报告从战略性分析、环境信息、竞争对手情报、资讯信息快报、市场行情与数据分析等几个方面对石油化工行业进行了分析评论。

报告从战略性分析、环境信息、竞争对手情报、资讯信息快报、市场行情与数据分析等几个方面对石油化工行业进行了分析评论。

报告从战略性分析、环境信息、竞争对手情报、资讯信息快报、市场行情与数据分析等几个方面对石油化工行业进行了分析评论。

报告从战略性分析、环境信息、竞争对手情报、资讯信息快报、市场行情与数据分析等几个方面对石油化工行业进行了分析评论。

报告从战略性分析、环境信息、竞争对手情报、资讯信息快报、市场行情与数据分析等几个方面对石油化工行业进行了分析评论。

LGFCS is developing an integrated planar (IP) SOFC technology for mega-watt scale power generation including the potential for use in highly efficient, economically competitive central generation power plant facilities fuel by coal synthesis gas. This Department of Energy Solid-State Energy Conversion Alliance (SECA) program is aimed at achieving further cell and stack technical advancements and assessing the readiness of the LGFCS SOFC stack technology to be scaled to larger-scale demonstrations in subsequent phases. LGFCS is currently in Phase 2 of the program with the Phase 1 test carrying over for completion during Phase 2.

The United States Department of Energy (DOE) Fissile Materials Disposition Program (FMDP) is pursuing disposal of surplus weapons-usable plutonium by reactor irradiation as the fissile constituent of MOX fuel. Lead test assemblies (LTAs) have been irradiated for approximately 36 months in Duke Energy's Catawba-1 nuclear power plant (NPP). Per the mixed oxide (MOX) fuel topical report, approved by the U.S. Nuclear Regulatory Commission (NRC), destructive post-irradiation examinations (PIEs) are to be performed on second cycle rods (irradiated to an average burnup of approximately 45 GWd/MTHM). The Radiochemical Analysis Group (RAG) at Oak Ridge National Laboratory (ORNL) is currently performing the detailed destructive post-irradiation examinations (PIE) on four of the mixed uranium and plutonium oxide fuel rods. The analytical process involves dissolution of designated fuel segments in a shielded hot cell for high precision quantification of select fission products and actinide isotopes employing isotope dilution mass spectrometry (IDMS) among other analyses. The hot cell dissolution protocol to include the collection and subsequent alkaline fusion digestion of the fuels acid resistant metallic particulates will be presented. Although the IDMS measurements of the fission products and actinide isotopes will not be completed by the time of the 51st INMM meeting, the setup and testing of the HPLC chromatographic separations in preparation for these measurements will be discussed.

The neutron radiography (NRAD) reactor is a 250 kW TRIGA (Training, Research, Isotopes, General Atomics) Mark IIa,b tank-type research reactor located in the basement, below the main hot cell, of the Hot Fuel Examination Facility (HFEF) at the Idaho National Laboratory (INL). It is equipped with two beam tubes with separate radiography stations for the performance of neutron radiography irradiation on small test components.c The NRAD reactor is currently under the direction of the Battelle Energy Alliance (BEA) and is operated and maintained by the INL and Hot Cell Services Division. It is primarily used for neutron radiography analysis of both irradiated and unirradiated fuels and materials. Typical applications for examining the internal features of fuel elements and assemblies include fuel pellet separations, fuel central-void formation, pellet cracking, evidence of fuel melting, and material integrity under normal and extreme conditions. Examination of the behavior of large test loops and assemblies can also be performed. Due to the intense gamma activity of most irradiated specimens, the HFEF uses an indirect radiography, where a beam of neutrons passes through a specimen, strikes a gamma-insensitive metal foil (typically indium or dysprosium, for epithermal or thermal neutron spectra, respectively), and activates the foil. The foil can then be placed against a sheet of x-ray photographic film. X-rays from the metal foil then render an image on the film, which is then developed. While this method takes longer than the conventional direct method, the results eliminate gamma interference and are more detailed. Neutron tomography capabilities are being developed, where radiographs are obtained from different rotational angles and digitized to reconstruct cross-sections of a specimen. Direct radiography, such as Polaroid or track-etch radiography, and in-tank irradiations and/or experiments with small in-core samples can also be performed in the NRAD reactor.

In an effort to understand and quantify the carbon and sulfur contents of a curium oxide production process performed in the hot cells at Oak Ridge National Laboratory's Radiochemical Engineering Development Center, a non-radioactive surrogate was used in a similar oxide formation process. Neodymium (Nd), which was chosen as a substitute for curium, was loaded onto a Dowex 50W-X8 resin by use of ion exchange column techniques and then treated under a variety of processing conditions. The surrogate product was analyzed for carbon and sulfur impurities, using inductively coupled plasma-mass spectrometry for sulfur assessment, a LECO combustion furnace/analyzer for carbon quantification, and X-ray diffraction for compound identification. The results indicate that the carbon and sulfur contents in the Nd oxide were similar to current estimations for curium oxide using the reference hot cell process. It was also seen that the major surrogate product of the hot cell process contained sulfur in a Nd oxysulfate (Nd2O2SO4) compound. Parametric analysis of the resin decomposition process revealed that increasing the temperature to 1400 degrees C yielded considerably better removal of carbon and sulfur.