermoluminescence measurements when the Pb concentration variable was not considered. A comparison of principal component analysis employing the three elements was similar to plotting of the relative mass fractions on a triangle graph.     

Alternative chromatographic processes for no-carrier added 177Lu radioisotope separation

HPLC technique combined with the simple conventional column solid phase extraction (SPE) chromatography using di-(2-ethylhexyl)orthophosphoric acid (HDEHP) impregnated OASIS-HLB sorbent based SPE resins (OASIS-HDEHP) was developed for the separation of no-carrier added (n.c.a) ¹⁷⁷Lu from the bulk quantity of ytterbium target. This combination strategy was based on combining the advantages of the better resolution of HPLC separation of n.c.a ¹⁷⁷Lu from the few milligram level Yb target with the high capacity of the OASISHDEHP column for the separation of ¹⁷⁷Lu from the bulk Yb target. The production batches of several hundred mCi activity of n.c.a ¹⁷⁷Lu radioisotope separated from 50 mg Yb target activated in a nuclear reactor of medium neutron flux (Φ=5·10¹³ n·cm^?2·s^?1) were successfully performed using this combined separation technique. With the target irradiation in a reactor of higher thermal neutron flux or with the parallel run of several separation units, several Ci-s of n.c.a ¹⁷⁷Lu can be profitably produced on a commercial production basis.     

Tests for liquid chromatographs

Summary The paper describes tests for liquid chromatographs to assess the autosampler and pump flow rate precision; suitability of the instrument for normal phase chromatography; UV detector performance; and external band broadening characteristics. Tests for mixing and proportioning characteristics of solvent pumps and performance of diode array detectors are also considered. These tests are designed to evaluate the performance of both newly released liquid chromatography equipment and equipment already in operation. Data from evaluations carried out by instrument manufacturer’s and suppliers is reported and discussed. This data offers specifications to a common format for initial selection of instruments prior to purchase.     

A rapid transportation facility for irradiation with thermal and fast neutrons

A rapid vertical transportation system for irradiation with thermal and fast neutrons is devised and partly constructed for inserting samples into the central thimble of our TRIGA MARK II reactor. Fast neutrons will be produced by a⁶LiD-converter, so that the energy distribution of neutrons is hardened by absorption of thermal and by the production of 14 MeV neutrons. In pulse irradiation, the 14 MeV-neutron flux is expected to be in the order of 10¹²/s. The transportation time is to be below 30ms to enable determination of short-lived nuclides down to 15ms. Helium will be used as propelling gas.     

An example for activation analysis by low-level radioisotope neutron soruce

A 1 Ci Pu−Be neutron source and a low-background beta-spectrometer were used to activate and to measure the beta-rays of low-activity. The main characteristics of this method can be given as follow: The determined S/N ratio increases because the background beta-rays are lower than the gamma-rays. For example, the sensitivity obtained for quantitative analysis of sulphur in silicon is 100 ppm in case of S/N=1.0.     

Direct assay techniques for comprehensive radionuclide quantification of radwaste packages

Battelle, Pacific Northwest Laboratories has recently developed, tested and field-demonstrated a technology for the direct assay of transuranic radionuclides (TRU), fission products, and activation products in a variety of radwaste packages generated at commercial nuclear power plants. This technology involves non-destructive passive neutron counting for determination of nanocurie/gram quantities of the TRU radionuclides. Direct gamma spectrometry combined with thermoluminescent dosimetry (TLD) and correlation analysis is also utilized to determine the concentrations of the fission and activation products present in the radwaste packages. Employing counting times of 10 to 20 minutes, a complete analysis of all radionuclides specified for assay by the U.S. Nuclear Regulatory Commission (in 10CFR61) prior to shallow-land disposal of commercial radwastes can be measured at concentrations at least tenfold below the least restrictive Class A waste catagory.