[en] Automation of routine and serial assays is a common practice of modern analytical laboratory, while it is virtually nonexistent in the field of radiochemistry. Flow injection analysis (FIA) is a general solution handling methodology that has been extensively used for automation of routine assays in many areas of analytical chemistry. Reproducible automated solution handling and on-line separation capabilities are among several distinctive features that make FI a very promising, yet under utilized tool for automation in analytical radiochemistry. The potential of the technique is demonstrated through the development of an automated ⁹⁰Sr analyzer and its application in the analysis of tank waste samples from the Hanford site. Sequential injection (SI), the latest generation of FIA, is used to rapidly separate ⁹⁰Sr from interfering radionuclides and deliver separated Sr zone to a flow-through liquid scintillation detector. The separation is performed on a mini column containing Sr-specific sorbent extraction material, which selectively retains Sr under acidic conditions. The ⁹⁰Sr is eluted with water, mixed with scintillation cocktail, and sent through the flow cell of a flow through counter, where ⁹⁰Sr radioactivity is detected as a transient signal. Both peak area and peak height can be used for quantification of sample radioactivity. Alternatively, stopped flow detection can be performed to improve detection precision for low activity samples. The authors current research activities are focused on expansion of radiochemical applications of FIA methodology, with an ultimate goal of creating a set of automated methods that will cover the basic needs of radiochemical analysis at the Hanford site. The results of preliminary experiments indicate that FIA is a highly suitable technique for the automation of chemically more challenging separations, such as separation of actinide elements

[en] The authors performed radiochemical separation either from metals (metals as targets or analyzed matrices) or using metals (metal collectors). Therefore, the theoretical part of this paper will be devoted to the study of chemical interactions of metals in open-quotes melted metal-trace elementclose quotes systems at high temperatures; the melted metal was either a collector or a matrix element. These studies, important for the practical use of radiochemical analysis, were conducted using tracer technique and autoradiography. The experiments were performed with master alloys labeled with radionuclides. The authors adopted the technique described earlier. The labeled master alloys were also directly used in the development of procedures for separating and concentrating radionuclides

[en] Automated laboratory radionuclide analysis systems greatly simplify the human component of processing and can offer greater reproducibility while saving time and effort. Automated field radionuclide analysis systems can provide more timely data reporting than previously available while reducing the costs associated with shipping field samples to a laboratory for analysis. This chapter describes general aspects of automating these systems and presents a number of examples

[en] New Brunswick Laboratory (NBL) serves as the U.S. Government's certifying authority for nuclear reference materials and measurement calibration standards. In this role, NBL provides nuclear reference materials certified for chemical and/or isotopic compositions traceable to a nationally accepted, internationally compatible reference base. Emphasis is now changing as to the types of traceable nuclear reference materials needed as operations change within the Department of Energy complex and at nuclear facilities around the world. New challenges include: environmental and waste minimization issues, facilities and materials transitioning from processing to storage modes with corresponding changes in the types of measurements being performed, emphasis on requirements for characterization of waste materials, and difficulties in transporting nuclear materials and international factors, including IAEA influences. During these changing times, it is critical that traceable reference materials be provided for calibration or validation of the performance of measurement systems. This paper will describe actions taken and planned to meet the changing reference material needs of the global nuclear community

No abstract available

[en] The determination of speciation of radioactive elements in natural-matrix standard reference soils and sediments was addressed at a workshop convened June 13-15, 1995 at the National Institute of Standards and Technology (NIST). Workshop participants agreed that the additional information provided by sequential extractions was very useful but further refinements of existing protocols are required before certification is possible

[en] During the operation and the decommissioning of a nuclear site the operator must assure the protection of the workers and the environment. It must furthermore identify and classify the various wastes, while optimizing the costs. At all stages of the decommissioning radiological measurements are performed to determine the initial situation, to monitor the demolition and cleanup, and to verify the final situation. The current operations for the characterization of radiological soils of CEA nuclear facilities, lead to a large increase of radiochemical analysis. To manage this high throughput of samples in a timely manner, the CEA has developed a new mobile laboratory for the clean-up of its soils, called SMaRT (Shelter for Monitoring and nuclear chemistry). This laboratory is dedicated to the preparation and the radiochemical analysis (alpha, beta, and gamma) of potentially contaminated samples. SMART is transportable via road and airline. Radiological analysis can then be performed without the disadvantages of radioactive material transport. This paper describes how this solution allows a fast response and control of costs, with a high analytical capacity. 2 dismantling projects in which SMART was used, are presented. The first one deals with a building whose soil underneath was contaminated with Ra²²⁶ and the second one deals with the dismantling of a hot cell at the CEA center in Fontenay-aux-Roses. Radiochemical Analyses were performed on site with SMART in order to detect natural or artificial contamination

[en] ((R)-1-(2-chlorophenyl)-N-1-[[¹¹C]methyl-N-(1-propyl)-3-isoquinoline carboxamide ((R)-PK11195) is a specific ligand for the peripheral type benzodiazepine receptor and a marker of activated microglia, used to measure inflammation in neurologic disorders. We report here that a direct and simple radiosynthesis of [[¹¹C](R)-PK11195 in mild condition using NaH suspension in DMF and one-step loop method. (R)-NDesmethyl- PK11195 (1 mg) in DMSO (0.1 mL) and NaH suspension in DMF (0.1 mL) were injected into a semi-prep HPLC loop. [¹¹C]methyl iodide was passed through HPLC loop at room temperature. Purification was performed using semi-preparative HPLC. Aliquots eluted at 11.3 min were collected and analyzed by analytical HPLC and mass spectrometer. The labeling efficiency of [[¹¹C](R)-PK11195 was 71.8±8.5%. The specific activity was 11.8±6.4 GBq/μmol and radiochemical purity was higher than 99.2%. The mass spectrum of the product eluted at 11.3 min showed m/z peaks at 353.1 (M+1), indicating the mass and structure of (R)-PK11195. By the one-step loop method with the [[¹¹C]CH3I automated synthesis module, [[¹¹C](R)-PK11195 could be easily prepared in high radiochemical yield using NaH suspension in DMF

[en] A rapid method for sequential separation of uranium, americium and plutonium from urine samples by extraction chromatography was developed. In this method, U-TEVA and TRU-resin columns were used for the separation of the radionuclides. By this method U, Am and Pu could be separated from urine samples with high recoveries and no interference from the sample matrix was observed. Radiochemical recoveries observed in the study were in the range 63.8-100%. Column separation of the radionuclides could be completed within 3 h compared to the present practice of separation of these radionuclides by ion exchange method which requires minimum 3 days to complete the separation. (author)

[en] Characterization activities, including radioisotope analyses, are performed in support of various U.S. Department of Energy environmental restoration and waste management (DOE/EM) programs. Radiochemical characterization requires the application of appropriate analytical methods. Matrices encountered in support of EM range from low-radioactivity-level aqueous matrices to high-radioactivity-level tank waste. Radioanalytical techniques are often developed by each laboratory to meet specific program needs, reduce sample analysis time, and reduce waste streams. These radioanalytical procedures are solicited for inclusion in Ref. 1, a consensus standard methods document. Other current standard sources of radioanalytical methods e.g., the U.S. Environmental Protection Agency, the American Society of Testing and Materials, are not always applicable to the evaluation of DOE/EM samples. Their applicability is generally limited to specific matrices (usually water), low-level radioactive samples, and a limited number of analytes. Reference 1 complements these standard methods by addressing the complexities, such as high activity, of commonly encountered EM characterization needs. Reference 1 is updated annually and is available either by mail or through Internet