Approximately one curie of 171Tm (T1/2 = 1.92a) has been produced and purified for the purpose of making a nuclear target for the first measurements of its neutron
capture cross section. Target preparation consisted of three key steps: (1) material production; (2) separation and purification;
and (3) electrodeposition onto a suitable backing material. Approximately 1.5 mg of the target material (at the time of separation)
was produced by irradiating ca. 250 mg of its stable enriched 170Er lanthanide neighbour with neutrons at the ILL reactor in France. This production method resulted in a “difficult-to-separate”
1:167 mixture of near-neighboring lanthanides, Tm and Er. Separation and purification was accomplished using high-performance
liquid chromatography (HPLC), with a proprietary cation-exchange column (Dionex, CS-3) and alpha-hydroxyisobutyric acid (α-HIB)
eluent. This technique yielded a final product of ∼95% purity with respect to Tm. A portion (20 μg) of the Tm was electrodeposited
onto thin Be foil and delivered to the Los Alamos Neutron Science Center (LANSCE) for preliminary analysis of its neutron
capture cross section using the Detector for Advanced Neutron Capture Experiments (DANCE). This paper discusses the major
hurdles associated with the separation and purification step, including scale-up issues related to the use of HPLC for material
separation and purification of the target material from α-HIB and 4-(2-pyridylazo)resorcinol (PAR) colorant.
Using 1 gram of 241Am from LANL stocks, the purification steps required to obtain a solution of 241Am from the original material are described. Part of the purified solution was submitted for purity analysis by mass spectrometry,
radiochemistry and trace metals analysis. The impurities were expected to be 239Pu and 237Np. A second fraction of this material was used for electroplating three samples onto titanium disks that were suitable for
insertion into an instrument package to be placed into the DANCE detector. The purification methods used, the electroplating
setup and the solutions to various problems that were encountered in making these targets are discussed. The analytical results
are discussed as well as the yields from the electrodeposition process. Comparison of these yields with those from similar
experiments utilizing 235U and 243Am are also discussed.
A simple method for the electrodeposition of elemental arsenic (As) on a metal backing from aqueous solutions has been developed.
The method was successfully applied to stable As (75As). Thin (2.5 mg cm−2) coherent, smooth layers of the metalloid on Ti foils (2.5 μm thickness) were obtained. Electrodeposits served as targets
for 75As(n,γ) 76As neutron capture experiments at Los Alamos Neutron Science Center (LANSCE). Respective 73As(n,γ) 74As experiments are planned for the near future, and 73As targets will be prepared in a similar fashion utilizing the new electrodeposition method. The preparation of an 73As (half-life 80.3 days) plating bath solution from proton irradiated germanium has been demonstrated. Germanium target irradiation
was performed at the Los Alamos Isotope Production Facility (IPF).
In this paper, we describe the separation chemistry and electrodepositions conducted for the preparation of 241Am, 243Am and 233U targets used for cross-section measurements at DANCE. Thick, adherent deposits were prepared using molecular plating from
isopropyl alcohol solutions. Improved yields and thicknesses were observed for 241Am electrodeposition after the material was purified using TRU resin from Eichrom. Similarly, 233U deposits were improved after purification with an anion exchange column in 9 M HBr followed by purification using UTEVA
resin from Eichrom.
This paper describes the preparation of samples for an experiment to measure the cross-section for 235U(n,n′)235mU in a fast fission spectrum of neutrons provided by a fast pulsed reactor/critical assembly. Samples of 235mU have been prepared for the calibration of the internal conversion electron detector that is used for the 235mU measurement. Two methods are described for the preparation of 235mU. The first method used a U-Pu chemical separation based on anion-exchange chromatography and the second method used an alpha
recoil collection method. Thin, uniform samples of 235mU+235U were prepared for the experiment using electrodeposition.
We investigated the immunological behavior of BTHX-1, before and after irradiation. SDS-PAGE showed that BTHX-1 irradiated
in the presence of NaNO3, had its structure preserved. Animals’ plasma immunized with native BTHX-1 had high IgG1 titers. The irradiated protein induced
high titers of IgG2b. When the toxin was irradiated with t-butanol, there was a slight decrease in the production of IgG2b.
Real-time PCR showed that both the IL-2 as for IL4 was more expression from the cells of the animals immunized with BTHX-1
irradiated. These results indicate that irradiation of proteins leads to significant structural modifications.
Perovskite type oxides have been intensively studied due to their interesting optical, electrical, and catalytic properties. Among perovskites the alkaline earth stannates stand out, being strontium stannates (SrSnO3) the most important material in ceramic technology among them due to their wide application as dielectric component. SrSnO3 has also been applied as stable capacitor and humidity sensor. In the present work, SrSnO3:Cu was synthesized by polymeric precursor method and heat treated at 700, 800, and 900 °C for 4 h. After that, the material was characterized by thermal analysis (TG/DTA), X-ray diffraction (XRD), infrared spectroscopy, and UV–vis spectroscopy. Results indicated three thermal decomposition steps and confirmed the presence of strontium carbonate and Cu2+ reduction to Cu+ at higher dopant amounts. XRD patterns indicated that the perovskite crystallization started at 700 °C with strontiatite (SrCO3) and cassiterite (SnO2) as intermediate phases, disappearing at higher temperatures. The amount of secondary phase was reduced with the increase in the Cu concentration.
In this work, the authors investigated the immunological behavior of bothropstoxin-I (BTHX-1), before and after irradiation
process, and also the influence of scavengers substances on protein alterations induced by free radical production. Structural
modifications were investigated by SDS-PAGE in reducing or non-reducing conditions. In vitro cytotoxicity assay was performed
to test average toxic activities of BTHX-I. BALB/c Isogenic mice were immunized with irradiated or non-irradiated (native)
forms of BTHX-I and antibody titers and isotypes were determined by ELISA method. Expression of murine cytokines was analyzed
by using expression data obtained by quantitative real-time PCR (qPCR) assays. The results indicate that irradiation of proteins
leads to significant structural modifications, and also changes the cytokines profile during immunization process, regarding
a suitable approach to new immunogenic production.
Alkaline earth stannates have recently become important materials in ceramic technology due to its application as humidity sensor. In this work, alkaline earth stannates doped with Fe3+ were synthesized by the polymeric precursor method, with calcination at 300 °C/7 h and between 400 and 1100 °C/4 h. The powder precursors were characterized by TG/DTA after partial elimination of carbon. Characterization after the second calcination step was done by X-ray diffraction, infrared spectroscopy, and UV–vis spectroscopy. Results confirmed the formation of the SrSnO3:Fe with orthorhombic perovskite structure, besides SrCO3 as secondary phase. Crystallization occurred at 600 °C, being much lower than the crystallization temperature of perovskites synthesized by solid state reaction. The analysis of TG curves indicated that the phase crystallization was preceded by two thermal decomposition steps. Carbonate elimination occurred at two different temperatures, around 800 °C and above 1000 °C.