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Sample records for aktivnostej nuklidov pu

  1. Gamma Attribute Measurements - Pu300, Pu600, Pu900

    International Nuclear Information System (INIS)

    Gamma rays are ideal probes for the determination of information about the special nuclear material that is in the transparency regime. Gamma rays are good probes because they interact relatively weakly with the containers that surround the SNM under investigation. In addition, gamma rays carry a great deal of information about the material under investigation. We have leveraged these two characteristics to develop three technologies that have proven useful for the measurements of various attributes of plutonium. These technologies are Pu-300, Pu-600 and Pu-900. These technologies obtain the age, isotopics and presence/absence of oxide of a plutonium sample, respectively. Pu-300 obtains the time since the last 241Am separation for a sample of plutonium. This is accomplished by looking at the 241Am/241pu ratio in the energy region from 330-350 keV, hence the name Pu-300. Pu-600 determines the isotopics of the plutonium sample under consideration. More specifically, it determines the 240Pu/239Pu ratio to determine if the plutonium sample is of weapons quality or not. This analysis is carded out in the energy region from 630-670 keV. Pu-900 determines the absence of PuO2 by searching for a peak at 870.7 keV. If this peak is absent then there is no oxide in the sample. This peak arises from the de-excitation of the first excited state of 17O. The assumption being made is that this state is populated by means of the 17O(α,α') reaction. The first excited state of 17O could also be populated by means of the 14N(α,p) reaction, which might indicate that this is not a good signature for the absence of PuO2, however in the samples we have measured this peak is visible in oxide samples and is absent in other samples. In this paper we will discuss the physics details of these technologies and also present results of various measurements

  2. Pu-239 and Pu-240 inventories and Pu-240/ Pu-239 atom ratios in the water column off Sanriku, Japan.

    Science.gov (United States)

    Yamada, Masatoshi; Zheng, Jian; Aono, Tatsuo

    2013-04-01

    A magnitude 9.0 earthquake and subsequent tsunami occurred in the Pacific Ocean off northern Honshu, Japan, on 11 March 2011 which caused severe damage to the Fukushima Dai-ichi Nuclear Power Plant. This accident has resulted in a substantial release of radioactive materials to the atmosphere and ocean, and has caused extensive contamination of the environment. However, no information is available on the amounts of radionuclides such as Pu isotopes released into the ocean at this time. Investigating the background baseline concentration and atom ratio of Pu isotopes in seawater is important for assessment of the possible contamination in the marine environment. Pu-239 (half-life: 24,100 years), Pu-240 (half-life: 6,560 years) and Pu-241 (half-life: 14.325 years) mainly have been released into the environment as the result of atmospheric nuclear weapons testing. The atom ratio of Pu-240/Pu-239 is a powerful fingerprint to identify the sources of Pu in the ocean. The Pu-239 and Pu-240 inventories and Pu-240/Pu-239 atom ratios in seawater samples collected in the western North Pacific off Sanriku before the accident at Fukushima Dai-ichi Nuclear Power Plant will provide useful background baseline data for understanding the process controlling Pu transport and for distinguishing additional Pu sources. Seawater samples were collected with acoustically triggered quadruple PVC sampling bottles during the KH-98-3 cruise of the R/V Hakuho-Maru. The Pu-240/Pu-239 atom ratios were measured with a double-focusing SF-ICP-MS, which was equipped with a guard electrode to eliminate secondary discharge in the plasma and to enhance overall sensitivity. The Pu-239 and Pu-240 concentrations were 2.07 and 1.67 mBq/m3 in the surface water, respectively, and increased with depth; a subsurface maximum was identified at 750 m depth, and the concentrations decreased with depth, then increased at the bottom layer. The total Pu-239+240 inventory in the entire water column (depth interval 0

  3. Comparison of evaluations for 235U, 239Pu, 240Pu, 241Pu and 242Pu with integral measurements

    International Nuclear Information System (INIS)

    The evaluations for 235U, 239Pu, 240Pu, 241Pu and 242Pu are considered. Intercomparison is made of the neutron cross section data from INDL/A, ENDL-84, ENDF/B-5 and ENDF/B-6 (where applicable). Integral measurements of the spectrum averaged cross sections are compared to the values derived from evaluated data libraries. (author). 40 refs, 49 figs, 11 tabs

  4. Phase investigations of the Pu-Pt, Pu-Rh, and Pu-Pt-Rh systems

    International Nuclear Information System (INIS)

    Phase and crystal structure studies performed on the Pu-Pt, Pu-Rh, and Pu-Pt-Rh systems are described. The techniques employed included metallography, X-ray diffraction, and an electron microprobe. Results of these studies are correlated with previous work to obtain phase diagrams for these three systems. Previously unreported PuPtsub(3-kappa) and PuPtsub(3-kappa) polymorphs and a new PuPt4 phase were identified. Eutectic points in the Pu-Pt and Pu-Rh systems were determined at 89.9 at%Pt and 84.5 at%Rh, respectively. No low melting eutectic alloys or ternary compounds were observed in the Pu-Pt-Rh system. Crystal structures determined by X-ray diffraction measurements were as follows: PuPt5 (hexagonal, P 6/mmm, CaCu5-type); PuPt4 (orthorhombic, Cmmm); and PuPtsub(3-kappa) (BC tetragonal, DOsub(e), PNi3-type). (Auth.)

  5. Designing Pu600 for Authentication

    Energy Technology Data Exchange (ETDEWEB)

    White, G

    2008-07-10

    Many recent Non-proliferation and Arms Control software projects include an authentication component. Demonstrating assurance that software and hardware performs as expected without hidden 'back-doors' is crucial to a project's success. In this context, 'authentication' is defined as determining that the system performs only its intended purpose and performs that purpose correctly and reliably over many years. Pu600 is a mature software solution for determining the presence of Pu and the ratio of Pu240 to Pu239 by analyzing the gamma ray spectra in the 600 KeV region. The project's goals are to explore hardware and software technologies which can by applied to Pu600 which ease the authentication of a complete, end-to-end solution. We will discuss alternatives and give the current status of our work.

  6. Designing Pu600 for Authentication

    International Nuclear Information System (INIS)

    Many recent Non-proliferation and Arms Control software projects include an authentication component. Demonstrating assurance that software and hardware performs as expected without hidden 'back-doors' is crucial to a project's success. In this context, 'authentication' is defined as determining that the system performs only its intended purpose and performs that purpose correctly and reliably over many years. Pu600 is a mature software solution for determining the presence of Pu and the ratio of Pu240 to Pu239 by analyzing the gamma ray spectra in the 600 KeV region. The project's goals are to explore hardware and software technologies which can by applied to Pu600 which ease the authentication of a complete, end-to-end solution. We will discuss alternatives and give the current status of our work

  7. Standardization of 238Pu

    International Nuclear Information System (INIS)

    An ion-implanted Si-detector and NaI(Tl) scintillation detector were employed for the standardization of 238Pu using the coincidence method. The low-energy discrimination method was applied to the degraded alpha spectrum for the efficiency variation, and an energy gate was provided for the X-rays between 7 and 35 keV. Two signals were compared to check their coincidence and counted if they were coincident. Three counts of alphas, X-rays and their coincidences were corrected for their dead times and/or the accidental coincidences between them before being extrapolated to the zero discrimination level of alphas. The resultant specific radioactivity is compared with that of the liquid scintillation counting method, and its evaluated uncertainty is given item by item. The impurity checks of the original solution source were described in brief too

  8. Plutonium isotopes 238Pu, 239+240Pu, 241Pu and 240Pu/239Pu atomic ratios in the southern Baltic Sea ecosystem

    Directory of Open Access Journals (Sweden)

    Dagmara I. Strumińska-Parulska

    2010-09-01

    Full Text Available The paper summarizes the results of plutonium findings in atmospheric fallout samples and marine samples from the southern Baltic Sea during our research in 1986-2007. The activities of 238Pu and 239+240Pu isotopes were measured with an alpha spectrometer. The activities of 241Pu were calculated indirectly by 241Am activity measurements 16-18 years after the Chernobyl accident. The 240Pu/239Pu atomic ratios were measured using accelerator mass spectrometry (AMS. The 241Pu activities indicate that the main impact of the Chernobyl accident was on the plutonium concentration in the components of the Baltic Sea ecosystem examined in this work. The highest 241Pu/239+240Pu activity ratio was found in sea water (140 ± 33. The AMS measurements of atmospheric fallout samples collected during 1986 showed a significant increase in the 240Pu/239Pu atomic ratio from 0.29 ± 0.04 in March 1986 to 0.47 ± 0.02 in April 1986.

  9. Redox equilibria of Pu4+/Pu3+ and PuO22+/Pu4+ couples in molten NaCl-CsCl eutectic as measured by absorption spectrophotometry

    International Nuclear Information System (INIS)

    In order to enhance the understanding of redox reactions of plutonium ions in molten NaCl-CsCl eutectic, absorption spectrophotometry was performed for Pu3+, Pu4+, and PuO22+ in molten NaCl-CsCl at 923 K by controlling the flow-rate ratio of Cl2 and Ar or O2 in the ventilating mixture gas. Based upon the relations of the measured rest potentials to the concentration ratios of [Pu4+]/[Pu3+] and [PuO22+]/[Pu4+], the redox potentials of Pu4+/Pu3+ and PuO22+/Pu4+ couples in molten NaCl-CsCl eutectic at 923 K were estimated. (orig.)

  10. Pu Anion Exchange Process Intensification

    Energy Technology Data Exchange (ETDEWEB)

    Taylor-Pashow, K. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

    2015-10-08

    This project seeks to improve the efficiency of the plutonium anion-exchange process for purifying Pu through the development of alternate ion-exchange media. The objective of the project in FY15 was to develop and test a porous foam monolith material that could serve as a replacement for the current anion-exchange resin, Reillex® HPQ, used at the Savannah River Site (SRS) for purifying Pu. The new material provides advantages in efficiency over the current resin by the elimination of diffusive mass transport through large granular resin beads. By replacing the large resin beads with a porous foam there is much more efficient contact between the Pu solution and the anion-exchange sites present on the material. Several samples of a polystyrene based foam grafted with poly(4-vinylpyridine) were prepared and the Pu sorption was tested in batch contact tests.

  11. Status of 239Pu evaluations

    International Nuclear Information System (INIS)

    This paper summarises the current status of nuclear data evaluations for n+239Pu. The nuclear data we address include fission, capture, scattering cross-sections, as well as the prompt fission neutron energy spectrum, which has large sensitivities to the criticality benchmark testing. The evaluated nuclear data files currently available for 239Pu are compared, and the source of differences in the cross-sections are discussed. Some open questions on the statistical model calculations for deformed systems are also given. (authors)

  12. Program Pu Futures 2006

    Energy Technology Data Exchange (ETDEWEB)

    Fluss, M

    2006-06-12

    The coordination chemistry of plutonium remains relatively unexplored. Thus, the fundamental coordination chemistry of plutonium is being studied using simple multi-dentate ligands with the intention that the information gleaned from these studies may be used in the future to develop plutonium-specific sequestering agents. Towards this goal, hard Lewis-base donors are used as model ligands. Maltol, an inexpensive natural product used in the commercial food industry, is an ideal ligand because it is an all-oxygen bidentate donor, has a rigid structure, and is of small enough size to impose little steric strain, allowing the coordination preferences of plutonium to be the deciding geometric factor. Additionally, maltol is the synthetic precursor of 3,4-HOPO, a siderophore-inspired bidentate moiety tested by us previously as a possible sequestering agent for plutonium under acidic conditions. As comparisons to the plutonium structure, Ce(IV) complexes of the same and related ligands were examined as well. Cerium(IV) complexes serve as good models for plutonium(IV) structures because Ce(IV) has the same ionic radius as Pu(IV) (0.94 {angstrom}). Plutonium(IV) maltol crystals were grown out of a methanol/water solution by slow evaporation to afford red crystals that were evaluated at the Advanced Light Source at Lawrence Berkeley National Laboratory using single crystal X-ray diffraction. Cerium(IV) complexes with maltol and bromomaltol were crystallized via slow evaporation of the mother liquor to afford tetragonal, black crystals. All three complexes crystallize in space group I4{sub 1}/a. The Ce(IV) complex is isostructural with the Pu(IV) complex, in which donating oxygens adopt a trigonal dodecahedral geometry around the metal with the maltol rings parallel to the crystallographic S{sub 4} axis and lying in a non-crystallographic mirror plane of D{sub 2d} molecular symmetry (Fig 1). The metal-oxygen bonds in both maltol complexes are equal to within 0.04 {angstrom

  13. Program Pu Futures 2006

    International Nuclear Information System (INIS)

    The coordination chemistry of plutonium remains relatively unexplored. Thus, the fundamental coordination chemistry of plutonium is being studied using simple multi-dentate ligands with the intention that the information gleaned from these studies may be used in the future to develop plutonium-specific sequestering agents. Towards this goal, hard Lewis-base donors are used as model ligands. Maltol, an inexpensive natural product used in the commercial food industry, is an ideal ligand because it is an all-oxygen bidentate donor, has a rigid structure, and is of small enough size to impose little steric strain, allowing the coordination preferences of plutonium to be the deciding geometric factor. Additionally, maltol is the synthetic precursor of 3,4-HOPO, a siderophore-inspired bidentate moiety tested by us previously as a possible sequestering agent for plutonium under acidic conditions. As comparisons to the plutonium structure, Ce(IV) complexes of the same and related ligands were examined as well. Cerium(IV) complexes serve as good models for plutonium(IV) structures because Ce(IV) has the same ionic radius as Pu(IV) (0.94 (angstrom)). Plutonium(IV) maltol crystals were grown out of a methanol/water solution by slow evaporation to afford red crystals that were evaluated at the Advanced Light Source at Lawrence Berkeley National Laboratory using single crystal X-ray diffraction. Cerium(IV) complexes with maltol and bromomaltol were crystallized via slow evaporation of the mother liquor to afford tetragonal, black crystals. All three complexes crystallize in space group I41/a. The Ce(IV) complex is isostructural with the Pu(IV) complex, in which donating oxygens adopt a trigonal dodecahedral geometry around the metal with the maltol rings parallel to the crystallographic S4 axis and lying in a non-crystallographic mirror plane of D2d molecular symmetry (Fig 1). The metal-oxygen bonds in both maltol complexes are equal to within 0.04 (angstrom) for each oxygen

  14. Preparation of Pu particle quality control materials

    International Nuclear Information System (INIS)

    Plutonium particles were produced at the Technical Research Centre of Finland (VTT) from a well characterized solution of CRM 136 (Department of Energy, New Brunswick Laboratory, Chicago, U.S.A.) after chemical separation of americium (Am) and the plutonium (Pu). Different particle recovery methods were tested and individual Pu particles characterized for their size, Pu content and isotopic composition. Samples with known numbers of individual particles were produced for Pu/Am age dating analysis.

  15. Economical Production of Pu-238

    Energy Technology Data Exchange (ETDEWEB)

    Steven D. Howe; Douglas Crawford; Jorge Navarro; Terry Ring

    2013-02-01

    All space exploration missions traveling beyond Jupiter must use radioisotopic power sources for electrical power. The best isotope to power these sources is plutonium-238. The US supply of Pu-238 is almost exhausted and will be gone within the next decade. The Department of Energy has initiated a production program with a $10M allocation from NASA but the cost is estimated at over $100 M to get to production levels. The Center for Space Nuclear Research has conceived of a potentially better process to produce Pu-238 earlier and for significantly less cost. The new process will also produce dramatically less waste. Potentially, the front end costs could be provided by private industry such that the government only had to pay for the product produced. Under a NASA Phase I NIAC grant, the CSNR has evaluated the feasibility of using a low power, commercially available nuclear reactor to produce at least 1.5 kg of Pu-238 per year. The impact on the neutronics of the reactor have been assessed, the amount of Neptunium target material estimated, and the production rates calculated. In addition, the size of the post-irradiation processing facility has been established. In addition, a new method for fabricating the Pu-238 product into the form used for power sources has been identified to reduce the cost of the final product. In short, the concept appears to be viable, can produce the amount of Pu-238 needed to support the NASA missions, can be available within a few years, and will cost significantly less than the current DOE program.

  16. PU Sizing Agent Sector Starts Reform

    Institute of Scientific and Technical Information of China (English)

    Wang Lei

    2007-01-01

    @@ Polyurethane (PU) sizing agent is a thermoplastic PU elastomer extensively used in synthetic leather, artificial deerskin and electrostatic flocking sectors. The drastic production and demand increase of synthetic leather in China in recent years has promoted rapid consumption growth of PU sizing agent.

  17. On the phase behaviour of the Pu-Ru-C, Pu-Rh-C and Pu-Pd-C systems

    International Nuclear Information System (INIS)

    The phase relations in the platinum metal rich regions of the Pu-Ru-C, Pu-RH-C and Pu-Pd-C systems have been investigated by experiments and are discussed. Ternary perovskite type carbides are observed; the existence, composition, structure and lattice parameters are in accordance with empirical relations obtained previously which are correlated with the reaction behaviour of the actinides within the carbide systems. Additional experiments in the U-Pu-Ru-Rh-Pd-C system reveal that the phase relations obtained in the ternary systems can be extrapolated only with limitations to the six-component system. (orig.)

  18. Determination of plutonium isotopes (238Pu, 239Pu, 240Pu, 241Pu) in environmental samples using radiochemical separation combined with radiometric and mass spectrometric measurements

    DEFF Research Database (Denmark)

    Xu, Yihong; Qiao, Jixin; Hou, Xiaolin;

    2014-01-01

    This paper reports an analytical method for the determination of plutonium isotopes (238Pu, 239Pu, 240Pu, 241Pu) in environmental samples using anion exchange chromatography in combination with extraction chromatography for chemical separation of Pu. Both radiometric methods (liquid scintillation...... counting and alpha spectrometry) and inductively coupled plasma mass spectrometry (ICP-MS) were applied for the measurement of plutonium isotopes. The decontamination factors for uranium were significantly improved up to 7.5×105 for 20 g soil compared to the level reported in the literature......, this is critical for the measurement of plutonium isotopes using mass spectrometric technique. Although the chemical yield of Pu in the entire procedure is about 55%, the analytical results of IAEA soil 6 and IAEA-367 in this work are in a good agreement with the values reported in the literature or reference...

  19. Electronic Correlation Strength of Pu

    DEFF Research Database (Denmark)

    Svane, A.; C. Albers, R.; E. Christensen, N.;

    2013-01-01

    A new electronic quantity, the correlation strength, is defined as a necessary step for understanding the properties and trends in strongly correlated electronic materials. As a test case, this is applied to the different phases of elemental Pu. Within the GW approximation we have surprisingly fo...... found a "universal" scaling relationship, where the f-electron bandwidth reduction due to correlation effects is shown to depend only upon the local density approximation (LDA) bandwidth and is otherwise independent of crystal structure and lattice constant....

  20. The relative uptake of 237Pu(IV) and Pu(VI) oxidation states from water by bush beans

    International Nuclear Information System (INIS)

    Recent data is presented on the status of Pu oxidation states (IV) and (VI) during plant uptake from an aqueous culture. An experiment was performed with bush beans, using 237Pu, to monitor the stability of Pu(IV) and Pu(VI) in the solution phase, to evaluate the relative uptake of each oxidation state by bush beans from water, and to determine the valence of the Pu inside the vascular system by analyzing the xylem exudate. Pu(VI) in solution was assimilated by plants more rapidly than Pu(IV) but was reduced to the less biologically mobile Pu(IV) in the plant biochemical environment. Dominance of Pu(IV) in the xylem exudate indicates that Pu(VI) would not be expected to persist in vegetable matter. Therefore of the biochemically associated Pu in plant matter ingested by humans a considerably larger amount would occur as Pu(IV) than as Pu(VI). (author)

  1. MGA Analysis on Elevated 238 Pu Samples

    Science.gov (United States)

    Wang, T. F.; Moody, K. J.; Raschke, K. E.; Ruhter, W. D.

    2002-10-01

    Plutonium gamma-ray data analysis, in the 100-keV region, using MGA has been improved to overcome the original maximum limit of 2% 238Pu relative plutonium content in a sample in order to perform an analysis. MGA analysis results of elevated 238Pu samples are compared to the results from mass spectrometry.

  2. Simultaneous measurement of 239Pu, 240Pu, 241Pu, and 242Pu by high resolution inductively coupled plasma mass spectrometer (HR ICP-MS) in marine sediments

    International Nuclear Information System (INIS)

    Transuranics elements are of particular interest in radioecological studies because of their radiotoxicity and their potential use to decipher source fingerprints and transport processes. The simultaneous measurement of 239Pu, 240Pu, 241Pu, and 242Pu in environmental samples requires a specific chemical procedure. This work deals with an analytical procedure which yields a very high grade of purification of Pu suitable for ultra low level detection by HR ICP-MS, from marine sediments. After the elimination of major elements (Fe, Al, Mg...) by a first chromatographic separation, a new device of purification by solvent extraction and concentration by a second chromatographic separation is used to obtain a concentrated and high purified solution of plutonium. The chemical procedure have been validated on IAEA certified sediment samples and on sediment samples collected in the roads of Cherbourg which had been previously analysed by other techniques (a spectrometry and thermo-ionisation mass spectrometer). (author)

  3. Chemical speciation of Pu in natural waters

    International Nuclear Information System (INIS)

    The behavior of plutonium in natural waters is determined to a major degree by the chemical forms which are present. We have characterized the ambient Pu in a number of surface waters with regard to its oxidation state and association with natural colloidal organic carbon compounds using a combination of field measurements and laboratory experiments. Both of these factors are shown to have a profound effect on the adsorption of Pu to natural sediments, since both complexation with organic matter and oxidation compete with adsorption. The concentration of organic carbon in the water is the key variable influencing both oxidation state and organic binding. The adsorption process conforms to the laws applicable to a reversible equilibrium with values of the distribution coefficient, K/sub D/, measured in laboratory experiments being similar to those observed for ambient Pu. Experiments using natural waters and sediments in which the Pu concentration was varied show the forms present at typical ambient concentrations (10-17 - 10-14 M) are the same as those found at concentrations up to 10-7 M. Moreover, the affinity for sediments did not change with concentration indicating the binding sites for Pu had not become saturated. Thus, the behavior observed for Pu at ultratrace concentrations should remain unchanged throughout this concentration range. The studies in this report all deal with Pu in exchangeable (and hence source independent) forms and should therefore reflect the behavior toward which the plutonium from any source will tend with time. 13 references, 7 figures, 10 tables

  4. Economical perspective of a global Pu economy

    International Nuclear Information System (INIS)

    Up to now, many times Nuclear Power Sector developed medium and long term Nuclear Energy Forecast, and in many scenario, the scarcity of future Uranium resources could produce a generalized used to Pu in the fuel cycle

  5. Isotope ratios of 240Pu/239Pu in soil samples from different areas

    International Nuclear Information System (INIS)

    Plutonium concentrations and 240Pu/239Pu atom ratios in soil samples from Japan and other areas in the world (including IAEA standard reference materials) were determined by ICP-MS. The range of 240Pu/239Pu atom ratios observed in 21 Japanese soil samples was 0.155 - 0.194 and the average was 0.180 ± 0.011, which is comparable to the global fallout value. A low ratio of about 0.05, which is derived from Pu-bomb, was found in samples from Nishiyama (Nagasaki) and Mururoa Atoll (IAEA-368), while a high ratio of about 0.31 was found in a sample from Bikini Atoll (Marshall Islands). The ratio for Irish Sea sediment (IAEA-135) was 0.21, which was higher than the global fallout value, suggesting the influence by the contamination from the Sellafield facility. The 240Pu/239Pu atom ratios in soils from the Chernobyl area were determined, and the ratio was found to be very high (about 0.4), indicating the high burn-up grade of the reactor fuel. These results show that the 240Pu/239Pu ratio can be used as a finger print to identify the source of the contamination. (author)

  6. Octupole correlations in U and Pu nuclei

    International Nuclear Information System (INIS)

    We study the even-even U and Pu nuclei in the framework of the spdf interacting boson model. Analysis of the systematics of positive and negative parity bands, together with the E1, E2, and E3 transitions, suggests that the properties of low-lying states can be understood without the introduction of stable octupole deformation. Double octupole phonon characteristics are also identified in certain low-lying 0+ excited states in U and Pu

  7. Aqueous Pu(IV) sorption on brucite

    International Nuclear Information System (INIS)

    The sorption behavior of aqueous Pu(IV) on brucite (Mg(OH)2) in the presence and absence of citrate was investigated by a combination of wet chemical batch sorption experiments and X-ray photoelectron spectroscopy (XPS). Sorption occurs rapidly at near 100% levels from pH 8 to pH 13, and is not affected by the presence of citrate. XPS results indicate that Pu was incorporated in the subsurface in the cases studied. (orig.)

  8. XAS and XRD study of annealed 238Pu- and 239Pu-substituted zircons (Zr0.92Pu0.08SiO4)

    International Nuclear Information System (INIS)

    An annealing study has been completed on two compositionally identical Pu-substituted zircons (Zr0.92Pu0.08SiO4) prepared 18 yr ago with different 238Pu/239Pu isotopic ratios. The activity and accumulated dose for each material varies greatly due to the very different half-lives of 238Pu (87.7 yr) and 239Pu (24 100 yr). The predominantly 238Pu-substituted zircon is in a highly amorphous state after accumulating a dose of 2.8x1019 α-decays/g, which is a factor of two higher than the dose previously determined necessary to amorphize this material. The 239Pu-substituted zircon has remained highly crystalline after an accumulated dose of 1.2x1017 α-decays/g. The Pu in both samples is trivalent due to sintering under reducing conditions. The short-range and long-range structures of each sample have been characterized by detailed X-ray absorption spectroscopy and X-ray diffraction (XRD) methods. The oxidation of Pu3+ to Pu4+ in the crystalline 239Pu-substituted zircon during annealing in air resulted in a decrease in lattice distortion due to the decrease in ionic radius of Pu3+ to Pu4+ on the Zr4+ site. A significant amount of PuO2 exsolved from the zircon structure after annealing at 1200 deg. C in air. Detailed characterization of the amorphous 238Pu-substituted zircon demonstrated that while devoid of long-range order it still retained a distorted zircon structure and composition over a length scale of 0.5 nm. The recrystallization of the amorphous 238Pu-substituted zircon could be achieved directly at temperatures as low as 1200 deg. C when annealed for 12 h in air; however, annealing at 1000 deg. C resulted in decomposition into constituent oxides

  9. 240Pu/239Pu atom ratios in seawater from the western North Pacific and its marginal sea

    International Nuclear Information System (INIS)

    Full text: The atom ratio of 240Pu/239Pu is known to be a useful tracer to identify the sources of plutonium in the ocean. The objectives of this study are to measure the 239+240Pu activities and 240Pu/239Pu atom ratios in seawater from the western North Pacific and its marginal sea and to discuss the transport processes of plutonium. The 240Pu/239Pu atom ratios were measured with sector-field ICPMS. The atom ratios were significantly higher than the mean global fallout ratio. These high atom ratios proved the existence of close-in fallout plutonium originating from the Pacific proving grounds. (author)

  10. Synthesis and study of 239Pu-doped ceramics based on zircon, (Zr,Pu)Sio4, and hafnon, (Hf,Pu)SiO4

    International Nuclear Information System (INIS)

    Zircon, ZrSiO4, as well as its Hf-analogue hafnon, HfSiO4, have been proposed for use as durable Pu host phases for the immobilization of weapons grade Pu and other actinides. Four samples of Pu-doped ceramics based on the zircon and hafnon structures were synthesized through sintering in air using precursors containing 5-6 and 10 wt% 239Pu. Synthesized ceramic samples were studied by X-ray powder diffraction (XRD), scanning electron microscopy (SEM), microprobe method, MCC-1 leach test at 25 and 90 deg C. Inclusions of separated a PuO2 phase in the matrix of zircon-based ceramic and presumably, (Pu,Hf)O2 phase in the hafnon-based ceramic were observed for samples obtained from precursors doped with 10 wt% Pu. No separated Pu-phases in significant amounts were identified in the matrices of both ceramics obtained from the precursors doped with 5-6 wt% Pu. It was found that normalized Pu mass losses (without correction on ceramic porosity) for samples doped with 10 wt% Pu which contain separated inclusions of PuO2 or (Pu1Hf)O2 after 14/28 days were approximately (in g/m2) - for zircon: 0.2/0.2 - at 90 deg C and 0.03/0.04 - at 25 deg C and for hafnon: 0.02/0.04 - at 90 deg C and 0.01/0.01 - at 25 deg C. The losses of Pu from samples doped with 5-6 wt% are 1-2 order of magnitude less. It was suggested that optimal amount of Pu which could be incorporated by zircon and hafnon lattices does not exceed 7 wt%. An important additional conclusion is that Pu-doped ceramic based on zircon or hafnon can be successfully fabricated excluding hot pressing method. Copyright (2001) Material Research Society

  11. Worldwide data on fluxes of 239,240Pu, 238Pu to the oceans

    International Nuclear Information System (INIS)

    According to measurements (GEOSECS) the world's oceans contain approximately 16 PBq 239,240Pu, of which one-fourth is in the Atlantic and three-fourths in the Pacific Ocean. The expected inventory (from nuclear weapons testing) in the world's oceans is 12 PBq 239,240Pu including local fallout at the test sites. In the Irish Sea a local contamination of 0.3 PBq 239,240Pu from the Sellafield reprocessing plant resides in the sediments. No other sources than fallout and reprocessing add significantly to the 239,240Pu inventories in the oceans. The discrepancy between measurements and expectations are assumed to be due to an underestimate of the rainfall and dry fallout (seaspray) and thus of the Pu-deposition over the oceans, but may also to some degree be due to inadequate sampling

  12. Neutron-diffraction study of PuAs and PuSb

    Science.gov (United States)

    Burlet, P.; Quezel, S.; Rossat-Mignod, J.; Spirlet, J. C.; Rebizant, J.; Müller, W.; Vogt, O.

    1984-12-01

    The first neutron scattering experiments on PuAs and PuSb single crystals are reported. PuAs is found to be a ferromagnet below Tc=123+/-1 K. PuSb develops below TN=85+/-1 K an incommensurate ordering and undergoes, at TIC=67 K, a first-order transition to a commensurate phase, ferromagnetic in nature. In both compounds, moments are perpendicular to the ferromagnetic (001) planes, their low-temperature value is μ=(0.75+/-0.1)μB, indicating a Γ8-type ground state within the Russell-Saunders level scheme. The magnetic phase diagram of PuSb has been determined. The incommensurate phase is suppressed by a small field of 8.5 kOe.

  13. Neutron-diffraction study of PuAs and PuSb

    International Nuclear Information System (INIS)

    The first neutron scattering experiments on PuAs and PuSb single crystals are reported. PuAs is found to be a ferromagnet below T/sub c/ = 123 +- 1 K. PuSb develops below T/sub N/ = 85 +- 1 K an incommen- surate ordering and undergoes, at T/sub I/C = 67 K, a first-order transition to a commensurate phase, ferromagnetic in nature. In both compounds, moments are perpendicular to the ferromagnetic (001) planes, their low-temperature value is μ = (0.75 +- 0.1)μ/sub B/, indicating a GAMMA8-type ground state within the Russell-Saunders level scheme. The magnetic phase diagram of PuSb has been determined. The incommensurate phase is suppressed by a small field of 8.5 kOe

  14. Temperature and time-dependence of the elastic moduli of Pu and Pu-Ga alloys

    Energy Technology Data Exchange (ETDEWEB)

    Migliori, Albert [Los Alamos National Laboratory, Los Alamos, NM (United States); Mihut, I. [Los Alamos National Laboratory, Los Alamos, NM (United States)], E-mail: izabela@lanl.gov; Betts, J.B.; Ramos, M.; Mielke, C.; Pantea, C.; Miller, D. [Los Alamos National Laboratory, Los Alamos, NM (United States)

    2007-10-11

    In previous work, on cooling from 300 K to 10 K the elastic moduli for both {alpha}- and {delta}-Pu dropped 30%. This large change may reflect effects of 5f-electron localization. In this work, the elastic moduli at ambient temperature of several Pu-Ga alloys were measured using resonant ultrasound spectroscopy (RUS). The strong temperature dependence of the bulk and shear modulus and the temperature independence of Poisson's ratio was confirmed and the upper temperature limit for {alpha}-Pu was extended to 360 K. Measurements of the time dependence of the shear moduli of Pu and Pu-2.36 at.% Ga were determined with high precision as a function of time and temperature. Using a model for time dependence of point defects, we determined the exponential time constant at ambient temperature for such variations. The low temperature results are consistent with Fluss.

  15. Temperature and time-dependence of the elastic moduli of Pu and Pu-Ga alloys

    International Nuclear Information System (INIS)

    In previous work, on cooling from 300 K to 10 K the elastic moduli for both α- and δ-Pu dropped 30%. This large change may reflect effects of 5f-electron localization. In this work, the elastic moduli at ambient temperature of several Pu-Ga alloys were measured using resonant ultrasound spectroscopy (RUS). The strong temperature dependence of the bulk and shear modulus and the temperature independence of Poisson's ratio was confirmed and the upper temperature limit for α-Pu was extended to 360 K. Measurements of the time dependence of the shear moduli of Pu and Pu-2.36 at.% Ga were determined with high precision as a function of time and temperature. Using a model for time dependence of point defects, we determined the exponential time constant at ambient temperature for such variations. The low temperature results are consistent with Fluss

  16. Prompt fission γ -ray spectrum characteristics from 240Pu(sf ) and 242Pu(sf )

    Science.gov (United States)

    Oberstedt, S.; Oberstedt, A.; Gatera, A.; Göök, A.; Hambsch, F.-J.; Moens, A.; Sibbens, G.; Vanleeuw, D.; Vidali, M.

    2016-05-01

    In this paper we present first results for prompt fission γ -ray spectra (PFGS) characteristics from the spontaneous fission (sf) of 240Pu and 242Pu. For 242Pu(sf ) we obtained, after proper unfolding of the detector response, an average energy per photon ɛ¯γ=(0.843 ±0.012 ) MeV, an average multiplicity M¯γ=(6.72 ±0.07 ) , and an average total γ -ray energy release per fission E¯γ ,tot = (5.66 ± 0.06) MeV. The 240Pu(sf ) emission spectrum was obtained by applying a so-called detector-response transformation function determined from the 242Pu spectrum measured in exactly the same geometry. The results are an average energy per photon ɛ¯γ=(0.80 ±0.07 ) MeV, the average multiplicity M¯γ = (8.2 ± 0.4), and an average total γ -ray energy release per fission E¯γ ,tot = (6.6 ± 0.5) MeV. The PFGS characteristics for 242Pu(sf ) are in very good agreement with those from thermal-neutron-induced fission on 241Pu and scales well with the corresponding prompt neutron multiplicity. Our results in the case of 240Pu(sf ), although drawn from a limited number of events, show a significantly enhanced average multiplicity and average total energy, but may be understood from a different fragment yield distribution in 240Pu(sf ) compared to that of 242Pu(sf ).

  17. Neutron nuclear data for Pu-240

    International Nuclear Information System (INIS)

    The report gives evaluated nuclear data for the isotopes 239Pu, 240Pu, 241Pu and 242Pu, in the energy region 10-5eV-15 MeV needed for reactor calculations and other applications. Tables of Q-values and threshold energies are first presented for different possible reactions of neutrons with these nuclei. Then, evaluated data for 240Pu are given for the following characteristics of possible neutron reactions: total interaction cross-section, absorption cross-section, radiative capture cross-section, elastic and inelastic scattering cross-sections, cross sections of the (n, zn) and (n, 3n) reactions, average number of neutrons per fission event and per absorption event, elastic and inelastic scattering angular distributions, energy distributions of secondary neutrons, gamma-ray spectra. In addition, group-averaged constants are given. The parameters used in the calculations in the resonance energy region, unresolved resonance region and fast neutron energy region are specified. The evaluated data constitute a nuclear constants library and have been approved as standard for use in the USSR

  18. Redefining design criteria for Pu-238 gloveboxes

    Energy Technology Data Exchange (ETDEWEB)

    Acosta, S.V.

    1998-12-31

    Enclosures for confinement of special nuclear materials (SNM) have evolved into the design of gloveboxes. During the early stages of glovebox technology, established practices and process operation requirements defined design criteria. Proven boxes that performed and met or exceeded process requirements in one group or area, often could not be duplicated in other areas or processes, and till achieve the same success. Changes in materials, fabrication and installation methods often only met immediate design criteria. Standardization of design criteria took a big step during creation of ``Special-Nuclear Materials R and D Laboratory Project, Glovebox standards``. The standards defined design criteria for every type of process equipment in its most general form. Los Alamos National Laboratory (LANL) then and now has had great success with Pu-238 processing. However with ever changing Environment Safety and Health (ES and H) requirements and Ta-55 Facility Configuration Management, current design criteria are forced to explore alternative methods of glovebox design fabrication and installation. Pu-238 fuel processing operations in the Power Source Technologies Group have pushed the limitations of current design criteria. More than half of Pu-238 gloveboxes are being retrofitted or replaced to perform the specific fuel process operations. Pu-238 glovebox design criteria are headed toward process designed single use glovebox and supporting line gloveboxes. Gloveboxes that will house equipment and processes will support TA-55 Pu-238 fuel processing needs into the next century and extend glovebox expected design life.

  19. An alternative structure of Pu4O9 (''PuO2.25'') incorporating interstitial hydroxyl rather than oxide

    International Nuclear Information System (INIS)

    Bond length/bond strength relationships are applied to the Pu4O9 ('PuO2.25') structure proposed by others and support one Pu(V) with a central hydroxyl ion but not a central oxide ion nor formation of Pu(VI). Bond distances and bond strengths are normal for a central ion of unit charge, and reconcile the finding that cell dimensions are so minimally changed from those of PuO2. Substitution of hydroxyl for oxide accounts for the 'excess' oxygen content of PuO2.265, yielding PuO2(OH)0.249. The short range, local order (structure) of the 'Pu4O9' entity is alternatively formulated as Pu4O8OH

  20. Localized 5f electrons in superconducting PuCoIn5: consequences for superconductivity in PuCoGa5

    International Nuclear Information System (INIS)

    The physical properties of the first In analog of the PuMGa5 (M = Co, Rh) family of superconductors, PuCoIn5, are reported. With its unit cell volume being 28% larger than that of PuCoGa5, the characteristic spin-fluctuation energy scale of PuCoIn5 is three to four times smaller than that of PuCoGa5, which suggests that the Pu 5f electrons are in a more localized state relative to PuCoGa5. This raises the possibility that the high superconducting transition temperature Tc = 18.5 K of PuCoGa5 stems from the proximity to a valence instability, while the superconductivity at Tc = 2.5 K of PuCoIn5 is mediated by antiferromagnetic spin fluctuations associated with a quantum critical point. (fast track communication)

  1. Presence of plutonium isotopes, {sup 239}Pu and {sup 240}Pu, in soils from Chile

    Energy Technology Data Exchange (ETDEWEB)

    Chamizo, E., E-mail: echamizo@us.es [Centro Nacional de Aceleradores, Avda. Thomas Alba Edison, 7, 41092 Sevilla (Spain); Garcia-Leon, M., E-mail: manugar@us.es [Departamento de Fisica Atomica, Molecular y Nuclear, Universidad de Sevilla, Avda. Reina Mercedes sn, 41012 Seville (Spain); Peruchena, J.I., E-mail: jiperuchena@gmail.com [Centro Nacional de Aceleradores, Avda. Thomas Alba Edison, 7, 41092 Sevilla (Spain); Cereceda, F., E-mail: francisco.cereceda@usm.cl [Laboratorio de Quimica Ambiental, Centro de Tecnologias Ambientales (CETAM), Universidad Tecnica Federico Santa Maria, Casilla 110-V, Valparaiso (Chile); Vidal, V., E-mail: victor.vidal@usm.cl [Laboratorio de Quimica Ambiental, Centro de Tecnologias Ambientales (CETAM), Universidad Tecnica Federico Santa Maria, Casilla 110-V, Valparaiso (Chile); Pinilla, E., E-mail: epinilla@unex.es [Departamento de Quimica Analitica, Facultad de Ciencias, Universidad de Extremadura, Avda. de Elvas sn, 06071 Badajoz (Spain); Miro, C., E-mail: cmiro@unex.es [Departamento de Fisica Aplicada, Universidad de Extremadura, Avda. de la Universidad sn, 10071 Caceres (Spain)

    2011-12-15

    Plutonium is present in every environmental compartment, due to a variety of nuclear activities. The Southern Hemisphere has received about 20% of the global {sup 239}Pu and {sup 240}Pu environmental inventory, with an important contribution of the so-called tropospheric fallout from both the atmospheric nuclear tests performed in the French Polynesia and in Australia by France and United Kingdom, respectively. In this work we provide new data on the impact of these tests to South America through the study of {sup 239}Pu and {sup 240}Pu in soils from different areas of Northern, Central and Southern Chile. The obtained results point out to the presence of debris from the French tests in the 20-40 Degree-Sign Southern latitude range, with {sup 240}Pu/{sup 239}Pu atomic ratios quite heterogeneous and ranging from 0.02 to 0.23. They are significantly different from the expected one for the global fallout in the Southern Hemisphere for the 30-53 Degree-Sign S latitude range (0.185 {+-} 0.047), but they follow the same trend as the reported values by the Department of Energy of United States for other points with similar latitudes. The {sup 239+240}Pu activity inventories show as well a wider variability range in that latitude range, in agreement with the expected heterogeneity of the contamination.

  2. Presence of plutonium isotopes, 239Pu and 240Pu, in soils from Chile

    International Nuclear Information System (INIS)

    Plutonium is present in every environmental compartment, due to a variety of nuclear activities. The Southern Hemisphere has received about 20% of the global 239Pu and 240Pu environmental inventory, with an important contribution of the so-called tropospheric fallout from both the atmospheric nuclear tests performed in the French Polynesia and in Australia by France and United Kingdom, respectively. In this work we provide new data on the impact of these tests to South America through the study of 239Pu and 240Pu in soils from different areas of Northern, Central and Southern Chile. The obtained results point out to the presence of debris from the French tests in the 20–40° Southern latitude range, with 240Pu/239Pu atomic ratios quite heterogeneous and ranging from 0.02 to 0.23. They are significantly different from the expected one for the global fallout in the Southern Hemisphere for the 30–53°S latitude range (0.185 ± 0.047), but they follow the same trend as the reported values by the Department of Energy of United States for other points with similar latitudes. The 239+240Pu activity inventories show as well a wider variability range in that latitude range, in agreement with the expected heterogeneity of the contamination.

  3. Transmutation of 239Pu with spallation neutrons

    International Nuclear Information System (INIS)

    Incineration studies of plutonium were carried out at the Synchrophasotron of the Joint Institute for Nuclear Research (JINR), Dubna, using proton beams with energies of 0.53 GeV and 1.0 GeV. Solid lead targets (8 cm in diameter and 20 cm long) were surrounded with 6 cm thick paraffin as neutron moderator and then irradiated. The transmutation of 239Pu and the associated production of fission products 91Sr, 92Sr, 97Zr, 99Mo, 103Ru, 105Ru, 129Sb, 132Te, 133I, 135I and 143Ce were studied in the present work. The plutonium samples (each 449 mg) were placed on the outer surface of moderator. For 1.0 GeV proton beam, the fission rate of 239Pu is 0.0032 atoms per proton in one gram plutonium samples, for 0.53 GeV proton this value is 0.0022. The experimental uncertainty is about 15%. The experiments are compared to two theoretical model calculations with moderate success, using the Dubna Cascade Model (CEM) and the LAHET code. The practical incineration rate of 239Pu is very high. For example: if one uses 10 mA, 1 GeV proton beams under the same (fictive) experimental conditions, the incineration rate of 239Pu via fission is 3 mg out of the 449 mg sample per day. For 0.53 GeV protons the corresponding rate is 2 mg per day. (author)

  4. Experimental Benchmarking of Pu Electronic Structure

    International Nuclear Information System (INIS)

    The standard method to determine the band structure of a condensed phase material is to (1) obtain a single crystal with a well defined surface and (2) map the bands with angle resolved photoelectron spectroscopy (occupied or valence bands) and inverse photoelectron spectroscopy (unoccupied or conduction bands). Unfortunately, in the case of Pu, the single crystals of Pu are either nonexistent, very small and/or having poorly defined surfaces. Furthermore, effects such as electron correlation and a large spin-orbit splitting in the 5f states have further complicated the situation. Thus, we have embarked upon the utilization of unorthodox electron spectroscopies, to circumvent the problems caused by the absence of large single crystals of Pu with well-defined surfaces. Our approach includes the techniques of resonant photoelectron spectroscopy, x-ray absorption spectroscopy, electron energy loss spectroscopy, Fano Effect measurements, and Bremstrahlung Isochromat Spectroscopy, including the utilization of micro-focused beams to probe single-crystallite regions of polycrystalline Pu samples.

  5. Investigation of single crystal zircon, (Zr,Pu)SiO4 doped with Pu

    Science.gov (United States)

    Hanchar, J. M.; Burakov, B. E.; Anderson, E. B.; Zamoryanskaya, M. V.

    2003-04-01

    Zircon-based ceramics are under consideration as durable waste forms for immobilization of weapons grade plutonium and other actinide elements. Samples of polycrystalline zircon doped with 238Pu and 239Pu have been obtained in previous studies. These materials, however, are difficult to use for precise measurement of the leach-rate of Pu, and to accurately determine the level of Pu doping that can be attained in zircon, (Zr,Pu)SiO_4. Single crystals of 238Pu doped zircon (ranging from 0.3 to 3.5 mm in size) were successfully grown for the first time ever using a Li-Mo flux synthesis method. The incorporation of Pu ranged from 1.9 to 4.7 wt. % el. (with approximately 81 wt.% of 238Pu isotope) based on electron microprobe analysis. The zircon crystals were pinkish-brown when they were crystallized, and then over a period of five months changed to a brown color. After fourteen months the crystals turned to a brown-gray color. The zircon crystals glow in the dark probably from alpha particle induced luminescence. The intensity of the cathodoluminescence (CL) emission in the Pu doped crystals is correlated with the Pu content, and the CL emission showed no change 141 days after the initial CL measurements were made. Single crystal X-ray diffraction results obtained 141 days after synthesis indicate unit cell parameters (in angstroms): a = 6.6267(15), c = 5.9992(10) and a cell volume of 263.41(10). When the zircon crystals were grown, they were free of cracks. Over the course of five months cracks appeared throughout the crystals, and after fourteen months the cracks became much more abundant. The zircon crystals were transparent upon crystallization, and even with numerous cracks throughout the crystals remain transparent. Radiation damage calculations indicate that after only a short period of time, six months, these zircon crystals had already accumulated significant alpha-induced radiation damage (˜2.5 x1014 alpha-decay events per milligram). After five years they

  6. Study and Application of Closed HOPG Diffractive EDXRF in Research of Pu Purification

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>In the Pu purification research, the recovering of Pu is very important. So the Pu concentration in the tail solution must be strictly controlled to several μg/mL. To determine Pu concentration in the tail

  7. Environmental actinide research. Present and future situations on Pu research

    International Nuclear Information System (INIS)

    With looking back on the environmental radioactivity researches, paper of environmental Pu is stated since 1996. On atmosphere environment, 137Cs, 90Sr and 239,240Pu, which do not exist in nature, are used as tracers of atmosphere to make clear global material circulation in atmosphere. By observation of fallout of 239,240Pu, there were rare amount of fallout from the nuclear tests in atmosphere, but re-flotation from fallout was observed. A state and measurement of each particle size of aerosol are reported. On land environment, there are hot-particle of environmental Pu in local area of nuclear test, nuclear accidents of nuclear installations and reprocessing plants. They changed with time. The states of hot-particle are observed by SEM, ED-XRF, XRD, laser and synchrotron orbital radiation. Pu behavior in land was reported. Effects of bacteria and Lichens on Pu and Pu in ground water and river were studied. On hydrosphere, the transfer and distribution model of Pu and a simulation model of the physical and chemical state of Pu in the Irish Sea were constructed by many kinds of researches. Local pollution of the coast of Spain, Greenland and the Marshall Islands are reported. The depth distribution of 239,240Pu in the sea was clear. The sedimentation behavior of Pu in the sea is studied. Today, the very low concentration of Pu in the sea is measured by ICP-MS, TIMS and AMS. (S.Y.)

  8. Prediction of thermodynamic property of Pu-zircon and Pu-pyrochlore

    Science.gov (United States)

    Xu, Hulfang; Wang, Yifeng

    2000-07-01

    Due to its high durability, zircon is often present as a heavy mineral in natural environments and is the oldest mineral that has been dated on the earth. There are four zircon structure phases of M4+SiO4 occurring in nature: zircon (ZrSiO4), hafnon (HfSiO4), thorite (ThSiO4), and coffinite (USiO4). These phases may form solid solution. Recent interest in zircon minerals stems from the study of highly durable radioactive waste forms. Crystalline phases of M4+SiO4 with zircon structure have been proposed as a durable ceramic waste form for immobilizing actinides such as Pu, Np, and U. To predict the behavior of zircon-based waste forms in a geologic repository environment as well as to optimize the fabrication of those waste forms, the thermodynamic and kinetic properties for zircon mineral phases have to be determined. In this paper, we use a linear free energy relationship to predict the Gibbs free energies of formation of Pu-bearing phases (Xu et al., 1999). The calculated results show that the PuSiO4 phase with zircon structure is unstable with respect to oxides of PuO2 and quartz. However, the PuSiO4 phase will be stable with respect to oxides of PuO2 and silica glass at low temperature.

  9. Contribution to the study of the upper valence states of Pu

    International Nuclear Information System (INIS)

    The properties of the Pu(VI) and Pu(VII) ions in aqueous solutions were investigated: spectrophotometric study of the formation of PuO22+ complexes with hydroxyl ions; electrochemical study of PuO22+; preparation, determination and coprecipitation of Pu(VII); electrochemical study of Pu(VII). A preliminary research was made on the chemistry of Pu in non-aqueous solutions especially the dissolution and the determination of Pu in propylene carbonate

  10. Neutron inelastic-scattering cross sections of 232Th, 233U, 235U, 238U, 239Pu and 240Pu

    International Nuclear Information System (INIS)

    Differential-neutron-emission cross sections of 232Th, 233U, 235U, 238U, 239Pu and 240Pu are measured between approx. = 1.0 and 3.5 MeV with the angle and magnitude detail needed to provide angle-integrated emission cross sections to approx. 232Th, 233U, 235U and 238U inelastic-scattering values, poor agreement is observed for 240Pu, and a serious discrepancy exists in the case of 239Pu

  11. Pu speciation in actual and simulated aged wastes

    Energy Technology Data Exchange (ETDEWEB)

    Lezama-pacheco, Juan S [Los Alamos National Laboratory; Conradson, Steven D [Los Alamos National Laboratory

    2008-01-01

    X-ray Absorption Fine Structure Spectroscopy (XAFS) at the Pu L{sub II/III} edge was used to determine the speciation of this element in (1) Hanford Z-9 Pu crib samples, (2) deteriorated waste resins from a chloride process ion-exchange purification line, and (3) the sediments from two Waste Isolation Pilot Plant Liter Scale simulant brine systems. The Pu speciation in all of these samples except one is within the range previously displayed by PuO{sub 2+x-2y}(OH){sub y}{center_dot}zH{sub 2}O compounds, which is expected based on the putative thermodynamic stability of this system for Pu equilibrated with excess H{sub 2}O and O{sub 2} under environmental conditions. The primary exception was a near neutral brine experiment that displayed evidence for partial substitution of the normal O-based ligands with Cl{sup -} and a concomitant expansion of the Pu-Pu distance relative to the much more highly ordered Pu near neighbor shell in PuO{sub 2}. However, although the Pu speciation was not necessarily unusual, the Pu chemistry identified via the history of these samples did exhibit unexpected patterns, the most significant of which may be that the presence of the Pu(V)-oxo species may decrease rather than increase the overall solubility of these compounds. Several additional aspects of the Pu speciation have also not been previously observed in laboratory-based samples. The molecular environmental chemistry of Pu is therefore likely to be more complicated than would be predicted based solely on the behavior of PuO{sub 2} under laboratory conditions.

  12. Determination of 240Pu/239Pu isotope ratios in Kara Sea and Novaya Zemlya sediments using accelerator mass spectrometry

    International Nuclear Information System (INIS)

    Accelerator mass spectrometry (AMS) has been used to determine Pu activity concentrations and 240Pu/239Pu isotope ratios in sediments from the Kara Sea and radioactive waste dumping sites at Novaya Zemlya. Measured 239,240Pu activities ranged from 0.06 - 9.8 Bq/kg dry weight, 240Pu/239Pu atom ratios ranged from 0.13 to 0.28, and 238Pu/239,240Pu activity ratios from 0.02 to 0.6. Perturbations from global fallout isotope ratios were evident at three sites: the Yenisey Estuary and Abrosimov Fjords where 240Pu/239Pu ratios were lower (0.13-0.14); and Stepovogo Fjord sediments where ratios were higher (up to 0.28) than fallout ratios. Based on procedural blanks, detection limits for AMS were below 1 fg Pu and the method showed good precision for isotope ratio measurements, minimal matrix, interference and memory effects. For high level samples, comparison between alpha spectrometry and AMS gave good agreement for measurement of 239,240Pu activity concentrations. (author)

  13. Redox reactions of Pu(IV) and Pu(III) in the presence of acetohydroxamic acid in HNO(3) solutions.

    Science.gov (United States)

    Tkac, Peter; Precek, Martin; Paulenova, Alena

    2009-12-21

    The reduction of Pu(IV) in the presence of acetohydroxamic acid (HAHA) was monitored by vis-NIR spectroscopy. All experiments were performed under low HAHA/Pu(IV) ratios, where only the Pu(IV)-monoacetohydroxamate complex and Pu uncomplexed with HAHA were present in relevant concentrations. Time dependent concentrations of all absorbing species were resolved using molar extinction coefficients for Pu(IV), Pu(III), and the Pu(AHA)(3+) complex by deconvolution of spectra. From fitting of the experimental data by rate equations integrated by a numeric method three reactions were proposed to describe a mechanism responsible for the reduction and oxidation of plutonium in the presence of HAHA and HNO(3). Decomposition of Pu(AHA)(3+) follows a second order reaction mechanism with respect to its own concentration and leads to the formation of Pu(III). At low HAHA concentrations, a two-electron reduction of uncomplexed Pu(IV) with HAHA also occurs. Formed Pu(III) is unstable and slowly reoxidizes back to Pu(IV), which, at the point when all HAHA is decomposed, can be catalyzed by the presence of nitrous acid. PMID:19904974

  14. Preliminary studies of Pu measurement by AMS using PuF4-

    Science.gov (United States)

    Zhao, X.-L.; Kieser, W. E.; Dai, X.; Priest, N. D.; Kramer-Tremblay, S.; Eliades, J.; Litherland, A. E.

    2013-01-01

    Using targets made with PbF2 matrices, Cs+ sputter sources have been found to yield element-specific patterns of molecular fluoride anions that may be used to enhance the mass spectrometry of certain elements. While the patterns are found similar for all lanthanides and the heavier actinides, substantial differences are found for the lighter actinides. In the case of Pu and U, of all their fluoride anions, PuF4- and UF5- are produced with the highest yield. Mass spectrometry of Pu using PuF4- can provide a partial chemical separation in the ion source, as the yield of UF4- is two orders of magnitude lower than that of the UF5-. This, in turn, reduces scattering of U ions when measuring Pu in the high-energy components of the AMS system. This instrumental reduction of U is advantageous in cases that require rapid Pu analyses as it simplifies the chemistry of Pu/U separation and other steps in the sample processing. In this procedure, Pu can be co-precipitated with another element as a fluoride, which is then mixed with a sufficient amount of PbF2 powder to form a sputter target. A series of tests were carried out and NdF3 was identified as one such suitable carrier. Measurements of Pu+3 at ∼0.85 MV terminal voltage showed that the 239,240,241,242Pu isotopes can be detected with a manageably low background, high efficiency and a 1 fg detection limit. Preliminary tests were carried out using the existing IsoTrace AMS system, modified only by the addition of electronic controls to automatically adjust the terminal voltage and all high-energy electric analyzers, along with the injection magnet bouncer. However, both the injection and detection systems were not designed for this task, so considerable room is available for reducing the detection limit into the ag range with modern AMS systems - such as the one being commissioned at University of Ottawa.

  15. Preliminary studies of Pu measurement by AMS using PuF{sub 4}{sup -}

    Energy Technology Data Exchange (ETDEWEB)

    Zhao, X.-L., E-mail: xzha5@uottawa.ca [Department of Physics, University of Ottawa, 150 Louis Pasteur, Ottawa, ON., K1N 6N5 (Canada); Kieser, W.E. [Department of Physics, University of Ottawa, 150 Louis Pasteur, Ottawa, ON., K1N 6N5 (Canada); Dai, X.; Priest, N.D.; Kramer-Tremblay, S. [Chalk River Laboratories, AECL, Chalk River, ON., K0J 1J0 (Canada); Eliades, J.; Litherland, A.E. [IsoTrace Laboratory, University of Toronto, 60 St. George St., Toronto, ON., M5S 1A7 (Canada)

    2013-01-15

    Using targets made with PbF{sub 2} matrices, Cs{sup +} sputter sources have been found to yield element-specific patterns of molecular fluoride anions that may be used to enhance the mass spectrometry of certain elements. While the patterns are found similar for all lanthanides and the heavier actinides, substantial differences are found for the lighter actinides. In the case of Pu and U, of all their fluoride anions, PuF{sub 4}{sup -} and UF{sub 5}{sup -} are produced with the highest yield. Mass spectrometry of Pu using PuF{sub 4}{sup -} can provide a partial chemical separation in the ion source, as the yield of UF{sub 4}{sup -} is two orders of magnitude lower than that of the UF{sub 5}{sup -}. This, in turn, reduces scattering of U ions when measuring Pu in the high-energy components of the AMS system. This instrumental reduction of U is advantageous in cases that require rapid Pu analyses as it simplifies the chemistry of Pu/U separation and other steps in the sample processing. In this procedure, Pu can be co-precipitated with another element as a fluoride, which is then mixed with a sufficient amount of PbF{sub 2} powder to form a sputter target. A series of tests were carried out and NdF{sub 3} was identified as one such suitable carrier. Measurements of Pu{sup +3} at {approx}0.85 MV terminal voltage showed that the {sup 239,240,241,242}Pu isotopes can be detected with a manageably low background, high efficiency and a 1 fg detection limit. Preliminary tests were carried out using the existing IsoTrace AMS system, modified only by the addition of electronic controls to automatically adjust the terminal voltage and all high-energy electric analyzers, along with the injection magnet bouncer. However, both the injection and detection systems were not designed for this task, so considerable room is available for reducing the detection limit into the ag range with modern AMS systems - such as the one being commissioned at University of Ottawa.

  16. Analysis Method of 241Pu Radioactivity by Isotope Dilution-Extraction Liquid Scintillation Spectrometer

    Institute of Scientific and Technical Information of China (English)

    2008-01-01

    <正>241Pu is the only pure β emitter with the maximum energy of 20.81 keV in plutonium isotopes of 238Pu, 239Pu, 240Pu and 242Pu, in which 241Pu is mostly specific radioactivity because its half-life is 14.29 a.

  17. Self-irradiation of Pu, its alloys and compounds

    Science.gov (United States)

    Timofeeva, L. F.

    2000-07-01

    Self-irradiation of Pu, its alloys and compounds by products of known α-decomposition is a continuous complicated process, which includes numerous different phenomena. The accumulation of Pu decomposition products causes material structure and properties change. This problem is the subject of many works, most of them concerned with the behavior of Pu and its alloys at low (liquid He and N) temperatures. The survey is given of the results of our experiments connected with radiogenic helium behavior, crystal structure and properties of Pu metallic compounds and Pu oxide ceramics in a self-irradiation process at room temperature under isochronal heat treatments.

  18. Comparison of the ENDF/B-V and SOKRATOR evaluations of 235U, 239Pu, 240Pu and 241Pu at low neutron energies

    International Nuclear Information System (INIS)

    The US and USSR's most recent evaluationsof 235U, 239Pu, 240Pu and 241Pu are compared over the thermal region and over the first few resonances. The two evaluations rest on essentially the same experimental data base and the differences reflect different approaches to the representation of the cross sections or different weightings of the experimental results. It is found that over the thermal and resolved ranges the two evaluations are very similar. Some differences in approaches are briefly discussed

  19. PuMa-ECR ion source operation

    International Nuclear Information System (INIS)

    The PuMa (Pulsed Magnetic field)-ECR ion source uses a pulsed solenoid coil to improve the peak current by opening the magnetic bottle along the beam axis. After demonstration of the principle of the pulsed magnetic extraction, the ion source was tested with different gases. We got promising results from helium up to krypton. For xenon the enhancement of the analyzed current was only in the same order as the enhancement of the afterglow. The influence of the current in the pulsed coil on the analyzed ion current was measured. With increased current levels in the pulsed coil the pulse height of the PuMa-pulse increases within the given pulse length of the coil. By using the pulsed coil the maximum of the charge state distribution can be shifted to higher charge states. (author)

  20. Artificial radioactivity and marine environment. Study of 238Pu, 239Pu+240Pu, 241Pu and 241Am in the Mediterranean sea

    International Nuclear Information System (INIS)

    This paper is in two parts. Part one is about the methods for analyzing transuranium elements particularly the development of an analytical process for plutonium and for perfecting an Americium analyzing method, capable of treating samples of 200 litres of sea water, 100 grams of sediment and 100 grams of biological matter. Part two concerns the in situ determinations carried out within the scope of the study on the distribution and behaviour of transuranium elements in the Mediterranean sea. The high sea studies concerned the effects of atmospheric fall out and the vertical distribution of Pu and Am. Studies along the coasts enabled a quantitative study to be made of the contribution of rivers to the Mediterranean and to study the distribution of Pu along the French Mediterranean coast line

  1. Ingestion intake of fallout Pu in Japan

    International Nuclear Information System (INIS)

    Ingestion intakes of fallout Pu throughout Japan in the 1959-1962 and 1978-1980 periods were measured by analyzing composite samples of each foodstuff or duplicate composite food samples consumed by five persons for a period of 1 d. Cumulative ingestion intake in Tokyo for the period from 1954-1980 was estimated by regression analysis. The cumulative ingestion intake, calculated by simple regression analysis between the natural log of the intake and that of annual fallout deposition of Pu, was estimated to be 450 pCi. Calculated by a multiple regression analysis, including the natural log of annual fallout deposition rates for a previous year as an additional independent variable, it was estimated to be 600 pCi. Considering in combination an ingestion intake, the value of which is calculated by the multiple regression analysis; an absorption ratio from the gastrointestinal tract of 0.001 (a recently reported value for low-level soluble Pu independent of chemical form); and the metabolic model in ICRP Publication 30, it is possible to estimate that the contribution of ingestion intake to liver and bone burden would be approximately 30%

  2. Effect of cross-link density and hydrophilicity of PU on blood compatibility of hydrophobic PS/hydrophilic PU IPNs.

    Science.gov (United States)

    Roh, H W; Song, M J; Han, D K; Lee, D S; Ahn, J H; Kim, S C

    1999-01-01

    To investigate the effect of the hydrophilic and hydrophobic microdomain structure on blood compatibility, a series of interpenetrating polymer networks (IPNs) composed of hydrophilic polyurethane (PU) and hydrophobic polystyrene (PS) was prepared. One series was prepared with varying cross-link densities of each network, the other with varying hydrophilicity of the PU component. All PU/PS IPNs exhibited microphase-separated structures that had dispersed PS domains in the continuous PU matrix. The domain size decreased with decreasing the hydrophilicity of the PU component and increasing the cross-link density of each network. As the cross-link density and hydrophobicity of the PU component was increased, an inward shift of Tgs was observed, which was due to the decrease in phase separation between the hydrophobic PS component and hydrophilic PU component. In the in vitro platelet adhesion test, as the microdomain size of PU/PS IPN surface decreased, the number of adhered platelets on the PU/PS IPN surface was reduced and deformation of the adhered platelets decreased. It could be concluded that blood compatibility of PU/PS IPN was mainly affected by the degree of mixing between PU and PS component, which was reflected by the domain size of PS rich phase. PMID:10091927

  3. Optical properties of PuO2 and α-Pu2O3 by GGA + U + QA studies

    Science.gov (United States)

    Yang, Yu; Lu, Yong; Zhang, Ping

    2014-09-01

    By performing first-principles calculations plus quasi-annealing simulations, we systematically study the ground-state electronic and optical properties for PuO2 and α-Pu2O3. We find that α-Pu2O3 has an energy band gap of 1.38 eV. Our obtained atomic and electronic structures for the two plutonium oxides are in agreement with available experimental as well as other theoretical results. Based on the ground-state electronic structures, we systematically calculate the frequency dependent dielectric functions, as well as the optical spectra for α-Pu2O3 and PuO2. It is found that at the visible light frequency range, the adsorption coefficient of α-Pu2O3 and PuO2 are similar, but their refractive indexes differ much. This difference can be used to detect or trace the oxidation products of the plutonium surfaces.

  4. 238Pu and 239+240Pu activities in lower Rhone valley in cultivated soils

    International Nuclear Information System (INIS)

    Measured 238Pu and 239+240Pu activities in French soils can be explained by the fallout from atmospheric nuclear tests and the disintegration of a US nuclear reactor satellite in 1964. However, some soil samples from the lower Rhone valley show higher mass activities, due to the Marcoule nuclear fuel reprocessing plant discharges. Soil samples from the Camargue, flooded in 1993 and 1994, where Rhone River sediments have been deposited, contain Pu from liquid effluents released by the nuclear plant. Seven samples taken near the nuclear facility show a direct influence by its atmospheric releases. Samples from soils irrigated with Rhone River water for 30 years do not show any activity significantly higher than regional means. (authors)

  5. Pu-241 in samples of forest soil from Poland

    International Nuclear Information System (INIS)

    241Pu activity measurements in coniferous forest soil samples from Poland are presented. The results were obtained in two ways: by alpha spectrometric remeasurements of the plutonium sources 3-4 years after their preparation (i.e. by the 241Am ingrowth) and by direct measurements of 241Pu using liquid scintillation (LS) spectrometry. Both methods gave consistent results. The maximum observed activity concentration obtained by the 241Am ingrowth was (254±43) Bq/kg, and by direct measurements it was (284±31) Bq/kg (the same sample, activities calculated for May 1, 1986). Enhanced levels of 241Pu were observed in all samples from the farthest north-eastern Poland. The estimated 241Pu maximum deposition from Chernobyl fallout in this area (sum of deposition for two examined layers of one site) was (1.025±0.110) kBq/m2. This will result after 70 years in an additional 241Am activity of about (30.1±3.2) Bq/m2. The average ratio for 241Pu to total 238,239,240Pu was of the order of 25. The obtained average Chernobyl ratios for 241Pu to 239,240Pu were about 86, and those for 241Pu to 238,239,240Pu were 56

  6. Speciation and unusual reactivity in PuO2+x.

    Science.gov (United States)

    Conradson, Steven D; Begg, Bruce D; Clark, David L; Den Auwer, Christophe; Espinosa-Faller, Francisco J; Gordon, Pamela L; Hess, Nancy J; Hess, Ryan; Keogh, D Webster; Morales, Luis A; Neu, Mary P; Runde, Wolfgang; Tait, C Drew; Veirs, D Kirk; Villella, Phillip M

    2003-06-16

    Pu L(3) XAFS measurements show that the excess oxygen in single phase PuO(2+)(x)() occurs as oxo groups with Pu-O distances of 1.83-1.91 A. This distance and the energy of the edge (via comparison with a large number of related compounds) are more consistent with a Pu(IV/V) than a Pu(IV/VI) mixture. Analogous to Pu(IV) colloids, although the Pu-Pu pair distribution remains single site even when it shows substantial disorder, the Pu-O distribution can display a number of additional shells at specific distances up to 3.4 A even in high fired materials when no oxo groups are present, implying intrinsic H(+)/OH(-)(/H(2)O). The number of oxo atoms increases when samples are equilibrated with humid air at ambient temperature, indicating that the Pu reactivity in this solid system differs notably from that of isolated complexes and demonstrating the importance of nanoscale cooperative phenomena and total free energy in determining its chemical properties. PMID:12793805

  7. Studies of U-Pu-C-Ti compounds

    International Nuclear Information System (INIS)

    The U-Pu-C-Ti compounds (5 to 20 atoms per cent Ti) have been studied in order to improve some properties of U-Pu-C carbides and to extend the existence field of the (U, Pu) C phase. The Pu/(U+Pu) ratio has been fixed to 15 per cent. All the alloys were elaborated and cast in an arc furnace. A two-phases field (U, Pu) C + Ti C exists which permits to avoid di- and sesqui-carbides and the (U, Pu) phase. An eutectic between (U, Pu) C and Ti C was found around 15 atoms per cent Ti. Practically the whole of the titanium is in Ti C form, titanium solubility in (U, Pu) C being inferior to 1 atom per cent. The most promising alloy are those containing two phases: (U, Pu) C+ Ti C. In comparison with the (U, Pu) C phase, titanium addition does not change very much the thermal expansion coefficients nor the thermal cycling behaviour between 160 and 1000 Celsius degrees which is excellent. On the other hand atmospheric corrosion behaviour is improved; compatibility with stainless steel is better; thermal conductivity, calculated from electrical resistivity K is enhanced: for U(0.85)-Pu(0.15)-C alloy we have K 0.179 W/cm.C at 1000 C and K = 0.187 W/cm.C at 1500 C, for U-Pu-C-Ti (10 atoms % Ti) alloy we have K = 0.193 W/cm.C at 1000 C and K = 0.205 W/cm.C at 1500 C. (author)

  8. Direct reduction of 238PuO2 and 239PuO2 to metal

    International Nuclear Information System (INIS)

    The process for reducing 700 g 239PuO2 to metal is a standard procedure at Los Alamos National Laboratory. This process is based on research for reducing 200 g 238PuO2 to metal. This report describes in detail the experiments and development of the 200-g process. The procedure uses calcium metal as the reducing agent in a molten CaCl2 solvent system. The process to convert impure plutonia to high-purity metal by oxide reduction followed by electrorefining is also described

  9. The evaluation of the mass distribution data for 238U, 239Pu and 242Pu fission

    International Nuclear Information System (INIS)

    The mass distribution data for 238U at En=1.5, 5.5, 8.3, 11.3, 14.9, 22.0, 27.5, 50.0, 99.5, 160.0 MeV, Ep=20.0, 60.0 MeV 239Pu at En=0.17, 7.9, 14.5 MeV and 242Pu at En=15.1 MeV were evaluated and recommended based on the main available experimental data up to now. The experimental data were make necessary corrections and their errors were also made necessary adjustments. The problems concerned were discussed

  10. Investigation on U - O - Na, Pu - O - Na and U,Pu - O - Na phase diagrams

    International Nuclear Information System (INIS)

    The thermochemical interaction between the nuclear fuel (uranium and plutonium mixed oxides) and the sodium has been investigated and particularly the three phase diagrams: U - O - Na; Pu - O - Na; U,Pu - O - Na. High temperature neutron diffraction, microcalorimetry and powder X-ray diffraction were used for the characterization of the compounds synthetized. This study allowed to complete the knowledge about each of these diagrams and to measure some physical and thermal properties on the compounds. The limits on the modelization of the fuel-sodium interaction are discussed from the results of the UO2 - Na reaction

  11. 238Pu and 239240Pu distribution in fish and invertebrates from the Great Miami River, Ohio

    International Nuclear Information System (INIS)

    Samples of minnows, shad, goldfish, carp, crayfish, and clams were taken from the Great Miami River in the vicinity of Miamisburg, Ohio. Activities of 238Pu and 239,240Pu are reported for these organisms. In addition, distributions were determined for plutonium between the gastrointestinal tract and the remainder of the organism in carp and between the shell and soft parts of crayfish. The results are discussed with regard to the spatial distribution of the organisms around Miamisburg and the tissue distribution within the animals

  12. The concentrations of 241Pu in the southern Baltic Sea

    Directory of Open Access Journals (Sweden)

    Strumińska-Parulska D. I.

    2013-04-01

    Full Text Available The aim of the work was 241Pu activities determination in different components (water, plankton and fish of the southern Baltic Sea ecosystem. The determination of 241Pu in the samples was done indirectly by activity measuring the increment in 241Am from the decay of β-emitting 241Pu in samples collected 10-15 years after the Chernobyl accident. Enhanced levels of 241Pu were observed in all analyzed Baltic samples. The plutonium is also non-uniformly distributed between the organs and tissues of the analyzed fish; especially pelagic herring and cod as well as benthic flounder. The annual individual effective doses calculated on the basis of 241Pu concentrations in fish indicated that the impact of the consumption of 241Pu with Baltic fish on the annual effective dose for a statistical inhabitant of Poland was very small.

  13. Adsorption behavior of 239Pu by Gaomiaozi bentonite

    International Nuclear Information System (INIS)

    Adsorption behavior of 239Pu by Gaomiaozi bentonite as a function of the factors of aqueous phase pH value, 239Pu initial concentration and ionic species is studied by static adsorption experiments in this paper. The following results are obtained. Adsorption equilibrium time of 239Pu by Gaomiaozi bentonite samples is about 24 h, and the adsorption distribution ratio Kd value of 239Pu increases with the pH value, but decreases with increasing initial concentration of 239Pu. And adsorption of 239Pu by bentonite samples with different ionic species show that anions affect the most on adsorption of bentonite is CO32-, followed by HCO3- and SO42-, whereas Cl- and NO3- hardly have any influence on the adsorption of bentonite. (authors)

  14. Metal-carbide multilayers for molten Pu containment

    International Nuclear Information System (INIS)

    Multilayers composed of nine or ten alternating layers of Ta or W and TaC were studied for the feasibility of their use in containing molten plutonium (Pu) at 1200 degrees C. Single layers of W and TaC were also investigated. A two-source electron beam evaporation process was developed to deposit these coatings onto the inside surface of hemispherical Ta cups about 38 mm in diameter. Pu testing was done by melting Pu in the coated hemispherical cups and holding them under vacuum at 1200 degrees C for two hours. Metallographic examination and microprobe analysis of cross sections showed that Pu had penetrated to the Ta substrate in all cases to some extent. Full penetration to the outer surface of the Ta substrate, however, occurred in only a few of the samples. The fact that full penetration occurred in any of the samples suggests that it would have occurred in uncoated Ta under these testing conditions which in turn suggests that the multilayer coatings do afford some protection against Pu attack. The TaC used for these specimens was wet by Pu under these testing conditions, and following testing, Pu was found uniformly distributed throughout the carbide layers which appeared to be rather porous. Pu was seen in the W and Ta layers only when exposed directly to molten Pu during testing or near defects suggesting that Pu penetrated the multilayers at defects in the coating and traveled parallel to the layers along the carbide layers. These results indicate that the use of alternating metal and ceramic layers for Pu containment should be possible through the use of nonporous ceramic that is not wet by molten Pu and defect-free films

  15. Delayed neutron yield of 238U and 241Pu

    International Nuclear Information System (INIS)

    The total delayed neutron yield for 238U and 241Pu were observed as a function of the incident neutron energy. The measurements extend from 2.5 to 5 MeV for 238U and from 0.15 to 5 MeV for 241Pu. The average ratio of the 241Pu delayed neutron yield to that of 238U is 0.292 +- 0.022

  16. Study of U - Pu - Fe alloys (Masurca critical experiment)

    International Nuclear Information System (INIS)

    Three compositions have been studied: 73.5 U - 25 Pu - 1.5 Fe (weight %) 74 U - 25 Pu - 1 Fe 74.5 U - 25 Pu - 0.5 Fe Elaboration and Casting are easy. After two weeks in air 74.5 U - 25 Pu - 0.5 Fe alloys are reduced in powder. As-cast alloys containing 1 and 1,5% Fe are kept undamaged during several months. A rapid oxidisation of the alloys is however observed when the samples undergo the phase transformation (at 595 deg. C and 590 deg. C respectively). Ignition tests in the presence of air show that the oxidisation starts at about 250 deg. C and that the reaction does not spread. Ignition is not observed during heating from 20 to 660 deg. C. The transformation temperature, the melting temperature and the thermal expansion coefficients have been determined by dilatometry. Below the transformation temperature, the principal phases are U-Pu zeta and (U, Pu)6Fe. Thermal conductibility, Young modulus, density and heat of fusion have been measured. Compatibility tests show that between U-Pu-Fe and stainless steel a phase of (U, Pu)6Fe type is formed. The 74 U - 25 Pu - 1% Fe alloy seems to behave better than 73.5 U - 25 Pu - 1.5% Fe alloy because the (U, Pu)6Fe layer is two or three times smaller. Finally, the thermal stability has been studied with the 74 U - 25 Pu - 1% Fe alloy. A dilatometric anomaly (very weak expansion) occurs when the sample is heated above transformation temperature and cooled. But there is no anomaly by thermal cycling from 50 deg. C to 400 deg. C and there is no deterioration of alloys by heat treatments at 100 deg. C, 200 deg. C, 300 deg. C during 5 months under vacuum. (authors)

  17. Gamma-ray intensities of 239Pu

    International Nuclear Information System (INIS)

    Relative intensities of 239Pu γ-rays were precisely measured with a Ge(Li) detector which was accurately calibrated and corrections were made for self-absorption of γ-rays. Accuracies of 1-2% were obtained for strong γrays. Detector efficiences were calibrated with a standard source of 133Ba and γ-ray sources of 152Eu, 154Eu and 182Ta. Intensities per decay were determined by the measured γ-ray intensities, weight and isotopic abundance of plutonium in the source. (author)

  18. Homogeneous oxalate precipitation of Pu(III)

    International Nuclear Information System (INIS)

    This paper reports on homogeneous oxalate precipitation using diethyl oxalate which was compared to precipitating Pu(III) oxalate with solid oxalic acid. The diethyl oxalate technique at 75 degrees C is better because it gives 50% less plutonium in the filtrate with a reasonable filtering time. Also, the procedure for the homogeneous precipitation is easier to automate because the liquid diethyl oxalate is simpler to introduce into the precipitator than solid oxalic acid. It also provides flexibility because the hydrolysis rate and therefore the precipitation rate can be controlled by varying the temperature

  19. 238Pu surface contamination of MHW impact shell assembly

    International Nuclear Information System (INIS)

    238PuO2 contamination of the grit blasted surface of the primary impact shell assembly (PISA) of the multi-hundred watt isotopic heat source was measured. The study determined the amount and distribution of the 238PuO2 and characterization of its behavior during aging at 13500C. The results concluded that normal decontamination effectively removes the superficial 238PuO2 but does not extract the 238PuO2 which is deep within the grit blasted structure. Subsequent heating results in migration of microcurie amounts of plutonium out of the grit blasted structure

  20. Ferro- and antiferro-magnetism in (Np, Pu)BC

    International Nuclear Information System (INIS)

    Two new transuranium metal boron carbides, NpBC and PuBC, have been synthesized. Rietveld refinements of powder XRD patterns of (Np,Pu)BC confirmed in both cases isotypism with the structure type of UBC. Temperature dependent magnetic susceptibility data reveal antiferromagnetic ordering for PuBC below TN = 44 K, whereas ferromagnetic ordering was found for NpBC below TC = 61 K. Heat capacity measurements prove the bulk character of the observed magnetic transition for both compounds. The total energy electronic band structure calculations support formation of the ferromagnetic ground state for NpBC and the antiferromagnetic ground state for PuBC

  1. Effect of equilibration time on Pu desorption from goethite

    International Nuclear Information System (INIS)

    It has been suggested that strongly sorbing ions such as plutonium may become irreversibly bound to mineral surfaces over time which has implications for near- and far-field transport of Pu. Batch adsorption-desorption data were collected as a function of time and pH to study the surface stability of Pu on goethite. Pu(IV) was adsorbed to goethite over the pH range 4.2 to 6.6 for different periods of time (1, 6, 15, 34 and 116 d). Following adsorption, Pu was leached from the mineral surface with desferrioxamine B (DFOB), a complexant capable of effectively competing with the goethite surface for Pu. The amount of Pu desorbed from the goethite was found to vary as a function of the adsorption equilibration time, with less Pu removed from the goethite following longer adsorption periods. This effect was most pronounced at low pH. Logarithmic desorption distribution ratios for each adsorption equilibration time were fit to a pH-dependent model. Model slopes decreased between 1 and 116 d adsorption time, indicating that overall Pu(IV) surface stability on goethite surfaces becomes less dependent on pH with greater adsorption equilibration time. The combination of adsorption and desorption kinetic data suggest that non-redox aging processes affect Pu sorption behavior on goethite.

  2. Pu vector sensitivity study for a Pu burning fast reactor. Pt. 2. Rod worth assessment and design optimization

    International Nuclear Information System (INIS)

    This study was based on a 'pancake' type fast reactor core design of 600 MW(e), which had been optimized for Pu burning with a feed Pu vector appropriate to once-through irradiation of MOX fuel in a PWR. The purpose of the study was to investigate the effects of varying the Pu vector, examining various methods of offsetting the effects of such a change, and finally to produce fuel cycles optimized for the different qualities of Pu vector within the same basic design. In addition to the reference (once-through) Pu vector, two extreme Pu vectors were examined: high quality Pu from military stockpiles; low quality Pu corresponding to the equilibrium point of multiple recycling in a Pu burning fast reactor. Variations in Pu quality were overcome by changing the fuel inventory - replacing some of the fuel by diluent material, and altering the fuel pin size. Using absorber material (10B4C) as diluent improves the rod worth shutdown margin but degrades the Na void and Doppler safety parameters, a non-absorber diluent has the opposite effects, so a mix of the 2 material types was used to optimize the core characteristics. Of the non-absorber diluent materials examined, ZrH gave significantly better performance than all others; 11B4C was the second choice for non-absorber diluent, because of its compatibility with 10B4C absorber. It was not possible to accommodate the lower quality (multi-recycled) Pu vector without a significant increase in the fuel pin volume. It was not generally possible, especially with the increased fuel pin size, to achieve positive rod worth shutdown margins - this was overcome by increasing the number of control rods. For the higher quality Pu vectors to maintain ratings within limits, it was necessary to adopt hollow fuel pellets, or else to use the diluent material as an inert matrix in the fuel pellets. (J.P.N.)

  3. 239Pu(n,2n) 238Pu cross section inferred from IDA calculations and GEANIE measurements

    Energy Technology Data Exchange (ETDEWEB)

    Chen, H; Ormand, W E; Dietrich, F S

    2000-09-01

    This report presents the latest {sup 239}Pu(n,2n){sup 238}Pu cross sections inferred from calculations performed with the nuclear reaction-modeling code system, IDA, coupled with experimental measurements of partial {gamma}-ray cross sections for incident neutron energies ranging from 5.68 to 17.18 MeV. It is found that the inferred {sup 239}Pu(n,2n){sup 238}Pu cross section peaks at E{sub inc} {approx} 11.4 MeV with a peak value of approximately 326 mb. At E{sub inc} {approx} 14 MeV, the inferred {sup 239}Pu(n,2n){sup 238}Pu cross section is found to be in good agreement with previous radio-chemical measurements by Lockheed. However, the shape of the inferred {sup 239}Pu(n,2n){sup 238}Pu cross section differs significantly from previous evaluations of ENDL, ENDF/B-V and ENDF/B-VI. In our calculations, direct, preequilibrium, and compound reactions are included. Also considered in the modeling are fission and {gamma}-cascade processes in addition to particle emission. The main components of physics adopted and the parameters used in our calculations are discussed. Good agreement of the inferred {sup 239}Pu(n,2n){sup 238}Pu cross sections derived separately from IDA and GNASH calculations is shown. The two inferences provide an estimate of variations in the deduced {sup 239}Pu(n,2n){sup 238}Pu cross section originating from modeling.

  4. Plutonium destruction with pebble bed type HTGRs using Pu burner balls and breeder balls

    International Nuclear Information System (INIS)

    It was made clear that pebble bed type HTGRs using Pu burner balls (pu balls) and breeder balls (Th balls) possesses a potential to burn weapons-grade Pu to 740 Gwd/TPu. The total amounts of Pu and 239Pu of can reduced to about 20 and 1%, respectively. (author). 10 refs, 4 figs, 2 tabs

  5. U, Pu, and Am nuclear signatures of the Thule hydrogen bomb debris

    DEFF Research Database (Denmark)

    Eriksson, Mats; Lindahl, Patric; Roos, Per;

    2008-01-01

    ). In the five hot particles examined, the measured uranium atomic ratio was U-235/U-238 = 1.02 +/- 0.16 and the Pu-isotopic ratios were as follows: Pu-240/Pu-239 0.0551 +/- 0.0008 (atom ratio), Pu-238/Pu239+240 = 0.0161 +/- 0.0005 (activity ratio), Pu-241/Pu239+240 = 0.87 +/- 0.12 (activity ratio), and Am-241...... than one Pu source involved in the accident, confirming earlier studies. The Pu-238/Pu239+240 activity ratio and the Pu-240/Pu-239 atomic ratio were divided into at least two Pu-isotopic ratio groups. For both Pu-isotopic ratios, one ratio group had identical ratios as the five hot particles described...... above and for the other groups the Pu isotopic ratios were lower (Pu-238/Pu239+240 activity ratio similar to 0.01 and the Pu-240/Pu-239 atomic ratio 0.03). On the studied particles we observed that the U/Pu ratio decreased as a function of the time these particles were present in the sediment. We...

  6. Fission Cross-Section Measurements on Pu239, Pu241 , U232, and a Search for Fission Components in Pu238 Resonances

    International Nuclear Information System (INIS)

    Fission cross-section measurements on Pu239 and Pu241 have been carried out from sub-thermal-neutron energy to the keV region; resonance parameters are given and errors in the average values of the cross-section are discussed. The discovery of large fission components in the U232 neutron resonances stimulated a search for fission components in Pu238. The results of these experiments are given. All the measurements were performed on the Harwell time-of-flight spectrometer. (author)

  7. Evaluation of fission cross sections and covariances for {sup 233}U, {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu

    Energy Technology Data Exchange (ETDEWEB)

    Kawano, Toshihiko [Kyushu Univ., Fukuoka (Japan); Matsunobu, Hiroyuki [Data Engineering, Inc. (Japan); Murata, Toru [AITEL Corporation, Tokyo (JP)] [and others

    2000-02-01

    A simultaneous evaluation code SOK (Simultaneous evaluation on KALMAN) has been developed, which is a least-squares fitting program to absolute and relative measurements. The SOK code was employed to evaluate the fission cross sections of {sup 233}U, {sup 235}U, {sup 238}U, {sup 239}Pu, {sup 240}Pu, and {sup 241}Pu for the evaluated nuclear data library JENDL-3.3. Procedures of the simultaneous evaluation and the experimental database of the fission cross sections are described. The fission cross sections obtained were compared with evaluated values given in JENDL-3.2 and ENDF/B-VI. (author)

  8. Is Octavalent Pu(VIII) Possible? Mapping the Plutonium Oxyfluoride Series PuO(n)F(8-2n) (n = 0-4).

    Science.gov (United States)

    Huang, Wei; Pyykkö, Pekka; Li, Jun

    2015-09-01

    While the oxidation state Pu(VIII) is shown to be less stable than Pu(V) in the PuO4 molecule, it is not clear if the more electronegative fluorine can help to stabilize Pu(VIII). Our calculations on PuO(n)F(8-2n) (n = 0-4) molecules notably confirm that PuO2F4 has both (1)D(4h) and (5)C(2v) minima with the oxidation states Pu(VIII) and Pu(V), respectively, with the latter having lower energy. The hybrid-DFT, CCSD(T), and CASSCF methods all give the same result. The results conform to a superoxide ligand when n ≥ 2. PuF8 in a (1)O(h) state can decompose to PuF6 and F2, and PuOF6 in a (1)C(2v) state also can break down to PuF6 and 1/2 O2. The Pu(VIII) anion PuO2F5(-) does have a D(5h) minimum, which also lies above a (5)C(2v) Pu(V) peroxide structure. However, the energy differences between the different minima are not large, indicating that metastable species with oxidation states higher than Pu(V) cannot be completely excluded. PMID:26309065

  9. Procedure for plutonium determination using Pu(VI) spectra

    International Nuclear Information System (INIS)

    This document describes a simple spectrophotometric method for determining total plutonium in nitric acid solutions based on the spectrum of Pu(VI). Plutonium samples in nitric acid are oxidized to Pu(VI) with Ce(IV) and the net absorbance at the 830 nm peak is measured

  10. Ceramic grade (U,Pu)O2 powder fabrication

    International Nuclear Information System (INIS)

    Ceramic grade UO2 powder was obtained by the homogeneous precipitation method. This procedure was afterwards applied to the fabrication of ceramic grade (U,Pu)O2 powders, and mixed oxide powders with Pu content ranging from 0.7 to 16% were obtained. The obtainment of mixed ceramic oxides as well as the recuperation of fabrication scraps were developed in three steps: 1)study of the process of homogeneous precipitation of ammonium diuranate (ADU); 2) co-precipitation of ADU/PuO2.H2O for Pu concentrations of 0.6 and 6.8; 3) the thermal conditioning to mixed oxide (U,Pu)O2 powders. The experimental procedure involves the following steps: preparation of the PuO2(NO3)4 solution; co-precipitation of the PuO2(NO3)2 solution with an UO2(NO3)2 solution; filtration and drying of the precipitate, thermal treatment and finally, mixing, pressing and sintering of the (U,Pu)O2 and Nukem UO2 powder with a 0. of zinc stearate. Different controls were made by means of physical, chemical and ceramographic tests. This method can be used for the fabrication of fast reactor fuels or, previous mechanical dispersion in UO2 powder, for the fabrication of thermal reactors fuels. (M.E.L.)

  11. Structure and potential energy function for Pu22+ ion

    International Nuclear Information System (INIS)

    The theoretical study on Pu22+ using density functional method shows that the molecular ion is metastable. Ground electronic state is 13Σg for Pu22+, the analytic potential energy function is in well agreement with the Z-W function, and the force constants and spectroscopic data have been worked out for the first time

  12. MGA Analysis on Elevated {sup 238}Pu Samples

    Energy Technology Data Exchange (ETDEWEB)

    Wang, T F; Moody, K J; Raschke, K E; Ruhter, W D

    2002-03-28

    Plutonium gamma-ray data analysis, in the 100-keV region, using MGA has been improved to overcome the original maximum limit of 2% {sup 238}Pu relative plutonium content in a sample in order perform an analysis. MGA analysis results of elevated {sup 238}Pu samples are compared to the results from mass spectrometry.

  13. Pu-238 fuel form activities, January 1-31, 1981

    Energy Technology Data Exchange (ETDEWEB)

    1981-02-01

    This monthly report for /sup 238/Pu Fuel Form Activities has two main sections: SRP-PuFF facility and SRL Fuel Form Activities. The program status, budget information, and milestone schedules are discussed in each main section. The Work Breakdown Structure (WBS) for this program is shown. Only one monthly report per year is processed for EDB.

  14. PU.1 silencing leads to terminal differentiation of erythroleukemia cells

    International Nuclear Information System (INIS)

    The transcription factor PU.1 plays a central role in development and differentiation of hematopoietic cells. Evidence from PU.1 knockout mice indicates a pivotal role for PU.1 in myeloid lineage and B-lymphocyte development. In addition, PU.1 is a key player in the development of Friend erythroleukemia disease, which is characterized by proliferation and differentiation arrest of proerythrocytes. To study the role of PU.1 in erythroleukemia, we have used murine erythroleukemia cells, isolated from Friend virus-infected mice. Expression of PU.1 small interfering RNA in these cells led to significant inhibition of PU.1 levels. This was accompanied by inhibition of proliferation and restoration in the ability of the proerythroblastic cells to produce hemoglobin, i.e., reversion of the leukemic phenotype. The data suggest that overexpression of PU.1 gene is the immediate cause for maintaining the leukemic phenotype of the disease by retaining the self-renewal capacity of transformed erythroblastic cells and by blocking the terminal differentiation program towards erythrocytes

  15. Np Analysis in IAT-Samples Containing <10 Microgram Pu

    International Nuclear Information System (INIS)

    A method for the determination of neptunium to plutonium in safeguards samples containing less than 10 microgram Pu is presented. The chemical treatment and the optimized measurement conditions for gamma spectrometry are reported. This method is based on thermal ionization mass spectrometry (TIMS) after chemical treatment and separation and was validated with mixtures of U, Pu and Np certified reference materials and using the 237Np standard addition method, followed by separation of the waste fraction and gamma spectrometric analysis. The highest sensitivity, precision and accuracy in the determination of the Np:Pu ratio at microgram levels of Pu is achieved by evaluating 241Pu and 233Pa after measuring the adsorbent with a well-type gamma detector 3 weeks after chemical treatment. The repeatability of determining the Np:Pu ratio is estimated to be 5%, the maximum uncertainty as determined from comparing the 4 measurement modes is within ± 10% for samples containing 3 μg Pu, while being within ± 20% for 0.4 μg Pu. (authors)

  16. Nuclear characteristics of Pu fueled LWR and cross section sensitivities

    Energy Technology Data Exchange (ETDEWEB)

    Takeda, Toshikazu [Osaka Univ., Suita (Japan). Faculty of Engineering

    1998-03-01

    The present status of Pu utilization to thermal reactors in Japan, nuclear characteristics and topics and cross section sensitivities for analysis of Pu fueled thermal reactors are described. As topics we will discuss the spatial self-shielding effect on the Doppler reactivity effect and the cross section sensitivities with the JENDL-3.1 and 3.2 libraries. (author)

  17. Performance of isotope correlations for the estimate of 242Pu

    International Nuclear Information System (INIS)

    Full text: The lack of a gamma-ray signature from 242Pu represents an Achilles heel for many plutonium isotope abundance measurements made by high-resolution gamma spectrometry (HRGS). This holds in particular for plutonium materials containing a significant fraction of this isotope. The problem is partially solved through the application of isotope correlations estimating the relative abundance of 242Pu from relations to ratios of other plutonium isotopes measurable by HRGS. In the mid of the nineties a new type of isotope correlation had been proposed for LWR plutonium based on the following relation: 242Pu/239Pu = C0·[238Pu/239Pu]c1 · [240Pu/239Pu]c2 with recommended coefficients C0, C1 and C2 for PWR and BWR fuels, respectively. We have adopted this type of correlation for the routine analysis of safeguards samples in the Euratom On-Site Laboratories and in the Institute for Transuranium Elements. In order to cover the full range of plutonium materials received for analysis, the application of the above correlation has been also extended to AGR and Magnox-type of plutonium. The differing sets of coefficients C0, C1 and C2 approximating best the correlation for the additional types of materials were determined from a set of reference isotopic data. Since in many instances the origin and the type of the plutonium are not known a priori, criteria for categorization were established helping to select the appropriate isotope correlation. Parametric plots of the ratios 238Pu/239Pu versus 240Pu/239Pu generally allow to discern unambiguously Magnox, AGR and LWR plutonium, and to some extent also BWR and PWR plutonium, as long as a mixing of the respective plutonium materials has not occurred. With this kind of categorization implemented in the routine analysis the performance of the 242Pu estimate is substantially improving in most cases. Performance data for 242Pu in particular, and for plutonium isotope abundance measurements by HRGS in general, as derived from a

  18. Spatial distribution of 241Am, 137Cs, 238Pu, 239,240Pu and 241Pu over 17 year periods in the Ravenglass saltmarsh, Cumbria, UK

    International Nuclear Information System (INIS)

    Ninety five surface scrape samples were collected at the Ravenglass saltmarsh and analysed for radionuclides by alpha spectrometry (238Pu and 239,240Pu), gamma spectrometry (241Am and 137Cs) and liquid scintillation counting (241Pu). Both 241Am and 137Cs activities are compared with those reported by Horrill [1983. Concentrations and spatial distribution of radioactivity in an ungrazed saltmarsh. In: Coughtrey, P.J. (Ed.), Ecological Aspects of Radionuclide Release. British Ecological Society Special Publication No. 3. Blackwell, Oxford, pp. 119-215.] Significant decreases in activities for both radionuclides were observed which is caused by the declining levels of discharges from the Sellafield nuclear reprocessing plant since the 1980s. It has been concluded that the spatial distribution of these radionuclides are controlled by the tidal currents and the clay contents in the sediments. There is evidence of surface erosion of the saltmarsh and redistribution of radionuclides in the saltmarsh using isotopic ratios of measured Pu.

  19. Sintering of (U,Pu)O2 pellets

    International Nuclear Information System (INIS)

    In this paper, results of sintering of UO2-PuO2 solid solutions are presented. Two processes are described: the first one is the standard process involving mechanically mixed oxides PuO2 and sinterable UO2, whereas in the second one direct mixtures of UO3 or U3O8 and PuO2 are pressed and sintered. For the two processes, sintering is carried out in flowing pure or dilute hydrogen at a temperature of 1650 deg. C during four hours. In both cases, the (U,Pu)O2 pellets have the same general characteristics (PuO2 ≅ 20 per cent): - a bulk density between 96 and 99 per cent of the theoretical density - a single phase product with grains of about 10 to 20 μ. - an oxygen to metal ratio varying between 2.00 and 1.95 according to the moisture content of the sintering atmosphere. (authors)

  20. Microscopic Calculations of 240Pu Fission

    Energy Technology Data Exchange (ETDEWEB)

    Younes, W; Gogny, D

    2007-09-11

    Hartree-Fock-Bogoliubov calculations have been performed with the Gogny finite-range effective interaction for {sup 240}Pu out to scission, using a new code developed at LLNL. A first set of calculations was performed with constrained quadrupole moment along the path of most probable fission, assuming axial symmetry but allowing for the spontaneous breaking of reflection symmetry of the nucleus. At a quadrupole moment of 345 b, the nucleus was found to spontaneously scission into two fragments. A second set of calculations, with all nuclear moments up to hexadecapole constrained, was performed to approach the scission configuration in a controlled manner. Calculated energies, moments, and representative plots of the total nuclear density are shown. The present calculations serve as a proof-of-principle, a blueprint, and starting-point solutions for a planned series of more comprehensive calculations to map out a large set of scission configurations, and the associated fission-fragment properties.

  1. Anomalous atomic volume of alpha-Pu

    DEFF Research Database (Denmark)

    Kollar, J.; Vitos, Levente; Skriver, Hans Lomholt

    1997-01-01

    We have performed full charge-density calculations for the equilibrium atomic volumes of the alpha-phase light actinide metals using the local density approximation (LDA) and the generalized gradient approximation (GGA). The average deviation between the experimental and the GGA atomic radii is 1.......3%. The comparison between the LDA and GGA results show that the anomalously large atomic volume of alpha-Pu relative to alpha-Np can be ascribed to exchange-correlation effects connected with the presence of low coordinated sites in the structure where the f electrons are close to the onset of...... localization. This effect is correctly described in the GGA but not in the LDA....

  2. Distinguishing Pu Metal from Pu Oxide and Determining alpha-ratio using Fast Neutron Counting

    Energy Technology Data Exchange (ETDEWEB)

    Verbeke, J. M. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Chapline, G. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Nakae, L. F. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Prasad, M. K. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Sheets, S. A. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Snyderman, N. J. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

    2015-01-07

    We describe a new method for determining the ratio of the rate of (α, n) source neutrons to the rate of spontaneous fission neutrons, the so called α-ratio. This method is made possible by fast neutron counting with liquid scintillator detectors, which can determine the shape of the fast neutron spectrum. The method utilizes the spectral difference between fission spectrum neutrons from Pu metal and the spectrum of (α, n) neutrons from PuO2. Our method is a generalization of the Cifarelli-Hage method for determining keff for fissile assemblies, and also simultaneously determines keff along with the α-ratio.

  3. CCRI(II) activity comparison of 241Pu: CCRI(II)-K2.Pu-241

    International Nuclear Information System (INIS)

    In 2010, seven laboratories took part in the CCRI(II) key comparison of activity concentration measurements of 241Pu, CCRI(II)-K2.Pu-241, using seven different methods. The spread of all results except one is 4 * 10-2 in relative terms. The results based on the CIEMAT/NIST efficiency tracing method are shown to be dependent on the beta spectrum shape selected and further work is proposed. The KCRV has been determined as the arithmetic mean of six independent results based on four different methods. The results of the comparison have been analysed with respect to the KCRV. The degrees of equivalence with the KCRV have been approved by the CCRI(II) and are published in the BIPM key comparison database. (authors)

  4. Thermal conductivity of hypostoichiometric low Pu content (U,Pu)O2-x mixed oxide

    International Nuclear Information System (INIS)

    The 'laser flash' method was used to measure the thermal diffusivity of PWR mixed oxide fuels with Pu contents ranging from 3 to 15 wt% and oxygen to metal ratio (O/M) ranging from 2.00 to ∼1.95. The temperature range extends from 700 to 2300 K. The fuel thermal conductivity is derived using heat capacity values of the mixed oxides calculated by Kopp's law from recommended values for the heat capacities of UO2, PuO2 and O2. We observe an effect of the deviation from stoichiometry on the conductivity smaller than what is recommended for high plutonium content FBR fuel. Our results are fitted in the low temperature range to a classical phonon transport model. Abeles's simplified theory of phonon diffusion by point defects is used to discuss the results. We propose a new thermal conductivity relation, which takes into account the effect of the O/M ratio

  5. Pu-238 Supply Program Project Execution Plan

    International Nuclear Information System (INIS)

    This Pu-238 Supply Program Project Execution Plan (PEP) summarizes critical information and processes necessary to manage the program. The PEP is the primary agreement regarding planning and objectives between The Department of Energy Office of Nuclear Energy (DOE NE-75), Oak Ridge National Laboratory Site Office (OSO) and the Oak Ridge National Laboratory (ORNL). The acquisition executive (AE) will approve the PEP. The PEP is a living document that will be reviewed and revised periodically until the project is complete. The purpose of the project is to reestablish the capability to produce plutonium-238 (Pu-238) domestically. This capability consists primarily of procedures, processes, and design information, not capital assets. As such, the project is not subject to the requirements of DOE O 413.3B, but it will be managed using the project management principles and best practices defined there. It is likely that some capital asset will need to be acquired to complete tasks within the project. As these are identified, project controls and related processes will be updated as necessary. Because the project at its initiation was envisioned to require significant capital assets, Critical Decision 0 (CD-0) was conducted in accordance with DOE O 413.3B, and the mission need was approved on December 9, 2003, by William Magwood IV, director of the Office of Nuclear Energy (NE), Science and Technology, DOE. No date was provided for project start-up at that time. This PEP is consistent with the strategy described in the June 2010 report to Congress, Start-up Plan for Plutonium-238 Production for Radioisotope Power Systems.

  6. The inflow of 238Pu and 239+240Pu from the Vistula River catchment area to the Baltic Sea

    International Nuclear Information System (INIS)

    The aim of the work was to estimate plutonium inflow from the Vistula River's catchments area to the Baltic Sea. There were differences in plutonium activities depending on season and sampling site. The highest activities of 238Pu and 239+240Pu were transported from the Vistula River watershed to the Baltic Sea in spring and the lowest in summer. Annually, the southern Baltic Sea is enriched via the Vistula River with 10.3 MBq of 238Pu and 89.0 MBq of 239+240Pu. The enhanced concentration of plutonium in water from the Vistula River is the result of its runoff from the Vistula drainage area, mostly from snowmelt, enhanced rainfalls and leached materials from river bed. - Highlights: → We estimated plutonium inflow from the Vistula River catchment area to the Baltic Sea. → We found differences in Pu activities depending on season and sampling site. → The highest amount of 239 + 240Pu was transported in spring and the lowest in summer. → Annually, the southern Baltic Sea is enriched with 89.0 MBq of 239 + 240Pu. → Enhanced Pu amount in water came from snowmelt, rainfalls and leached materials.

  7. Oxidation states, geometries, and electronic structures of plutonium tetroxide PuO4 isomers: is octavalent Pu viable?

    Science.gov (United States)

    Huang, Wei; Xu, Wen-Hua; Su, Jing; Schwarz, W H E; Li, Jun

    2013-12-16

    In neutral chemical compounds, the highest known oxidation state of all elements in the Periodic Table is +VIII. While PuO4 is viewed as an exotic Pu(+VIII) complex, we have shown here that no stable electronic homologue of octavalent RuO4 and OsO4 exists for PuO4, even though Pu has the same number of eight valence electrons as Ru and Os. Using quantum chemical approaches at the levels of quasi-relativistic DFT, MP2, CCSD(T), and CASPT2, we find the ground state of PuO4 as a quintet (5)C2v-(PuO2)(+)(O2)(-) complex with the leading valence configuration of an (f(3))plutonyl(V) unit, loosely coupled to a superoxido (π*(3))O2(-) ligand. This stable isomer is likely detectable as a transient species, while the previously suggested planar (1)D4h-Pu(VIII)O4 isomer is only metastable. Through electronic structure analyses, the bonding and the oxidation states are explained and rationalized. We have predicted the characteristics of the electronic and vibrational spectra to assist future experimental identification of (PuO2)(+)(O2)(-) by IR, UV-vis, and ionization spectroscopy. PMID:24274785

  8. Precision and accuracy in the determination of sup(238)Pu/(sup(239)Pu + sup(240)Pu) alpha activity ratio by alpha spectrometry

    International Nuclear Information System (INIS)

    Investigations were carried out for the evaluation of precision and accuracy in determining sup(238)Pu/(sup(239)Pu + sup(240)Pu) activity ratio by α spectrometry from the point of view of determining sup(238)Pu accurately in plutonium samples and in exploiting Isotope Dilution Alpha Spectrometry (IDAS) for determining the concentration of plutonium in the irradiated fuel dissolver solutions. Synthetic mixtures with α activity ratios ranging from 0.01 to 10 were prepared using sup(238)Pu and sup(239)Pu isotopes. Different methods which can be routinely used were tried to calculate the α activity ratio from the α spectrum taken on electrodeposited sources prepared from these mixtures. An accuracy of better than 0.5% and a precision of +- 0.2% (1 sigma) is demonstrated in the determination of α activity ratios ranging from 0.01 to 10 using electrodeposited sources and the evaluation method based on the geometric progression decrease (G.P.) for the far tail of the spectrum. (auth.)

  9. Pu(V) transport through Savannah River Site soils - an evaluation of a conceptual model of surface- mediated reduction to Pu (IV)

    International Nuclear Information System (INIS)

    Over the last fifteen years the Savannah River Site (SRS) in South Carolina, USA, was selected as the site of three new plutonium facilities: the Mixed Oxide Fuel Fabrication Facility, Pit Disassembly and Conversion Facility, and the Pu Immobilization Plant. In order to assess the potential human and environmental risk associated with these recent initiatives, improved understanding of the fate and transport of Pu in the SRS subsurface environment is necessary. The hypothesis of this study was that the more mobile forms of Pu, Pu(V) and Pu(VI), would be reduced to the less mobile Pu(III/IV) oxidation states under ambient SRS subsurface conditions. Laboratory-scale dynamic flow experiments (i.e., column studies) indicated that Pu(V) was very mobile in SRS sediments. At higher pH values the mobility of Pu decreased and the fraction of Pu that became irreversibly sorbed to the sediment increased, albeit, only slightly. Conversely, these column experiments showed that Pu(IV) was essentially immobile and was largely irreversibly sorbed to the sediment. More than 100 batch sorption experiments were also conducted with four end-member sediments, i.e., sediments that include the chemical, textural, and mineralogical properties likely to exist in the SRS. These tests were conducted as a function of initial Pu oxidation state, pH, and contact time and consistently demonstrated that although Pu(V) sorbed initially quite weakly to sediments, it slowly, over the course of <33 days, sorbed very strongly to sediments, to approximately the same degree as Pu(IV). This is consistent with our hypothesis that Pu(V) is reduced to the more strongly sorbing form of Pu, Pu(IV). These studies provide important experimental support for a conceptual geochemical model for dissolved Pu in a highly weathered subsurface environment. That is that, irrespective of the initial oxidation state of the dissolved Pu introduced into a SRS sediment system, Pu(IV) controls the environmental transport

  10. Interception and retention of 238Pu deposition by orange trees

    International Nuclear Information System (INIS)

    Radioisotope thermoelectric generators (RTG) transform the heat produced during the alpha decay of 238Pu into electrical energy for use by deep-space probes, such as the Voyager spacecraft, which have returned images and other data from Jupiter, Saturn and Uranus. Future missions involving RTGs may be launched aboard the space shuttle, and there is a remote possibility that an explosion of liquid-hydrogen and liquid-oxygen fuel could rupture the RTGs and disperse 238Pu into the atmosphere over central Florida. Research was performed to determine the potential transport to man of atmospherically dispersed Pu via contaminated orange fruits. The results indicate that the major contamination of oranges would result from the interception and retention of 238Pu deposition by fruits. The resulting surface contamination could enter human food chains through transfer to internal tissues during peeling or in the reconstituted juices and flavorings made from orange skins. The interception of 238Pu deposition by fruits is especially important because the results indicate no measurable loss of Pu from fruit surfaces through time or with washing. Approximately 1% of the 238Pu deposited onto an orange grove would be harvested in the year following deposition

  11. Measurement of the 242Pu neutron capture cross section

    Science.gov (United States)

    Buckner, M. Q.; Wu, C. Y.; Henderson, R. A.; Bucher, B.; Bredeweg, T. A.; Baramsai, B.; Couture, A.; Jandel, M.; Mosby, S.; O'Donnell, J. M.; Ullmann, J. L.; Chyzh, A.; Dance Collaboration

    2015-10-01

    Precision (n,f) and (n, γ) cross sections are important for the network calculations of the radiochemical diagnostic chain for the U.S. DOE's Stockpile Stewardship Program. 242Pu(n, γ) cross section is relevant to the network calculations of Pu and Am. Additionally, new reactor concepts have catalyzed considerable interest in the measurement of improved cross sections for neutron-induced reactions on key actinides. To date, little or no experimental data has been reported on 242Pu(n, γ) for incident neutron energy below 50 keV. A new measurement of the 242Pu(n, γ) reaction was performed with the DANCE together with an improved PPAC for fission-fragment detection at LANSCE during FY14. The relative scale of the 242Pu(n, γ) cross section spans four orders of magnitude for incident neutron energies from thermal to ~ 30 keV. The absolute scale of the 242Pu(n, γ) cross section is set according to the measured 239Pu(n,f) resonance at 7.8 eV; the target was spiked with 239Pu for this measurement. The absolute 242Pu(n, γ) neutron capture cross section is ~ 30% higher than the cross section reported in ENDF for the 2.7 eV resonance. Latest results to be reported. Funded by U.S. DOE Contract No. DE-AC52-07NA27344 (LLNL) and DE-AC52-06NA25396 (LANL). U.S. DOE/NNSA Office of Defense Nuclear Nonproliferation Research and Development. Isotopes (ORNL).

  12. Elastic properties of gamma-Pu by resonant ultrasound spectroscopy

    Energy Technology Data Exchange (ETDEWEB)

    Migliori, Albert [Los Alamos National Laboratory; Betts, J [Los Alamos National Laboratory; Trugman, A [Los Alamos National Laboratory; Mielke, C H [Los Alamos National Laboratory; Mitchell, J N [Los Alamos National Laboratory; Ramos, M [Los Alamos National Laboratory; Stroe, I [WORXESTER, MA

    2009-01-01

    Despite intense experimental and theoretical work on Pu, there is still little understanding of the strange properties of this metal. We used resonant ultrasound spectroscopy method to investigate the elastic properties of pure polycrystalline Pu at high temperatures. Shear and longitudinal elastic moduli of the {gamma}-phase of Pu were determined simultaneously and the bulk modulus was computed from them. A smooth linear and large decrease of all elastic moduli with increasing temperature was observed. We calculated the Poisson ratio and found that it increases from 0.242 at 519K to 0.252 at 571K.

  13. Uso de contraceptivos por puérperas adolescentes

    OpenAIRE

    Fernanda Schulz da Rosa; Diana Cecagno; Sonia Maria Könzgen Meincke; Simoní Saraiva Bordignon; Marilu Correa Soares; Ana Cândida Lopes Corrêa

    2014-01-01

    Objetivo: Indagar el uso de métodos contraceptivos por las puérperas adolescentes a fin de relacionar su (des)uso con el embarazo en la adolescencia. Método: Estudio transversal, descriptivo, realizado por medio de un instrumento estructurado con 181 puérperas adolescentes que tuvieron sus partos en el hospital participante de la investigación. Los datos fueron recolectados en el período de diciembre de 2008 a diciembre de 2009. Resultados: El 64,1% de las puérperas usaba algún método contrac...

  14. Determination of {sup 238}Pu, {sup 239+240}Pu, {sup 241}Pu and {sup 241}Am in radioactive waste from IPEN reactor

    Energy Technology Data Exchange (ETDEWEB)

    Geraldo, Bianca; Taddei, Maria Helena T.; Cheberle, Sandra M.; Ferreira, Marcelo T., E-mail: bgeraldo@cnen.gov.b, E-mail: mhtaddei@cnen.gov.b, E-mail: scsantos@cnen.gov.b, E-mail: ferreira@cnen.gov.b [Brazilian Nuclear Energy Commission (LAPOC/CNEN-MG), Pocos de Caldas, MG (Brazil). Lab. of Pocos de Caldas; Marumo, Julio T., E-mail: jtmarumo@ipen.b [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

    2011-07-01

    Ion exchange resin is a common type of radioactive waste arising from treatment of coolant water of the main circuit of research and nuclear power reactors. This waste contains high concentrations of fission and activation products. The management of this waste includes its characterization in order to determine and quantify specific radionuclides including those known as difficult-to-measure radionuclides (RDM). The analysis of RDMs generally involves expensive and time-consuming complex radiochemical analysis for purification and separation of the radionuclides. The objective of this work is to show an easy methodology for quantifying plutonium and americium isotopes in spent ion exchange resin, used for purification of the cooling water of the IEA-R1 reactor located at the Nuclear and Energy Research Institute, IPEN-CNEN/SP. The resins were destroyed by acid digestion, followed by purification and separation of the Pu and Am isotopes with anionic and chromatographic resins. {sup 238}Pu, {sup 239}+{sup 24}'0Pu, and {sup 24}'1Am isotopes were analyzed in an alpha spectrometer equipped with surface barrier detectors. {sup 241}Pu isotope was analyzed by liquid scintillation counting. Chemical recovery yield ranged from 73 to 98% for Pu and 77 to 98% for Am, demonstrating that the methodology is suitable for identification and quantification of the isotopes studied in spent resins. (author)

  15. Fission of 239Pu with resonance neutrons

    International Nuclear Information System (INIS)

    A measurement of fission fragment energy and mass distributions in the 239Pu(n,f) resolved resonance region has been performed applying the twin Frisch-gridded ionization chamber technique. An improved pile-up rejection system has been developed to cope with the strong α background. The results for the mass and mean total kinetic energy (TKE-bar) distributions for resolved resonances do not show any strong 'pattern' of fluctuations, unlike it was the case for 235U(n,f) in the same neutron energy region. This can be explained in the frame of existing theoretical models, according to which the only possible low-energy spin states available (Jπ=0+, 1+) belong to two well separated (∼1.25 MeV) transition state bands with given fission fragment properties. An anti-correlation between TKE-bar and ν-barp was found to be not significant. The obtained small spin dependence of TKE-bar of about 70 keV is in agreement with literature values. A slight correlation was found between TKE-bar versus 1/Γf. But also this was considered not to be significant. (author)

  16. Biosorption of 239Pu by immobilized sargassum fusiforme

    International Nuclear Information System (INIS)

    Sargassum fusiforme was immobilized with calcium alginates and its biosorption property to 239Pu was studied by batch and column methods. Biosorption equilibrium time of immobilized Sargassum fusiforme biosorbent to 239Pu is 120 min and biosorption efficiency is over 99.2% when the initial concentration of 239Pu is 21.5 kBq/L and pH is 2.5-5.0. After five times repetition biosorption-desorption cycles biosorption efficiency is still over 98.0% when the velocity of flow is 2 ml/min in column experiment. Immobilized Sargassum fusiforme biosorbent is better to 239Pu due to its better chemical stability, mechanical strength, lower cost, high biosorption efficiency and repeated biosorption-desorption cycles. (authors)

  17. Ferro- and antiferro-magnetism in (Np, Pu)BC

    Energy Technology Data Exchange (ETDEWEB)

    Klimczuk, T., E-mail: tomasz.klimczuk@pg.gda.pl [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Faculty of Applied Physics and Mathematics, Gdansk University of Technology, Narutowicza 11/12, 80-233 Gdansk (Poland); Shick, A. B. [Institute of Physics, ASCR, Na Slovance 2, CZ-18221 Prague (Czech Republic); Kozub, A. L. [Faculty of Applied Physics and Mathematics, Gdansk University of Technology, Narutowicza 11/12, 80-233 Gdansk (Poland); Institute of Physics, ASCR, Na Slovance 2, CZ-18221 Prague (Czech Republic); Griveau, J.-C.; Colineau, E.; Wastin, F. [European Commission, Joint Research Centre (JRC), Institute for Transuranium Elements (ITU), Postfach 2340, 76125 Karlsruhe (Germany); Falmbigl, M.; Rogl, P., E-mail: peter.franz.rogl@univie.ac.at [Institute for Physical Chemistry, University Vienna, Währingerstrasse 42, A-1090 Wien (Austria)

    2015-04-01

    Two new transuranium metal boron carbides, NpBC and PuBC, have been synthesized. Rietveld refinements of powder XRD patterns of (Np,Pu)BC confirmed in both cases isotypism with the structure type of UBC. Temperature dependent magnetic susceptibility data reveal antiferromagnetic ordering for PuBC below T{sub N} = 44 K, whereas ferromagnetic ordering was found for NpBC below T{sub C} = 61 K. Heat capacity measurements prove the bulk character of the observed magnetic transition for both compounds. The total energy electronic band structure calculations support formation of the ferromagnetic ground state for NpBC and the antiferromagnetic ground state for PuBC.

  18. Reduction of Pu(V) by humic acid

    International Nuclear Information System (INIS)

    The reduction of Pu(V) by humic acid in the presence of divalent cations (calcium and magnesium) was investigated. Tracer concentrations of 238Pu were used (ca. 10-10 M). Experiments were run in 5 m NaCl in the dark at pcH values of 6 and 8 with humic acid concentrations between 0 and 10 ppm. The redox speciation of plutonium was determined by solvent extraction methods. The reduction of Pu(V) by humic acid in the absence of divalent cations was investigated also with samples exposed to light prior to or after the introduction of plutonium. The presence of divalent cations, as well as light exposure increased the reduction of Pu(V), compared to when experiments were run in the dark without divalent cations. (orig.)

  19. Effects of monomeric 239Pu on the pregnant rabbit

    International Nuclear Information System (INIS)

    The effects of 239Pu treatment (0, 10 or 40 μCi/kg) on hematological measurements in pregnant rabbits were studied at 29 days of gestation. Mean clotting times were significantly increased in all plutonium-treated rabbits. There was also a significant increase in clotting time with increasing time between plutonium dosing and sample collection in rabbits injected with 10 μCi/kg. Platelet counts were significantly decreased in all rabbits exposed to 239Pu for 14 days or greater. Hematocrits were significantly depressed in rabbits exposed to 239Pu for 20 days. It is speculated that monomeric 239Pu accumulates at a hematopoietic site close to that affected in X-irradiated animals. (U.K.)

  20. Metabolic pathways of 239Pu immediately after administration

    International Nuclear Information System (INIS)

    239Pu chloride was given to male rats intravenously or by the oral route. The early stages of the Pu metabolism are characterized by a fast distribution in liver and skeleton and a high concentration in the intestine and the muscle tissue. The rate of elimination from the liver and muscles was the same for both types of application. With injection into different parts of the vascular system, the binding to protein and other tissue components was identical. 239Pu is practically not absorbed from the gastrointestinal tract if given perorally. The absorbed fraction had an osteotropic character, i.e. the plutonium was bound to the organic as well as to the mineral fraction. When Pu chloride is injected intravenously, there is a slow redistribution from the characteristic hepatotropic to the osteotropic type. The function of the liver as a barrier against the plutonium is not very prominent and seems to depend on the type of compound given. (MG/AK)

  1. Sequential Separation of U, Np and Pu From Environmental Samples

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    Affected by nuclear testing and nuclear reactor accidents, the release of radioactive substances into the environment, especially long-lived radionuclides including U, Np and Pu can cause great harm to the environment, ecology and

  2. Neutron Capture and Fission Measurement on ^238Pu at DANCE

    Science.gov (United States)

    Chyzh, Andrii; Wu, Ching-Yen; Kwan, Elaine; Henderson, Roger; Gostic, Jolie; Couture, Aaron; Young, Hye; Ullmann, John; O'Donnell, John; Jandel, Marian; Haight, Robert; Bredeweg, Todd

    2012-10-01

    Neutron capture and fission reactions on actinides are important in nuclear engineering and physics. DANCE (Detector for Advanced Neutron Capture Measurement, LANL) combined with PPAC (avalanche technique based fission tagging detector, LLNL) were used to study the neutron capture reactions in ^238Pu. Because of extreme spontaneous α-radioactivity in ^238Pu and associated safety issues, 3 separate experiments were performed in 2010-2012. The 1st measurement was done without fission tagging on a 396-μg thick target. The 2nd one was with PPAC on the same target. The 3rd final measurement was done on a thin target with a mass of 40 μg in order to reduce α-background load on PPAC. This was the first such measurement in a laboratory environment. The absolute ^238Pu(n,γ) cross section is presented together with the prompt γ-ray multiplicity in the ^238Pu(n,f) reaction.

  3. Pu600 energy window arithmetic of plutonium isotopes ratio

    International Nuclear Information System (INIS)

    The idea of calculating plutonium isotopes ratio using Pu600 energy window (630-670 keV) was put forward by the LLNL. And plutonium isotopes ratio arithmetic on Pu600 energy window was developed in this paper. Some γ energy spectra of two plutonium samples were calculated on this arithmetic, and the results are consistent with the results from PC/FRAM. (authors)

  4. Performance of isotope correlations for the estimate of 242Pu

    International Nuclear Information System (INIS)

    The lack of a gamma-ray signature from 242 Pu represents an Achilles heel for many plutonium isotope abundance measurements made by high-resolution gamma spectrometry (HRGS). This holds in particular for plutonium materials containing a significant fraction of this isotope. The problem is partially solved through the application of isotope correlations estimating the relative abundance of 242 Pu from relations to ratios of other plutonium isotopes measurable by HRGS. In the mid of the nineties a new type of isotope correlation had been proposed for LWR plutonium with the recommended coefficients for PWR and BWR fuels. This type of correlation was adopted for the routine analysis of safeguards samples in the Euratom On-Site Laboratories and in the Institute for Transuranium Elements. In order to cover the full range of plutonium materials received for analysis, the application of the above correlation has been also extended to AGR and Magnox-type of plutonium with different sets of coefficients approximating best the correlation for the additional types of materials were determined from a set of reference isotopic data. Since in many instances the origin and the type of the plutonium are not known a priori, criteria for categorization were established helping to select the appropriate isotope correlation. Parametric plots of the ratios 238 Pu/239 Pu versus 240 Pu/239 Pu generally allow to discern unambiguously Magnox, AGR and LWR plutonium, and to some extent also BWR and PWR plutonium, as long as a mixing of the respective plutonium materials has not occurred. With this kind of categorization implemented in the routine analysis the performance of the 242 Pu estimate is substantially improving in most cases. Performance data for 242 Pu in particular, and for plutonium isotope abundance measurements by HRGS in general, as derived from a larger set of measurement data are presented and discussed in terms of their impact on the interpretation of passive neutron

  5. Plutonium concentration and 240Pu/239Pu atom ratio in biota collected from Amchitka Island, Alaska: recent measurements using ICP-SFMS

    International Nuclear Information System (INIS)

    Three underground nuclear tests, including the Unites States' largest, were conducted on Amchitka Island, Alaska. Monitoring of the radiological environment around the island is challenging because of its remote location. In 2008, the Department of Energy (DOE) Office of Legacy Management (LM) became responsible for the long term maintenance and surveillance of the Amchitka site. The first DOE LM environmental survey occurred in 2011 and is part of a cycle of activities that will occur every 5 years. The University of Alaska Fairbanks, a participant in the 2011 study, provided the lichen (Cladonia spp.), freshwater moss (Fontinalis neomexicanus), kelp (Eualaria fistulosa) and horse mussel (Modiolus modiolus) samples from Amchitka Island and Adak Island (a control site). These samples were analyzed for 239Pu and 240Pu concentration and 240Pu/239Pu atom ratio using inductively coupled plasma sector field mass spectrometry (ICP-SFMS). Plutonium concentrations and 240Pu/239Pu atom ratios were generally consistent with previous terrestrial and marine studies in the region. The 239+240Pu levels (mBq kg−1, dry weight) ranged from 3.79 to 57.1 for lichen, 167–700 for kelp, 27.9–148 for horse mussel, and 560–573 for moss. Lichen from Adak Island had higher Pu concentrations than Amchitka Island, the difference was likely the result of the higher precipitation at Adak compared to Amchitka. The 240Pu/239Pu atom ratios were significantly higher in marine samples compared to terrestrial and freshwater samples (t-test, p 240Pu/239Pu ratios in terrestrial samples are within the range of global fallout. • Elevated 240Pu/239Pu in marine samples was characteristic of North Pacific Ocean. • Potential sources of enriched Pu to the marine environment regionally are suggested. • Pu ratios cannot by themselves explain the enriched Pu in seawater around Amchitka

  6. Radiative capture on $^{242}$Pu for MOX fuel reactors

    CERN Multimedia

    The use of MOX fuel (mixed-oxide fuel made of UO$_{2}$ and PuO$_{2}$) in nuclear reactors allows substituting a large fraction of the enriched Uranium by Plutonium reprocessed from spent fuel. Indeed around 66% of the plutonium from spent fuel is made of $^{239}$Pu and $^{241}$Pu, which are fissile in thermal reactors. A typical reactor of this type uses a fuel with 7% reprocessed Pu and 93% depleted U, thus profiting from both the spent fuel and the remaining $^{238}$U following the $^{235}$U enrichment. With the use of such new fuel compositions rich in Pu the better knowledge of the capture and fission cross sections of the Pu isotopes becomes very important. This is clearly stated in the recent OECD NEA’s “High Priority Request List” and in the WPEC-26 “Uncertainty and target accuracy assessment for innovative systems using recent covariance data evaluations” report. In particular, a new series of cross section evaluations have been recently carried out jointly by the European (JEFF) and United ...

  7. Simultaneous estimation of Pu and fission products by gamma spectrometry

    International Nuclear Information System (INIS)

    A gamma spectrometric method is described for the simultaneous estimation of Pu and fission products using a 62cc intrinsic germanium detector coupled to a 4K MCA. The 120 KeV peak of 239Pu was employed for the assay of plutoniu m. The low energy 51 KeV photopeak of 239Pu was not employed due to the interfer ence of the germanium escape peak from 241Am gamma. A nonlinear exponential parame terised function was employed to relate the concentration of 239Pu and the counts obtained from 129 KeV photopeak after subtracting the compton and background. Standard solutions were used for computing the fitting parameters. For fission product analysis, an efficiency versus energy plot was generated using a fission product solution of known individual activities. This was then fitted in a quadratic equation and the fitting parameters were obtained. The inbuilt programme in 4K MCA was used to calculate the 239Pu and the fission products concentration from the respective fitting factors. The isotopic composition was fed externally to obtain the total plutonium concentration. This method was used for the analysis of Pu in the range of 0.5 to 5 g/1. The values when compared with those obtained with coulometric meth od show an agreement within ± 2.5 per cent in the above range. (author). 4 refs., 4 figs., 2 tables

  8. Thermodynamics and speciation: Solubility of PuO2 and Pu(OH)4 and electrophoretic speciation of Np ions

    International Nuclear Information System (INIS)

    This report contains experimental results of two separate subjects: Solubility products of crystalline PuO2 and amorphous Pu(OH)4 separation of Np oxidation states with continuous electrophoretic ion focusing, which are presented separately in part A and B, respectively. The new solubility products of Pu oxide and hydroxide are determined to be log Ksp=-60.20±0.17 and -57.85±0.05, respectively. The free energy of formation for Pu(OH)4(am) is -1141 kJ mol-1. The chemical speciation method using continuous electrophoretic ion focusing has been examined to separate Np(IV) and Np(V) in the picomol contraction under different experimental conditions, i.e. varying pH, complexing agent and medium conductivity. A successful separation of Np ions of two important oxidation states is demonstrated. (orig.)

  9. Assessment of 238Pu and 239+240Pu, in marine sediments of the oceans Atlantic and Pacific of Guatemala

    International Nuclear Information System (INIS)

    In this investigation samples of marine sediments were taken from 14 places representatives of the oceans coast of Guatemala. For the assesment of 238Pu and 239+240Pu in sediments a radiochemical method was used to mineralize sediments and by ionic interchange it was separated from other elements, after that an electrodeposition of plutonium was made in metallic discs. The radioactivity of plutonium was measured by alpha spectrometry system and the alpha spectrums were obtained. The levels of plutonium are not higher than other countries that shown contamination. The contamination of isotope of 239+240Pu is higher than 238Pu and the contamination by two isotopes of plutonium is higher in the Atlantic than the Pacific ocean

  10. Evaluation of the fission and capture cross sections of 240Pu and 241Pu for ENDF/B-V

    International Nuclear Information System (INIS)

    Since there were appreciable new data which were not available for ENDF/B-IV, new evaluations for 240Pu and 241Pu were carried out for ENDF/B-V. The evaluation of the fission and capture cross sections is reviewed and problem areas are discussed. The neutron energy range of concern was from 10-5 eV to 20 MeV. Significant changes were made over the entire neutron energy region because of the new experimental data available. The problems in the evaluations due to discrepancies in the nuclear data are emphasized, particularly the 1-eV resonance in 240Pu and the 0.3-eV resonance in 241Pu. The evaluation of the fission and capture cross sections for ENDF/B-V represents an improvement over the previous evaluation; however, there continues to be a need for accurate experimental data. 7 figures

  11. First-principles thermodynamic calculations for {delta}-Pu and {epsilon}-Pu

    Energy Technology Data Exchange (ETDEWEB)

    Yi Wang [Department of Physics, National Mesoscopic Physics Laboratory, Peking University, Beijing (China); Institute of Applied Physics and Computational Mathematics, Beijing (China); Sun Yunfeng [Department of Physics, National Mesoscopic Physics Laboratory, Peking University, Beijing (China)

    2000-05-29

    With the aim of investigating several long-standing issues, e.g. the equilibrium atomic volumes of the high-temperature {delta}-phase (fcc) and {epsilon}-phase (bcc) of plutonium metal, a first-principles thermodynamic calculation has been carried out on the basis of (i) accurate calculations of 0 K total energies with the full-potential linearized augmented-plane-wave method within the generalized gradient approximation to the exchange-correlational functional and (ii) the newly developed classical mean-field statistics where both the cold and thermal parts of the Helmholtz free energy are derived entirely from the 0 K total energy. The calculated results show that at 0 K the antiferromagnetic states are energy preferable, both for the fcc and for the bcc phases. For the first time, an ab initio thermodynamic calculation gives calculated atomic volumes for {delta}-Pu and {epsilon}-Pu: these are, respectively, 24.97 A{sup 3} and 23.82 A{sup 3}, which are very comparable with the corresponding experimental values of 24.89 A{sup 3} and 24.29 A{sup 3}. (author). Letter-to-the-editor.

  12. Evaluation of the thermal cross sections of 239Pu and 241Pu

    International Nuclear Information System (INIS)

    The thermal neutron cross sections of the isotopes 239Pu and 241Pu have been evaluated in the thermal neutron energy region below 1.0 eV. The method of evaluation fitted energy-dependent data constrained by a modified Adler-Adler multilevel resonance fission and capture formalism and multilevel Breit-Wigner scattering theory. The energy dependence of the number of neutrons per fission was prescribed in the theory by introducing nu as fitted resonance spin-dependent values. The data were fitted in a resonance parameter fitting code, RPFC, using the method of maximum likelihood. The code fits simultaneously the total and partial energy-dependent cross section data to the theory. The types of data explicitly fitted are total, fission, capture, total scattering, coherent scattering, and absorption cross sections plus the quantities alpha, total nu and eta. Relative energy-dependent data with precision errors are fitted along with absolute values and errors at chosen energies. RPFC also allows energy-scale adjustment and Doppler broadening of selected data sets, and fits correlated data of two isotopes simultaneously. Reference experimental data bases of original data plus condensed and modified data were assembled for the evaluation for each isotope. 19 figures, 9 tables

  13. LLNL PuPS Weld Qualification Plan

    Energy Technology Data Exchange (ETDEWEB)

    Dodson, K E; Riley, D

    2001-08-24

    This plan ensures the quality of the Lawrence Livermore National Laboratory (LLNL) DOE 3013 Standard Plutonium Packaging System (PuPS) can welds meet the requirements stipulated in the DOE Standard 3013-00 ''Stabilization, Packaging, and Storage of Plutonium-Bearing Materials'' (Reference 1) and G-ESR-G-00035, Revision 1 dated July 26, 2000, ''Savannah River Site Stabilization and Packaging Requirements for Plutonium Bearing Materials for Storage.'' (Reference 2) This plan also meets the requirements for a weld qualification plan as stipulated in the G-ESR-G-00035. The Outer Can weld must meet ASME VIII & IX. The Outer Can welds will be evaluated initially and during production. The initial evaluation will be done by performing the following: ASME IX welding procedure qualification, ASME IX operator qualification, and a 25 can Dummy Outer Can (DOC) verification run. During production, product cans and DOCs will be evaluated. Product cans will be evaluated by a combination of visual examination of the weld faces and the use of helium leak checking. The DOCs will be examined by visual examination, leak check, radiographic examination and metallographic examination. Appendix 2 summarizes the requirements of each of these evaluations. The Inner Can weld must meet the leak tightness requirements of DOE 3013. The Inner Can weld, while not required to meet ASME requirements, will be controlled as described in this plan to ensure a reliable leak path barrier and consistent production processing behavior. The product Inner Cans will be evaluated by a combination of visual examination of the weld faces and the use of helium leak checking.

  14. Study of neutron-deficient isotopes of Fl in the 239Pu, 240Pu + 48Ca reactions

    Science.gov (United States)

    Voinov, A. A.; Utyonkov, V. K.; Brewer, N. T.; Oganessian, Yu Ts; Rykaczewski, K. P.; Abdullin, F. Sh; Dmitriev, S. N.; Grzywacz, R. K.; Itkis, M. G.; Miernik, K.; Polyakov, A. N.; Roberto, J. B.; Sagaidak, R. N.; Shirokovsky, I. V.; Shumeiko, M. V.; Tsyganov, Yu S.; Subbotin, V. G.; Sukhov, A. M.; Sabelnikov, A. V.; Vostokin, G. K.; Hamilton, J. H.; Stoyer, M. A.; Strauss, S. Y.

    2016-07-01

    The results of the experiments aimed at the synthesis of Fl isotopes in the 239Pu + 48Ca and 240Pu + 48Ca reactions are presented. The experiment was performed using the Dubna gas-filled recoil separator at the U400 cyclotron. In the 239Pu+48Ca experiment one decay of spontaneously fissioning 284Fl was detected at 245-MeV beam energy. In the 240Pu+48Ca experiment three decay chains of 285Fl were detected at 245 MeV and four decays were assigned to 284Fl at the higher 48Ca beam energy of 250 MeV. The α-decay energy of 285Fl was measured for the first time and decay properties of its descendants 281Cn, 277Ds, 273Hs, 269Sg, and 265Rf were determined more precisely. The cross section of the 239Pu(48Ca,3n)284Fl reaction was observed to be about 20 times lower than those predicted by theoretical models and 50 times less than the value measured in the 244Pu+48Ca reaction. The cross sections of the 240Pu(48Ca,4-3n)284,285Fl at both 48Ca energies are similar and exceed that observed in the reaction with lighter isotope 239Pu by a factor of 10. The decay properties of the synthesized nuclei and their production cross sections indicate rapid decrease of stability of superheavy nuclei with departing from the neutron number N=184 predicted to be the next magic number.

  15. Adsorption of Pu(IV) and Pu(VI) under controlled pH and Eh by soil minerals

    International Nuclear Information System (INIS)

    Preliminary experiments indicated that a potentiostat could be used to control the Eh of soil slurries (kaolinite). Results so far indicate that the major amount of adsorption occurs in the first 15 minutes, that Pu(VI) adsorbs less than Pu(IV), that an increase in pH increases the adsorption, and that an increase in surface area and/or cation exchange capacity also increases the adsorption. 4 figs

  16. Analysis and composition of the first U-Pu charge (0,043 per cent of Pu)

    International Nuclear Information System (INIS)

    Checking the homogeneity in the content of plutonium of 0,043 per cent Pu-natural uranium alloy slugs has been made by Pu 240 and U 238 spontaneous fissions neutrons counting. The purpose of the test was to select groups of slugs to be correctly associated into fuel rods for critical experiments. General technic for spontaneous fissions counting, then elaboration of data in view of ranking the slugs are described. Results are given for this particular case. (authors)

  17. Cation interdiffusion in the UO2 - (U, Pu)O2 and UO2 - PuO2 systems

    International Nuclear Information System (INIS)

    The interdiffusion of U and Pu ions in UO sub(2 +- x) - (U sub(0,83) Pu sub(0,17))O sub(2 + - x) and UO sub(2 + - x) -PuO sub(2 - x) sintered pellets and UO sub(2 +- x) -(U sub(0,82) Pu sub(0,18))O sub(2 + - x) single crystals has been studied as a function of the oxygen potential ΔG sup(-) (O2) or the stoichiometric ratio O/M. The diffusion profiles of UO2/(U,Pu)O2 and UO2/PuO2 couples of different O/M ratios have been measured using high resolution α-spectrometer and microprobe. Thermal annealing of the specimens was performed in controlled atmospheres using either CO-CO2 gas mixtures for constant O/M ratios or purified argon. The interdiffusion profiles have been analysed by means of the Boltzmann-Matano and Hall methods. The interdiffusion coefficient D sus(approx.) increases with increasing Pu content in sintered pellets (up to 17 wt. %PuO2) showing a strong dependence of D sup(approx.) on the O/M ratio. The micropobe results show that the interdiffusion along grain boundaries is the main diffusion mechanism in the pellets. Experiments have also been carried out in single cristals to measure just the bulk-interdiffusion and avoiding effects due to grain boundaries. A marked dependence of D sup(approx.) on O/M ratio or on oxygen potential ΔG sup(-) (O2), similar to the dependence already reported for self diffusion by means of radioactive tracers, has also been observed. (Author)

  18. Estimation of uncertainties in resonance parameters of {sup 56}Fe, {sup 239}Pu, {sup 240}Pu and {sup 238}U

    Energy Technology Data Exchange (ETDEWEB)

    Nakagawa, Tsuneo; Shibata, Keiichi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-05-01

    Uncertainties have been estimated for the resonance parameters of {sup 56}Fe, {sup 239}Pu, {sup 240}Pu and {sup 238}U contained in JENDL-3.2. Errors of the parameters were determined from the measurements which the evaluation was based on. The estimated errors have been compiled in the MF32 of the ENDF format. The numerical results are given in tables. (author)

  19. Kinetics of Pu reduction by acetaldoxime and application of acetaldoxime to separation of Pu from U in purex process

    International Nuclear Information System (INIS)

    The effects of concentrations of C2H4NOH, H+, NO3-, Fe(III) and temperature on the reaction rate of the Pu(IV)-acetaldoxime were studied by spectrophotometry, and then the rate equation and the corresponding parameters were obtained. The reduction rate of Pu(IV) can be improved by either increasing the acetaldoxime concentration and the temperature, or decreasing the concentration of acid. However, the effects of concentrations of NO3- and Fe3+ on the reduction rate of Pu(IV) are negligible. It is found that the rate constant is (39.51 ± 0.05) (mol/L)1.1·min-1 at 25 degree C, and the activation energy is (88.96 ± 9.43) kJ/mol. In the counter current cascade experiments with acetaldoxime used as reductant (in which 6 stages for supplemental extraction, 8 stages for stripping, and ratio of flow is 1BS:1BF:1BX=1:4:1), the recoveries are more than 99.99% for U and 99.99% for Pu. The separation factor of Pu from U is 1.05 x 104, while that of U from Pu is 2.7 x 105. (authors)

  20. On the electrochemical formation of Pu-Al alloys in molten LiCl-KCl

    Science.gov (United States)

    Mendes, E.; Malmbeck, R.; Nourry, C.; Souček, P.; Glatz, J.-P.

    2012-01-01

    Properties of Pu-Al alloys were investigated in connection with development of pyrochemical methods for reprocessing of spent nuclear fuel. Electroseparation techniques in molten LiCl-KCl are being developed in ITU to group-selectively recover actinides from the mixture with fission products. In the process, actinides are electrochemically reduced on solid aluminium cathodes, forming solid actinide-aluminium alloys. This article is focused on electro-chemical characterisation of Pu-Al alloys in molten LiCl-KCl, on electrodeposition of Pu on solid Al electrodes and on determination of chemical composition and structure of the formed alloys. Cyclic voltammetry and chronopotentiometry were used to study Pu-Al alloys in the temperature range 400-550 °C. Pu is reduced to metal in one reduction step Pu 3+/Pu 0 on an inert W electrode. On a reactive Al electrode, the reduction of Pu 3+ to Pu 0 occurs at a more positive potential due to formation of Pu-Al alloys. The open circuit potential technique was used to identify the alloys formed. Stable deposits were obtained by potentiostatic electrolyses of LiCl-KCl-PuCl 3 melts on Al plates. XRD and SEM-EDX analyses were used to characterise the alloys, which were composed mainly of PuAl 4 with some PuAl 3. In addition, the preparation of PuCl 3 containing salt by carbochlorination of PuO 2 is described.

  1. Investigation of the oxidation states of Pu isotopes in a hydrochloric acid solution.

    Science.gov (United States)

    Lee, M H; Kim, J Y; Kim, W H; Jung, E C; Jee, K Y

    2008-12-01

    The characteristics of the oxidation states of Pu in a hydrochloric acid solution were investigated and the results were applied to a separating of Pu isotopes from IAEA reference soils. The oxidation states of Pu(III) and Pu(IV) were prepared by adding hydroxylamine hydrochloride and sodium nitrite to a Pu stock solution, respectively. Also, the oxidation state of Pu(VI) was adjusted with concentrated HNO(3) and HClO(4). The stability of the various oxidation states of plutonium in a HCl solution with elapsed time after preparation were found to be in the following order: Pu(III) approximately Pu(VI)>Pu(IV)>Pu(V). The chemical recoveries of Pu(IV) in a 9M HCl solution with an anion exchange resin were similar to those of Pu(VI). This method for the determination of Pu isotopes with an anion exchange resin in a 9M HCl medium was applied to IAEA reference soils where the activity concentrations of (239,240)Pu and (238)Pu in IAEA-375 and IAEA-326 were consistent with the reference values reported by the IAEA. PMID:18674920

  2. Study of thermodynamic properties of Pu-Al alloys in eutectic LiCl-KCl

    International Nuclear Information System (INIS)

    Pyrochemical separation processes are considered as a promising alternative to the hydrometallurgical methods. A technique developed in ITU is based on electrochemical reduction of actinides on an Al cathode in molten salts. This work is focused on chemical characterisation and determination of thermodynamic properties of Pu-Al alloys. The alloys are formed on a solid Al electrode during Pu electrodeposition in molten LiCl-KCl Eutectic. A carbo-chlorination was applied to convert PuO2 added to the molten salt in order to produce a LiCl-KCl-PuCl3 (∼2 wt.%). It was proven, by electrochemical measurements, that the salt contained pure PuCl3 without impurities. Pu-Al alloy properties were studied in the temperature range of 400 - 550 deg. C by electrochemical techniques. Cyclic voltammetry showed one reduction step of Pu3+ on inert W electrode (Pu3+/Pu0). On reactive aluminium electrode, reduction of Pu3+ to Pu0 occurs at more positive potential due to the formation of Pu-Al intermetallic compounds. Open Circuit Potentiometric (OCP) measurements, after depositions of Pu metal onto the Al electrode by short galvanic electrolysis, were used to identify Pu-Al intermetallic compounds. The curves obtained after OCP measurements exhibits 6 plateaus which is in agreement with the Pu-Al phase diagram, containing 5 compounds stable at working temperature range. The thermodynamic properties of the Pu-Al alloys (ΔG, ΔH, ΔS) were deduced from those curves by e.m.f. measurements. Pu-Al deposits were obtained by galvano-static electrolyses on Al plates. XRD and SEM analysis revealed a mixture of PuAl3 and PuAl4 alloys. (authors)

  3. A study of accelerated radiation damage effects in PuO2 and gadolinia-stabilized cubic zirconia, Zr0.79Gd0.14Pu0.07O1.93, doped with 238Pu

    Science.gov (United States)

    Burakov, B. E.; Yagovkina, M. A.

    2015-12-01

    Polycrystalline samples of cubic zirconia, Zr0.79Gd0.14Pu0.07O1.93, doped with approximately 9.9 wt.% 238Pu, and PuO2 containing 11.0 wt. % 238Pu (and main isotope is 239Pu) have been repeatedly studied during many years by X-ray diffraction analysis. At a temperature of 25 °C the unit-cell parameter of PuO2 increases depending on accumulated dose, and is accompanied by decrease of coherent scattering region (CSR). Self-irradiation of Zr0.79Gd0.14Pu0.07O1.93 is accompanied with repeated change of unit-cell parameter and CSR.

  4. Determination of the 240Pu/239Pu atom ratio in low activity environmental samples by alpha spectrometry and spectral deconvolution

    International Nuclear Information System (INIS)

    In this paper, a simple technique, based on commercially-available software developed for gamma spectra analysis (MicroSAMPO trademark), is described by which this complex multiplet can be resolved at the much lower activities typical of many environmental samples. In our approach, it is not necessary to make any alterations to the normal alpha spectrometric set-up (including energy dispersion), other than to improve collimation. The instrumental function is defined for each spectrum by fitting a modified gaussian with exponential tails to the comparatively well-resolved 242Pu ''doublet'' (used as tracer) and, if present, the 238Pu ''doublet''. The fitted peaks are used to create an energy calibration file with which, using published energy data, the positions (in channels) of the component peaks of the multiplet are predicted. These positions are not altered subsequently when MicroSAMPO's interactive multiplet analysis facility is used to quantify the relative spectral intensities of the components. Before calculating the 240Pu/239Pu ratio, it is advisable to correct for coincidence summing of alpha particles and conversion electrons. The technique has been applied to the determination of the 240Pu/239Pu ratio in a set of environmental samples, most of which were supplied by IAEA-MEL under their laboratory intercomparison programme. Subsequently, replicate samples were analysed independently using thermal ionisation mass spectrometry. The agreement between the two sets of data was most satisfactory. Further validation of this deconvolution technique was provided by the good agreement between the measured alpha-emission probabilities for the component peaks in the 239,240Pu multiplet and published values. (orig.)

  5. Chemical behaviour of Np, Pu and Am in aquatic solutions

    International Nuclear Information System (INIS)

    The chemical behaviour of Np, Am and Pu has been studied in aquatic systems of various ionic strength and NaCl concentrations as well as in natural groundwaters. Basic chemical reactions investigated are hydrolysis reaction of Np(V), Pu(IV) and Am(III), carbonate complexation of Pu(IV) and Am(III), and redox reaction of Pu and Am induced by α-radiolysis in brine solutions. The α-induced radiolysis reactions in NaCl solutions are carefully evaluated. The generation of real-colloids of Am(III) and Pu(IV) and the generation of Am(III)-pseudo-colloids through sorption of Am3+ on groundwater-colloids have been also investigated. The natural groundwater-colloids and humic substances, being present in Gorleben groundwaters, are characterized systematically in order to facilate a better understanding of colloid generation in a given groundwater. Transuranium ions in solution have been speciated either by UV-VIS spectroscopy for relatively high concentrations or by Laser-induced photoacoustic spectroscopy (LPAS) for sub-μmol concentrations. (orig.)

  6. Fractionation of 137Cs and Pu in natural peatland

    International Nuclear Information System (INIS)

    High Cs-137 concentrations in plants growing on peatland inspired us to investigate the quantity of its bioavailable fraction in natural peat. Our investigation aims to: a) estimate the quantity of bioavailable Cs-137 and Pu present in peat, b) verify the similarity of Cs-137 and K-40 behaviours, and c) perform a quantification of Cs-137 and Pu transfer from peat to plants. We analysed the vertical distribution of Cs-137 and Pu isotopes in the peat and their concentrations in plants growing on these places. Bioavailability of radionuclides was investigated by sequential extraction. Sequential analyses revealed that it was the upper layer which contained the majority of Cs-137 in an available form while deeper layers retained Cs-137 in immobile fractions. We can conclude that 18% of all Cs-137 in the peat is still bioavailable. Despite of the low quantity of bioavailable fraction of Cs-137 its transfer factor reached extremely high values. In the case of Pu, 64% of its total amount was associated with fulvic/humic acids which resulted in the high transfer factor from peat to plants. 27 years after the Chernobyl nuclear accident, the significant part of radionuclides deposited in peatland is still bioavailable. - Highlights: • Decrease of exchangeable 137Cs and its increase in residual fraction with depth. • High 137Cs transfer factor contrary to its low quantity in bioavailable fractions. • Fulvic/humic acids are a more effective carrier for Pu than for Cs

  7. Neutron Capture Cross Section Measurement on 238Pu at DANCE

    International Nuclear Information System (INIS)

    The proposed neutron capture measurement for 238Pu was carried out in Nov-Dec, 2010, using the DANCE array at LANSCE, LANL. The total beam-on-target time is about 14 days plus additional 5 days for the background measurement. The target was prepared at LLNL with the new electrplating cell capable of plating the 238Pu isotope simultaneously on both sides of the 3-(micro)m thick Ti backing foil. A total mass of 395 (micro)g with an activity of 6.8 mCi was deposited onto the area of 7 mm in diameter. The 238Pu sample was enriched to 99.35%. The target was covered by 1.4 (micro)m double-side aluminized mylar and then inserted into a specially designed vacuum-tight container, shown in Fig. 1, for the 238Pu containment. The container was tested for leaks in the vacuum chamber at LLNL. An identical container without 238Pu was made as well and used as a blank for the background measurement.

  8. LEAD SLOWING DOWN SPECTROSCOPY FOR DIRECT Pu MASS MEASUREMENTS

    International Nuclear Information System (INIS)

    The direct measurement of Pu in previously irradiated fuel assemblies is a recognized need in the international safeguards community. A suitable technology could support more timely and independent material control and accounting (MC and A) measurements at nuclear fuel storage areas, the head-end of reprocessing facilities, and at the product-end of recycled fuel fabrication. Lead slowing down spectroscopy (LSDS) may be a viable solution for directly measuring not only the mass of 239Pu in fuel assemblies, but also the masses of other fissile isotopes such as 235U and 241Pu. To assess the potential viability of LSDS, an LSDS spectrometer was modeled in MCNP5 and 'virtual assays' of nominal PWR assemblies ranging from 0 to 60 GWd/MTU burnup were completed. Signal extraction methods, including the incorporation of nonlinear fitting to account for self-shielding effects in strong resonance regions, are described. Quantitative estimates of Pu uncertainty are given for simplistic and more realistic fuel isotopic inventories calculated using ORIGEN. A discussion of additional signal-perturbing effects that will be addressed in future work, and potential signal extraction approaches that could improve Pu mass uncertainties, are also discussed

  9. Oxygen induced transformations of the δ-Pu(111) surface

    Science.gov (United States)

    Taylor, Christopher D.

    2013-12-01

    The oxides that form on metal surfaces are critical to the preservation of the material under oxidizing conditions. For the case of plutonium, oxide film properties may affect a variety of kinetic phenomena related to the corrosion of the material. To investigate the behavior of the metal-oxygen interactions critical to the formation of such passive films, electronic structure calculations were performed on the interactions between O and the δ-Pu(111) surface. By probing the relationship between structure (coordination), charge transfer (valence) and thermodynamics (reactivity), it was found that oxidation is initially a local phenomenon, but, at 1.0 ML oxygen coverage, significant reconstructions that alter the phase structure of the near-surface region are induced. At this high-surface coverage the surface metal atoms are disbonded and the Pusbnd O coordination becomes four-fold as opposed to three fold. Even at this high coverage, however, the charge state more closely resembles Pu2O3 rather than PuO2. The ability for surface Pu atoms to adapt to a variety of changes in charge state and coordination provides a fundamental basis for understanding the multilayer structure of passive films formed on clean Pu surfaces. An analysis using first-principles thermodynamics also suggests that these films should develop uniformly, and not via an island or columnar growth mechanism.

  10. Neutron Capture Cross Section Measurement on $^{238}$Pu at DANCE

    Energy Technology Data Exchange (ETDEWEB)

    Chyzh, A; Wu, C Y

    2011-02-14

    The proposed neutron capture measurement for {sup 238}Pu was carried out in Nov-Dec, 2010, using the DANCE array at LANSCE, LANL. The total beam-on-target time is about 14 days plus additional 5 days for the background measurement. The target was prepared at LLNL with the new electrplating cell capable of plating the {sup 238}Pu isotope simultaneously on both sides of the 3-{micro}m thick Ti backing foil. A total mass of 395 {micro}g with an activity of 6.8 mCi was deposited onto the area of 7 mm in diameter. The {sup 238}Pu sample was enriched to 99.35%. The target was covered by 1.4 {micro}m double-side aluminized mylar and then inserted into a specially designed vacuum-tight container, shown in Fig. 1, for the {sup 238}Pu containment. The container was tested for leaks in the vacuum chamber at LLNL. An identical container without {sup 238}Pu was made as well and used as a blank for the background measurement.

  11. Pu(V) transport through Savannah River Site soils - an evaluation of a conceptual model of surface- mediated reduction to Pu (IV).

    Science.gov (United States)

    Powell, Brian A; Kaplan, Daniel I; Serkiz, Steven M; Coates, John T; Fjeld, Robert A

    2014-05-01

    Over the last fifteen years the Savannah River Site (SRS) in South Carolina, USA, was selected as the site of three new plutonium facilities: the Mixed Oxide Fuel Fabrication Facility, Pit Disassembly and Conversion Facility, and the Pu Immobilization Plant. In order to assess the potential human and environmental risk associated with these recent initiatives, improved understanding of the fate and transport of Pu in the SRS subsurface environment is necessary. The hypothesis of this study was that the more mobile forms of Pu, Pu(V) and Pu(VI), would be reduced to the less mobile Pu(III/IV) oxidation states under ambient SRS subsurface conditions. Laboratory-scale dynamic flow experiments (i.e., column studies) indicated that Pu(V) was very mobile in SRS sediments. At higher pH values the mobility of Pu decreased and the fraction of Pu that became irreversibly sorbed to the sediment increased, albeit, only slightly. Conversely, these column experiments showed that Pu(IV) was essentially immobile and was largely irreversibly sorbed to the sediment. More than 100 batch sorption experiments were also conducted with four end-member sediments, i.e., sediments that include the chemical, textural, and mineralogical properties likely to exist in the SRS. These tests were conducted as a function of initial Pu oxidation state, pH, and contact time and consistently demonstrated that although Pu(V) sorbed initially quite weakly to sediments, it slowly, over the course of oxidation state of the dissolved Pu introduced into a SRS sediment system, Pu(IV) controls the environmental transport within a couple weeks and Pu strongly binds to the sediment, limiting its mobility. PMID:24238838

  12. ZZ WPPR-FR-MOX/BNCMK, Benchmark on Pu Burner Fast Reactor

    International Nuclear Information System (INIS)

    Description of program or function: In order to intercompare the characteristics of the different reactors considered for Pu recycling, in terms of neutron economy, minor actinide production, uranium content versus Pu burning, the NSC Working Party on Physics of Plutonium Recycling (WPPR) is setting up several benchmark studies. They cover in particular the case of the evolution of the Pu quality and Pu fissile content for Pu recycling in PWRs; the void coefficient in PWRs partly fuelled with MOX versus Pu content; the physics characteristics of non-standard fast reactors with breeding ratios around 0.5. The following benchmarks are considered here: - Fast reactors: Pu Burner MOX fuel, Pu Burner metal fuel; - PWRs: MOX recycling (bad quality Pu), Multiple MOX recycling

  13. Vertical distribution of 241Pu in the southern Baltic Sea sediments

    International Nuclear Information System (INIS)

    Highlights: • The unique study on 241Pu in sediments from the southern Baltic Sea was presented. • 241Pu was determined using alpha spectrometry by indirect method. • The biggest amount of 241Pu existed in the surface layers of all analyzed sediments. • The highest 241Pu amount comes from the Chernobyl accident. - Abstract: The vertical distribution of plutonium 241Pu in marine sediments can assist in determining the deposition history and sedimentation process of analyzed regions. In addition, 241Pu/239+240Pu activity ratio could be used as a sensitive fingerprint for radioactive source identification. The present preliminary studies on vertical distribution of 241Pu in sediments from four regions of the southern Baltic Sea are presented. The distribution of 241Pu was not uniform and depended on sediment geomorphology and depth as well as location. The highest concentrations of plutonium were found in the surface layers of all analyzed sediments and originated from the Chernobyl accident

  14. Electronic and thermodynamic properties of α-Pu2O3

    Science.gov (United States)

    Lu, Yong; Yang, Yu; Zheng, Fawei; Zhang, Ping

    2014-08-01

    Based on density functional theory+U calculations and the quasi-annealing simulation method, we obtain the ground electronic state for α-Pu2O3 and present its phonon dispersion curves as well as various thermodynamic properties, which have seldom been theoretically studied because of the huge unit cell. We find that the Pu-O chemical bonding is weaker in α-Pu2O3 than in fluorite PuO2, and subsequently a frequency gap appears between oxygen and plutonium vibration density of states. Based on the calculated Helmholtz free energies at different temperatures, we further study the reaction energies for Pu oxidation, PuO2 reduction, and transformation between PuO2 and α-Pu2O3. Our reaction energy results are in agreements with available experiment. And it is revealed that high temperature and insufficient oxygen environment are in favor of the formation of α-Pu2O3.

  15. Vertical distribution and migration of global fallout Pu in forest soils in southwestern China

    International Nuclear Information System (INIS)

    Soil samples collected in southwestern China were analyzed for Pu isotopes. The 240Pu/239Pu atom ratios were around 0.18, which indicated the dominant source of global fallout. Consistent sub-surface maximums followed by exponential decline of 239+240Pu activities in the soil cores were observed. Most of the Pu has still remained in the 0–10 cm layers since its deposition. Convection velocities and dispersion coefficients for Pu migration in the soils were estimated by the convection–dispersion equation (CDE) model. The effective convection velocities and effective dispersion coefficients ranged from 0.05 to 0.11 cm/y and from 0.06 to 0.29 cm2/y, respectively. Other factors that control the vertical migration of Pu in soil besides precipitation, soil particle size distribution and organic matter were suggested. Long-term migration behaviors of Pu in the soils were simulated. The results provide the Pu background baseline for further environmental monitoring and source identification of non-global fallout Pu inputs in the future. - Highlights: • Pu isotopes in the soil cores collected in southwestern China were analyzed. • Background baseline data of Pu isotopes in the soils were given. • Parameters of convection–dispersion equation model for Pu migration were estimated. • Long-term migration behavior of Pu in soil was simulated

  16. Observation of cold fission in 242Pu spontaneous fission

    International Nuclear Information System (INIS)

    Coincidence γ-ray data from the spontaneous fission of 242Pu were collected at the Lawrence Berkeley Laboratory high purity Ge (HPGe) array, GAMMASPHERE. Data from several cold-fission (0 neutron emission) isotopic pairs were observed and are presented. An interesting trend in the fractional population of cold-fission events was observed and is discussed. Relative yields of Zr-Xe, Sr-Ba, and Mo-Te pairs were measured. The Zr-Xe system has the most complete data set. Some speculations on the trend in the number of neutrons emitted as a function of the mass of the Xe isotope populated are presented. Comparisons between the yields from the spontaneous fission of 242Pu and the yields from thermal-neutron-induced fission of 241Pu are also presented. copyright 1996 The American Physical Society

  17. ICE1 of Pyrus ussuriensis functions in cold tolerance by enhancing PuDREBa transcriptional levels through interacting with PuHHP1

    Science.gov (United States)

    Huang, Xiaosan; Li, Kongqing; Jin, Cong; Zhang, Shaoling

    2015-12-01

    ICE1 transcription factor plays an important role in plant cold stress via regulating the expression of stress-responsive genes. In this study, a PuICE1 gene isolated from Pyrus ussuriensis was characterized for its function in cold tolerance. The expression levels of the PuICE1 were induced by cold, dehydration and salt, with the greatest induction under cold conditions. PuICE1 was localized in the nucleus and could bind specifically to the MYC element in the PuDREBa promoter. The PuICE1 fused to the GAL4 DNA-binding domain to have transcriptional activation activity. Ectopic expression of the PuICE1 in tomato conferred enhanced tolerance to cold stress at cold temperatures, less electrolyte leakage, less MDA content, higher chlorophyll content, higher survival rate, higher proline content, higher activities of enzymes. In additon, steady-state mRNA levels of six stress-responsive genes coding for either functional or regulatory genes were induced to higher levels in the transgenic lines by cold stress. Yeast two-hybrid, transient assay, split luciferase complementation and BiFC assays all revealed that PuHHP1 protein can physically interact with PuICE1. Taken together, these results demonstrated that PuICE1 plays a positive role in cold tolerance, which may be due to enhancement of PuDREBa transcriptional levels through interacting with the PuHHP1.

  18. Analytical Method for Pu-239, Pu-240, Np-237 and Tc-99 using Inductively Coupled Plasma Mass Spectrometry

    International Nuclear Information System (INIS)

    An efficient analytical method for Pu isotopes (Pu-239 and Pu-240), Np-237 and Tc-99 in environmental samples has been developed using sector field inductively coupled plasma mass spectrometry (SF-ICPMS) detection. The chemical separation of Pu in terrestrial samples, soil, and sediment was carried out on two extraction resins, Sr-Spec and TEVA, which were sequentially combined in PrepLab, an integrated liquid handing device. By reducing the final eluent volume to 2.4 mL, directly injecting it to SF-ICPMS, and employing MCN-6000, a membrane desolvating sample introduction system, the analysis of Pu isotopes was found to be feasible in 1 g of soil. The detection limits of Pu-239, Pu-240, and Pu-242 were approximately 4 fg mL-1 (9.2 Bq mL-1), 3 fg mL-1 (25 Bq mL-1), and 6 fg mL-1 (0.87 Bq mL-1), which represent total amounts of 9.6, 7.2, and 14 fg, respectively, in the final eluent. Chemical separation and measurement were fully automated by a sequential injection (SI) program in an on-line system, and the analysis could thereby be completed within roughly 5 hours. The reliability of this method was confirmed by a validity test with several certified standard reference materials (NIST-4350b, IAEA-6, IAEA-300, IAEA-367, IAEA-368, IAEA-375). The analytical method for Pu in environmental seawater is different from that of terrestrial samples owing to the strong interference effect of U as well as ultra-low level Pu. Although the principle of chemical separation is nearly the same as in soil, seawater was co-precipitated with Fe(OH)2 in the pre-treatment step and a micro TEVA column (50 L) was used in the on-line system to improve precision and the lower detection limit. With this method, it was possible to analyze ultra-trace level Pu isotopes in only 5 L of surface seawater within 1 day, and the precision for Pu-239 and Pu-240 was less than 3.4% (n=7) and 5% (n=7), respectively. The accuracy of this method was verified by analysis of reference seawater (IAEA-381) as

  19. Transuranic concentrations in reef and pelagic fish from the Marshall Islands. [/sup 239/Pu, /sup 240/Pu

    Energy Technology Data Exchange (ETDEWEB)

    Noshkin, V.E.; Eagle, R.J.; Wong, K.M.; Jokela, T.A.

    1980-09-01

    Concentrations of /sup 239 + 240/Pu are reported in tissues of several species of reef and pelagic fish caught at 14 different atolls in the northern Marshall Islands. Several regularities that are species dependent are evident in the distribution of /sup 239 + 240/Pu among different body tissues. Concentrations in liver always exceeded those in bone and concentrations were lowest in the muscle of all fish analyzed. A progressive discrimination against /sup 239 + 240/Pu was observed at successive trophic levels at all atolls except Bikini and Enewetak, where it was difficult to conclude if any real difference exists between the average concentration factor for /sup 239 + 240/Pu among all fish, which include bottom feeding and grazing herbivores, bottom feeding carnivores, and pelagic carnivores from different atoll locations. The average concentration of /sup 239 + 240/Pu in the muscle of surgeonfish from Bikini and Enewetak was not significantly different from the average concentrations determined in these fish at the other, lesser contaminated atolls. Concentrations among all 3rd, 4th, and 5th trophic level species are highest at Bikini where higher environmental concentrations are found. The reasons for the anomalously low concentrations in herbivores from Bikini and Enewetak are not known.

  20. Analytical Method for Pu-239, Pu-240, Np-237 and Tc-99 using Inductively Coupled Plasma Mass Spectrometry

    Energy Technology Data Exchange (ETDEWEB)

    Kim, Cheol Su

    2007-02-15

    An efficient analytical method for Pu isotopes (Pu-239 and Pu-240), Np-237 and Tc-99 in environmental samples has been developed using sector field inductively coupled plasma mass spectrometry (SF-ICPMS) detection. The chemical separation of Pu in terrestrial samples, soil, and sediment was carried out on two extraction resins, Sr-Spec and TEVA, which were sequentially combined in PrepLab, an integrated liquid handing device. By reducing the final eluent volume to 2.4 mL, directly injecting it to SF-ICPMS, and employing MCN-6000, a membrane desolvating sample introduction system, the analysis of Pu isotopes was found to be feasible in 1 g of soil. The detection limits of Pu-239, Pu-240, and Pu-242 were approximately 4 fg mL-1 (9.2 Bq mL-1), 3 fg mL-1 (25 Bq mL-1), and 6 fg mL-1 (0.87 Bq mL-1), which represent total amounts of 9.6, 7.2, and 14 fg, respectively, in the final eluent. Chemical separation and measurement were fully automated by a sequential injection (SI) program in an on-line system, and the analysis could thereby be completed within roughly 5 hours. The reliability of this method was confirmed by a validity test with several certified standard reference materials (NIST-4350b, IAEA-6, IAEA-300, IAEA-367, IAEA-368, IAEA-375). The analytical method for Pu in environmental seawater is different from that of terrestrial samples owing to the strong interference effect of U as well as ultra-low level Pu. Although the principle of chemical separation is nearly the same as in soil, seawater was co-precipitated with Fe(OH)2 in the pre-treatment step and a micro TEVA column (50 L) was used in the on-line system to improve precision and the lower detection limit. With this method, it was possible to analyze ultra-trace level Pu isotopes in only 5 L of surface seawater within 1 day, and the precision for Pu-239 and Pu-240 was less than 3.4% (n=7) and 5% (n=7), respectively. The accuracy of this method was verified by analysis of reference seawater (IAEA-381) as

  1. Economical Production of Pu-238: NIAC Phase I Final Report

    Science.gov (United States)

    Howe, Steven D.; Crawford, Douglas; Navarro, Jorge; O'Brien, Robert C.; Katalenich, Jeff; Ring, Terry

    2016-01-01

    All space exploration missions traveling beyond Jupiter must use radioisotopic power sources for electrical power. The best isotope to power these sources is plutonium-238 (Pu-238). The US supply of Pu-238 is almost exhausted and will be gone within the next decade. The Department of Energy has initiated a production program with a $10M allocation from NASA but the cost is estimated at over $100M to get to production levels. The Center for Space Nuclear Research (CSNR) has conceived of a potentially better process to produce Pu-238 earlier and for significantly less cost. Potentially, the front end capital costs could be provided by private industry such that the government only had to pay for the product produced. In the Phase I NIAC (NASA Innovative Advanced Concepts) grant, the CSNR has evaluated the feasibility of using a low power, commercially available nuclear reactor to produce 1.5 kg of Pu-238 per year. The impact on the neutronics of the reactor have been assessed, the amount of Neptunium target material estimated, and the production rates calculated. In addition, the size of the post-irradiation processing facility has been established. Finally, as the study progressed, a new method for fabricating the Pu-238 product into the form used for power sources has been identified to reduce the cost of the final product. In short, the concept appears to be viable, can produce the amount of Pu-238 needed to support the NASA missions, can be available within a few years, and will cost significantly less than the current DOE program.

  2. Toxicity of inhaled 238PuO2 II

    International Nuclear Information System (INIS)

    Studies are in progress to determine dose-response relationships for inhaled 238PuO2. Beagle dogs were given a single, brief, nose-only inhalation exposure to aerosols of monodisperse particles of 238PuO2. Aerosols of two sizes were used, 1.5 μm aerodynamic diameter (AD) and 3.0 μm AD. Dogs were exposed to achieve initial lung burdens of 0.56, 0.28, 0.14, 0.07, 0.03 or 0.01 μCi 238PuO2/kg body weight. Twelve dogs were exposed at each activity level to each aerosol particle size. The local dose around each 3.0 μm AD particle was 10 times higher than the local dose around 1.5 μm AD particles, but the dose averaged over the whole lung was the same at each activity level for both particle sizes. The lung retention of 238Pu was divided into two phases of clearance. During the first 100 days after exposure, the average retention half-time for 238Pu in the lung was 310 days. When the solubility changed due to particle breakup, the retention half-time decreased to 180 days during the period from 1OO to 1,500 days after exposure. The first biological effects observed were lymphopenia and neutropenia in peripheral blood. To date, 28 Beagle dogs have died at times from 536 to 1683 days after exposure. Initial lung burdens for the dead dogs ranged from 0.18 to 2.2 μCi 238Pu/kg body weight. Nine died with radiation pneumonitis and pulmonary fibrosis, 10 died with lung tumors and 19 dogs died with bone tumors. There are 116 exposed and 22 control dogs surviving and under observation. Current patterns of dose versus response are discussed. (author)

  3. Random Probability Analysis of 48Ca +239Pu Experimental Data

    Science.gov (United States)

    Strauss, S. Y.; Henderson, R. A.; Stoyer, M. A.; Abdullin, A. F. Sh.; Brewer, N. T.; Dmitriev, S. N.; Grzywacz, R. K.; Hamilton, J. H.; Itkis, M. G.; Miernik, K.; Oganessian, Yu. Ts.; Polyakov, A. N.; Roberto, J. B.; Rykaczewski, K. P.; Sabelnikov, A. V.; Sagaidak, R. N.; Shirokovsky, I. V.; Shumeyko, M. V.; Subbotin, V. G.; Sukhov, A. M.; Tsyganov, Yu. S.; Utyonkov, V. K.; Voinov, A. A.; Vostokin, G. K.

    2014-09-01

    Element 114 (Fl), was discovered at the Flerov Laboratory of Nuclear Reactions (FLNR) using the 48Ca +244Pu reaction and the Dubna Gas-Filled Recoil Separator (DGFRS). The structural properties of the super heavy elements are still largely unknown. The extent of the region of enhanced stability near Z = 114 and N = 184 is not completely known. To examine these properties, a new experimental data set has been taken using the 48Ca +239Pu reaction at the DGFRS, in an effort to look for lighter isotopes of Fl. Progress on the production of lighter isotopes of Fl, cross-section measurements, and any nuclear decay properties will be discussed. Comparisons with reactions using heavier 242,244Pu targets and Monte Carlo random probability analysis will be highlighted. Element 114 (Fl), was discovered at the Flerov Laboratory of Nuclear Reactions (FLNR) using the 48Ca +244Pu reaction and the Dubna Gas-Filled Recoil Separator (DGFRS). The structural properties of the super heavy elements are still largely unknown. The extent of the region of enhanced stability near Z = 114 and N = 184 is not completely known. To examine these properties, a new experimental data set has been taken using the 48Ca +239Pu reaction at the DGFRS, in an effort to look for lighter isotopes of Fl. Progress on the production of lighter isotopes of Fl, cross-section measurements, and any nuclear decay properties will be discussed. Comparisons with reactions using heavier 242,244Pu targets and Monte Carlo random probability analysis will be highlighted. This work was performed under Contract DE-AC52-07NA27344 and Grant DE-NA0002135.

  4. Electronic structure of Pu-Ce(-Ga) and Pu-Am(-Ga) alloys, stabilized in the {delta} phase; Structure electronique d'alliages Pu-Ce(-Ga) et Pu-Am(-Ga) stabilises en phase {delta}

    Energy Technology Data Exchange (ETDEWEB)

    Dormeval, M

    2001-09-01

    The behaviour of {delta}-plutonium, stable between 319 and 451 deg C, exhibits numerous singularities which are still a mystery for both physicists and metallurgists. This is due to its complex electronic structure, and in particular to the 5f electrons, which are at the edge between localization and delocalization. The stability domain of the {delta} phase can be extended down to room temperature by alloying with so called 'deltagen atoms' such as gallium (Ga), aluminum (A1), cerium (Ce) or americium (Am). The present work deals, one the one hand, with the influence of cerium and americium solutes regarding the localization of the 5f electrons of {delta}-plutonium, in binary Pu-Ce and Pu-Am alloys. On the other hand, the effect of two different deltagen solutes, simultaneously present, on the stability of the {delta} phase has been studied in ternary Pu-Am-Ga and Pu-Ce-Ga alloys. The electronic structure being strongly related to the crystalline organization, characterization methods such as X-Ray diffraction and EXAFS measurements were used together with electrical resistivity and magnetic susceptibility experiments. These showed that the roles of cerium and americium, supposed to be similar at the beginning of this investigation, are actually very different. Moreover, the additive effect of cerium and gallium, and, americium and gallium, has been demonstrated. Studying plutonium alloys, which are radioactive, also means following their evolution in time. The characteristics of the alloys have then been followed which allowed to detect, in Pu-Ce(-Ga) alloys, a destabilization of the {delta} phase and, to observe, in Pu-Am(-Ga) alloys, the influence of self-irradiation defects on the magnetic response. (author)

  5. The stability of Pu(III) in sorption studies

    International Nuclear Information System (INIS)

    Full text of publication follows: Plutonium has been studied in a number of instances in conjunction with its expected behavior in a geological repository for spent nuclear fuel. In the case of no reprocessing, plutonium will make up about one percent of the spent fuel and be one of the constituents that contribute the most to the long storage time that is demanded. Sorption onto mineral surfaces is one of the mechanisms that are believed to limit the migration of dissolved waste products from a repository. Studies of plutonium in solution tend to encounter trouble with the stability of the oxidation state as work is done on the tri-, tetra- and pentavalent states. The work presented here is a summary of results on the seemingly first sorption experiments done using Pu(III) as a sorbate. It shows some of the limitations of what can be done with Pu(III) in such experiments, and has yielded some sorption data as a function of pH on TiO2 and UO2. Pu(III) is quite prone to oxidize in the presence of oxygen. This tendency needs to be suppressed during a sorption experiment. Three degrees of oxygen exclusion and provision of reducing conditions have been applied and are compared: - A glove-box, in contact with the ambient atmosphere, hosting a vessel of Pu(III) solution through which a 4% hydrogen/argon gas mix was bubbled in the presence of a catalyst. - An inert gas box (N2) with 2. - The same inert gas box with a reducing sorbent sorbent. The results of the experiments show that the conditions under the first point were not sufficient to keep plutonium trivalent. There was considerably more success in an inert glove-box where batch sorption experiments (10-6 M Pu) have been done on TiO2 and UO2. Of these oxides, TiO2 does not affect the oxidation state of a Pu solution, while UO2 is a powerful reductant. Cations of higher effective charges tend to sorb more strongly. It is absolutely essential to have an idea about the oxidation state during the experiment, or

  6. Fabrication of 12% {sup 240}Pu calorimetry standards

    Energy Technology Data Exchange (ETDEWEB)

    Long, S.M.; Hildner, S.; Gutierrez, D.; Mills, C.; Garcia, W.; Gurule, C.

    1995-08-01

    Throughout the DOE complex, laboratories are performing calorimetric assays on items containing high burnup plutonium. These materials contain higher isotopic range and higher wattages than materials previously encountered in vault holdings. Currently, measurement control standards have been limited to utilizing 6% {sup 240}Pu standards. The lower isotopic and wattage value standards do not complement the measurement of the higher burnup material. Participants of the Calorimetry Exchange (CALEX) Program have identified the need for new calorimetric assay standards with a higher wattage and isotopic range. This paper describes the fabrication and verification measurements of the new CALEX standard containing 12% {sup 240}Pu oxide with a wattage of about 6 to 8 watts.

  7. Constrained Density Functional Calculations of alpha and delta Pu

    Science.gov (United States)

    Eriksson, Olle

    2002-03-01

    The electronic structure of α and δ Pu are described using a modified density functional theory that incorporates localization effects of the 5f shell. It is argued that a Russel-Saunders coupled state involving a 5f^4 multiplet, together with one itinerant 5f electron explains most of the observed ground state properties of δ Pu (equilibrium volume, elastic constants, near degeneracy with the alpha phase). This 5f electrons in the α phase are argued to form itinerant states, that are well described in density functional theory. The two distinctly different electronic ground states give rise to different excitation spectra and a comparison with experimental data is made.

  8. BSAP Can Repress Enhancer Activity by Targeting PU.1 Function

    OpenAIRE

    Maitra, Shanak; Atchison, Michael

    2000-01-01

    PU.1 and BSAP are transcription factors crucial for proper B-cell development. Absence of PU.1 results in loss of B, T, and myeloid cells, while absence of BSAP results in an early block in B-cell differentiation. Both of these proteins bind to the immunoglobulin κ chain 3′ enhancer, which is developmentally regulated during B-cell differentiation. We find here that BSAP can repress 3′ enhancer activity. This repression can occur in plasmacytoma lines or in a non-B-cell line in which the enha...

  9. Measurement of the fission cross-section of $^{240}$Pu and $^{242}$Pu at CERN's n_TOF Facility

    CERN Multimedia

    Pavlik, A F; Gonzalez romero, E M

    The n_TOF Collaboration proposes to continue the fission program, already started in 2002-2004, taking advantage of the newly constructed Work Sector Type A, with the measurement of the two isotopes : $^{240}$ Pu and $^{242}$ Pu. They are both of major importance for reactor physics applications and are included in the Nuclear Energy Agency (NEA) High Priority List [1], in the NEA WPEC Subgroup 26 Report on the accuracy of nuclear data for advanced reactor designe [2] and in the EU 6$^{th}$ Framework Programme IP-EUROTRANS/NUDATRA reports [3]. Based on those requests, the measurement of the fission cross-section of the two Pu isotopes is one of the objectives of the project ANDES of the FP7 EURATOM program [4].

  10. Sequential leaching extraction of 239,240Pu, 238Pu, 241Pu and 241Am from a mud sample: An intercomparison study

    International Nuclear Information System (INIS)

    Full text: The determination of the association percentages of transuranics to different sediment phases could define their fate once they have been deposited onto the marine floor and their possible reactivity at the sediment/sea water interphase. Nowadays, there is a wide variety of leaching methods to extract transuranics from the different geochemical compounds conforming the sediments. Nevertheless, a general controversy is extended in the scientific world due to the extreme difficulty in testing their reliability, since the standards of transuranics linked to a certain sedimentary phase are not commercially available. Two mud subsamples taken from a storage container were analysed employing the same sequential extraction method, but with small handling differences.The following fractions were isolated: (1) Readily available (2) Carbonate bound and specifically adsorbed (3) Organically bound (4) Oxide and hydroxides bound and (5) residual. The 239,240Pu, 238Pu and 241Am extracted in each phase were analysed using standard radiochemical procedures. 241Pu was determined by both direct scintillation counting and through the 241Am in-growth up on the old disks containing Plutonium. The procedure for uncertainty calculations has been also included. (author)

  11. Sequential leaching extraction of 239,240Pu, 238Pu, 241Pu, 237Np and 241Am from a mud sample: An intercomparison study

    International Nuclear Information System (INIS)

    The transuranics content of a mud sample taken from a nuclear waste storage container was analysed employing two different sequential extraction methods. The following fractions were isolated: (1)Water soluble (2) Readily available (3) Carbonate bound and specifically adsorbed (4) Organically bound (5) Oxide and hydroxides bound and (6) residual. Both methods differ in the reagents employed, the extraction sequence applied as well as the temperature and means of extraction. The 239,240Pu, 238Pu, 237Np and 241Am extracted in each phase were determined using standard radiochemical procedures. 241Pu was analysed through the 241Am in-growth on just one old disk of the residual fraction containing plutonium. Plutonium was mainly associated to organic-oxides fractions (89-92 %). The percentage extracted in each fraction depended on the method and the extraction sequence used. The soluble fraction of plutonium was less than 13%. Neptunium seemed to be the more soluble than the other transuranics (27%) and the americium showed a tendency to be associated to carbonates (30%). (author)

  12. Field solid/liquid partitioning of Pu and Am: new scientific aspects

    International Nuclear Information System (INIS)

    The field distribution coefficient Ksub(d,f) is an important global parameter to describe the transfer of elements and radionuclides in aquatic, terrestrial and geologic environments. Pu and Am are transuranic elements with well studied environmental and radiological concerns. New aspects presented here are: 1) The valence of mobile chemical forms of Pu: PuO2+(Pu V) PuO2++(Pu VI) and their radiological incidence; 2) The chemical speciation of Pu and Am, especially complexation with natural inorganic and organic ligands. Selected parameters affecting Ksub(d,f) are discussed: physical and mechanical factors of liquid/solid contact; sorption and exchange by minerals, clay and organic matter; precipitation; oxidoreduction and pH; complexation, competition with stable elements (Na, K, Fe,...), microbiological factors. The incidence of the Ksub(d,f) variability on the transfer of Pu and Am in environment and trophic chains of animal and man is briefly discussed. (author)

  13. Biogeochemical Cycling and Environmental Stability of Pu Relevant to Long-Term Stewardship of DOE Sites

    Energy Technology Data Exchange (ETDEWEB)

    Honeyman, Bruce D.; Francis, A.J.; Gillow, Jeffrey B.; Dodge, Cleveland J.; Santschi, Peter H.; Chin-Chang Hung; Diaz, Angelique; Tinnacher, Ruth; Roberts, Kimberly; Schwehr, Kathy

    2006-04-05

    The overall objective of this research is to understand the biogeochemical cycling of Pu in environments of interest to long-term DOE stewardship issues. Central to Pu cycling (transport initiation and immobilization) is the role of microorganisms. The hypothesis underlying this work is that microbial activity is the causative agent in initiating the mobilization of Pu in near-surface environments: through the transformation of Pu associated with solid phases, production of extracellular polymeric substances (EPS) carrier phases and the creation of microenvironments. Also, microbial processes are central to the immobilization of Pu species, through the metabolism of organically complexed Pu species and Pu associated with extracellular carrier phases and the creation of environments favorable for Pu transport retardation.

  14. Biogeochemical Cycling and Environmental Stability of Pu Relevant to Long-Term Stewardship of DOE Sites

    Energy Technology Data Exchange (ETDEWEB)

    Francis, Arokiasamy J.; Santschi, Peter H.; Honeyman, Bruce D.

    2005-06-01

    The overall objective of this proposed research is to understand the biogeochemical cycling of Pu in environments of interest to long-term DOE stewardship issues. Central to Pu cycling (transport initiation to immobilization) is the role of microorganisms. The hypothesis underlying this proposal is that microbial activity is the causative agent in initiating the mobilization of Pu in near-surface environments: through the transformation of Pu associated with solid phases, production of extracellular polymeric substances (EPS) carrier phases, and the creation of microenvironments. Also, microbial processes are central to the immobilization of Pu species, through the metabolism of organically complexed Pu species and Pu associated with extracellular carrier phases and the creation of environments favorable for Pu transport retardation.

  15. Refinement of Pu parent-daughter isotopic and concentration analysis for forensic (dating) purposes

    International Nuclear Information System (INIS)

    Plutonium (Pu) metal samples from an interlaboratory exchange exercise and simulated swipe samples were dated using plutonium-uranium (Pu-U) and plutonium-americium (Pu-Am). Metal data were evaluated for consistency and the swipe data against its source material. Metal ages based on 239Pu versus 235U and 240Pu versus 236U agreed to within a few percent, while the 238Pu-234U and 241Pu-241Am measurements had larger uncertainties. Swipe ages compared favorably with the material's known history. Neptunium (237Np) analyses were examined in the context of the 241Pu-241Am-237Np system to estimate whether Np can provide insights on material from which Am, Np, and U were removed. (author)

  16. HPLC method for determination of Th, U and Pu in irradiated (Th,Pu)O2 using mandelic acid as an eluent

    International Nuclear Information System (INIS)

    Studies for chromatographic separation of Th, U(VI) and Pu(IV) were carried out using mandelic acid as an eluent. The different chromatographic conditions like concentration of mandelic acid, pH of the mobile phase, presence of MeOH and effect of ion interaction reagent (IIR) were studied. The method was optimized for the separation of Th, U(VI) and Pu(IV). At pH3.5, reverse trend was observed. The optimized parameters were employed for the separation and determination of Th, U(VI) and Pu(IV) in a dissolved solution of irradiated (Th,Pu)O2. Sample treatment was optimized to minimize loss of Pu and Th during chromatographic determination. Studies were carried out using two IIRs to understand the anomalous chromatographic behavior of Pu(IV). Retention behavior of different oxidation states of Pu viz. Pu(III), Pu(IV) and Pu(VI) was also studied in mandelic acid.

  17. Characterization of Pu-238 Heat Source Granule Containment

    Energy Technology Data Exchange (ETDEWEB)

    Richardson, Paul Dean II [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Sanchez, Joey Leo [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wall, Angelique Dinorah [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Chavarria, Rene [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-02-11

    The Milliwatt Radioisotopic Themoelectric Generator (RTG) provides power for permissive-action links. Essentially these are nuclear batteries that convert thermal energy to electrical energy using a doped silicon-germanium thermopile. The thermal energy is provided by a heat source made of 238Pu, in the form of 238PuO2 granules. The granules are contained by 3 layers of encapsulation. A thin T-111 liner surrounds the 238PuO2 granules and protects the second layer (strength member) from exposure to the fuel granules. An outer layer of Hastalloy-C protects the T-111 from oxygen embrittlement. The T-111 strength member is considered the critical component in this 238PuO2 containment system. Any compromise in the strength member seen during destructive testing required by the RTG surveillance program is characterized. The T-111 strength member is characterized through Scanning Electron Microscopy (SEM), and Metallography. SEM is used in the Secondary Electron mode to reveal possible grain boundary deformation and/or cracking in the region of the strength member weld. Deformation and cracking uncovered by SEM are further characterized by Metallography. Metallography sections are mounted and polished, observed using optical microscopy, then documented in the form of microphotographs. SEM mat further be used to examine polished Metallography mounts to characterize elements using the SEM mode of Energy Dispersive X-ray spectroscopy (EDS).

  18. Biological effects in intramuscular 239Pu administration during chelatotherapy

    International Nuclear Information System (INIS)

    Durable (up to 64 days) application of complexones (Ca and Zn DTPA) in the case of intramuscular administration of 239Pu large amounts in rats is studied. The results of studying the biological effect proving considerable decrease of the average lifespan of rats are given

  19. Fractionation of (137)Cs and Pu in natural peatland.

    Science.gov (United States)

    Mihalík, Ján; Bartusková, Miluše; Hölgye, Zoltán; Ježková, Tereza; Henych, Ondřej

    2014-08-01

    High Cs-137 concentrations in plants growing on peatland inspired us to investigate the quantity of its bioavailable fraction in natural peat. Our investigation aims to: a) estimate the quantity of bioavailable Cs-137 and Pu present in peat, b) verify the similarity of Cs-137 and K-40 behaviours, and c) perform a quantification of Cs-137 and Pu transfer from peat to plants. We analysed the vertical distribution of Cs-137 and Pu isotopes in the peat and their concentrations in plants growing on these places. Bioavailability of radionuclides was investigated by sequential extraction. Sequential analyses revealed that it was the upper layer which contained the majority of Cs-137 in an available form while deeper layers retained Cs-137 in immobile fractions. We can conclude that 18% of all Cs-137 in the peat is still bioavailable. Despite of the low quantity of bioavailable fraction of Cs-137 its transfer factor reached extremely high values. In the case of Pu, 64% of its total amount was associated with fulvic/humic acids which resulted in the high transfer factor from peat to plants. 27 years after the Chernobyl nuclear accident, the significant part of radionuclides deposited in peatland is still bioavailable. PMID:24631917

  20. Strain differences in the embryotoxicity of 239Pu

    International Nuclear Information System (INIS)

    Comparison of the embryolethality of monomeric 239Pu injected at 9 days of gestation demonstrated that the sensitivity of Charles River CD strain was greater than that of Hilltop Wistar rats. Subsequent comparisons showed that rats derived from the Hilltop Fischer strain were more sensitive than the Wistar and, although not directly compared, more sensitive than the CD

  1. Analysis of safety margins for PuO2 containers

    International Nuclear Information System (INIS)

    In the regular manner the containers for PuO2 transport are type B(U) and give satisfaction to the AIEA proofs. However the vigour of this conception's containers and the analysis of other radioactive containers permit to think that large safety margins exist. In this paper, the importance and the kind of these margins are studied

  2. Process for cleaning a nitric acid U/Pu-solution

    International Nuclear Information System (INIS)

    The impure starting solution is passed through a cation exchange column following oxidation of the U/Pu ions present to the hexavalent state. Here the impurities, in particular Americium, are retained and after subsequent elution are handled by known waste treatments or waste utilization (Americium). (orig.)

  3. Evaluation of neutron nuclear data for 240Pu

    International Nuclear Information System (INIS)

    Based on the experimental data evaluation and theoretical calculation, a complete set of neutron nuclear data for 240Pu has been recommended in the incident neutron energy range from 10-5 eV to 20 MeV for CENDL-2. The comparison of present evaluation with ENDF/B-6 and JENDL-3 has been carried out

  4. PDF analysis of PuAl alloys local structure

    Science.gov (United States)

    Platteau, C.; Bruckel, P.; Ravat, B.; Delaunay, F.

    2009-03-01

    For understanding singular properties of plutonium, there is a need in studying the average and local atomic structure in Pu alloys. To study the local structure of the δ phase, a pair distribution function (PDF) analysis was done and has shown some significant differences with the average structure.

  5. Monte Carlo simulations of the stability of delta-Pu

    DEFF Research Database (Denmark)

    Landa, A.; Soderlind, P.; Ruban, Andrei

    2003-01-01

    . It is found that at T-c similar to 548 K, delta-Pu undergoes transformation from a disordered magnetic state to a structure with an anti ferromagnetic spin alignment that is mechanically unstable with respect to tetragonal distortion. The calculated transition temperature is in good agreement with...

  6. Evaluation of the neutron cross sections for Pu-240

    International Nuclear Information System (INIS)

    The present evaluation is proposed to supersede the ENDF/B-V, Revision 2 file for 240Pu. In this work, resonance parameters, cross sections, energy distributions, and angular distributions have been modified. These changes are outlined in detail and appropriate references included. 37 refs., 21 figs., 2 tabs

  7. Atomic Structure and Phase Transformations in Pu Alloys

    Energy Technology Data Exchange (ETDEWEB)

    Schwartz, A J; Cynn, H; Blobaum, K M; Wall, M A; Moore, K T; Evans, W J; Farber, D L; Jeffries, J R; Massalski, T B

    2008-04-28

    Plutonium and plutonium-based alloys containing Al or Ga exhibit numerous phases with crystal structures ranging from simple monoclinic to face-centered cubic. Only recently, however, has there been increased convergence in the actinides community on the details of the equilibrium form of the phase diagrams. Practically speaking, while the phase diagrams that represent the stability of the fcc {delta}-phase field at room temperature are generally applicable, it is also recognized that Pu and its alloys are never truly in thermodynamic equilibrium because of self-irradiation effects, primarily from the alpha decay of Pu isotopes. This article covers past and current research on several properties of Pu and Pu-(Al or Ga) alloys and their connections to the crystal structure and the microstructure. We review the consequences of radioactive decay, the recent advances in understanding the electronic structure, the current research on phase transformations and their relations to phase diagrams and phase stability, the nature of the isothermal martensitic {delta} {yields} {alpha}{prime} transformation, and the pressure-induced transformations in the {delta}-phase alloys. New data are also presented on the structures and phase transformations observed in these materials following the application of pressure, including the formation of transition phases.

  8. {\\alpha}-accompanied cold ternary fission of $^{238-244}$Pu isotopes in equatorial and collinear configuration

    OpenAIRE

    Santhosh, K P; Krishnan, Sreejith; Priyanka, B.

    2015-01-01

    The cold ternary fission of $^{238}$Pu, $^{240}$Pu, $^{242}$Pu and $^{244}$Pu isotopes, with $^{4}$He as light charged particle, in equatorial and collinear configuration has been studied within the Unified ternary fission model (UTFM). The fragment combination $^{100}$Zr+$^{4}$He+$^{134}$Te possessing the near doubly magic nuclei $^{134}$Te (N=82, Z=52) gives the highest yield in the alpha accompanied ternary fission of $^{238}$Pu. For the alpha accompanied ternary fission of $^{240}$Pu, $^{...

  9. Towards a spectroscopic standard database for Pu in repository environments

    International Nuclear Information System (INIS)

    Full text of publication follows: The alteration behaviour of Pu in geological and technical environments is, although of crucial importance for example in final repository assessment procedures for high-level nuclear waste, not sufficiently investigated. Since Pu chemistry differs significantly from U behaviour (mostly due to the different stabilities of the +IV oxidation states of both elements), conclusions based on the uranium analogy cannot be extended to Pu chemistry in many cases. In order to examine precisely the alteration behaviour of Pu under repository storage conditions, customized tools for the spectroscopic identification of the element need to be developed. We are currently constructing systematically a database of Pu compounds and collect their spectra for this purpose. Pu compounds (with the element in the oxidation states +III, +IV, +V, and +VI) are synthesised, mostly by using hydrothermal synthesis techniques [1]. Compounds of high importance for repository studies are: Carbonates, (oxy)hydroxides, silicates, peroxides, and phosphates. The products are characterised by Scanning Electron Microscopy (SEM), X-Ray Photoelectron spectroscopy (XPS), and X-Ray diffraction (XRD). Furthermore, vibrational spectra (Raman and IR) of the substances will be recorded. These will allow the unambiguous identification of chemically similar compounds, once the database is compiled: Although reported for a few cases with nuclear material only, the combined investigation of solids with Raman [2,3] and SEM-EDX [3] in a combined mode, especially when spatially resolving, holds great potential An investigation with accelerator-based XAS techniques is planned within the framework of the Excellence network Actinet 6. [1] Grigorev, M., Bessonov, A., Makarenkov, V., Fedoseev, A., Model of the (PuO2)2SiO4 * 2H2O crystal structure, based on powder X-ray diffraction data, Radiochemistry, Vol. 45, No 3 (2003) 257-260. [2] M. Amme, B. Renker, B. Schmid, M. Feth, H

  10. Study on Analytical Method of Pu(Ⅲ, Ⅳ) and U(Ⅳ) in 1BP

    Institute of Scientific and Technical Information of China (English)

    LIU; Huan-liang; ZHANG; Li-hua; FAN; De-jun; WANG; Ling; QIAN; Hong-juan

    2013-01-01

    U(Ⅳ)is taken as reductant in uranium and plutonium separation process of China spent nuclear fuel reprocessing pilot plant.Rapid determining the concentrations of Pu(Ⅲ)/Pu(Ⅳ)and U(Ⅳ)in 1BP is vital to monitor 1B processing stage and condition the subsequent processing solution.A rapid method for determining the concentrations of Pu(Ⅲ)/Pu(Ⅳ)and U(Ⅳ)in 1BP was developed

  11. DENSITY-FUNCTIONAL STUDY OF Zr-BASED ACTINIDE ALLOYS: 2. U-Pu-Zr SYSTEM

    Energy Technology Data Exchange (ETDEWEB)

    Landa, A; Soderlind, P; Turchi, P; Vitos, L; Ruban, A

    2009-02-09

    Density-functional theory, previously used to describe phase equilibria in the U-Zr alloys [1], is applied to study ground state properties of the bcc U-Pu-Zr solid solutions. Calculated heats of formation of the Pu-U and Pu-Zr alloys are in a good agreement with CALPHAD assessments. We found that account for spin-orbit coupling is important for successful description of Pu-containing alloys.

  12. Bulk characterization of (U, Pu) mixed carbide fuel for distribution of plutonium

    Energy Technology Data Exchange (ETDEWEB)

    Devi, K. V. Vrinda, E-mail: kvvdevi@barc.gov.in; Khan, K. B. [Radiometallurgy Division, Bhabha Atomic Research Centre, Mumbai-400094 (India); Biju, K. [Health physics Division, Bhabha Atomic Research Centre, Mumbai-400094 (India); Kumar, Arun [Nuclear fuels group, Bhabha Atomic Research Centre, Mumbai-400094 (India)

    2015-06-24

    Homogeneous distribution of plutonium in (U, Pu) mixed fuels is important from fuel performance as well as reprocessing point of view. Radiation imaging and assay techniques are employed for the detection of Pu rich agglomerates in the fuel. A simulation study of radiation transport was carried out to analyse the technique of autoradiography so as to estimate the minimum detectability of Pu agglomerates in MC fuel with nominal PuC content of 70% using Monte Carlo simulations.

  13. Radionuclide release from irradiated Th-Pu mox fuel

    Energy Technology Data Exchange (ETDEWEB)

    Rodriguez, N.; Quinones, J. [Ciemat., Avda. Complutense 22. E-28040 Madrid (Spain); Cobos, J. [Centro Nacional de Aceleradores, Parque Tecnologico Cartuja 93, Av. Thomas Alva Edison, 7, E-41092 Sevilla (Spain); Rondinella, V.V.; Van Winckel, S.; Somers, J.; Papaioanu, D.; Glatz, J.P. [European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, D-76125 Karlsruhe (Germany)

    2010-07-01

    Plutonium and minor actinides produced as by-products of the UO{sub 2} nuclear cycle could be considered as waste or energy source depending on the strategy selected in the nuclear energy programme. Considering Pu and Minor Actinides as a source, they can be burned in existing water reactor for diminishing the radiotoxicity of the spent fuel, it is necessary to use 'inactive' materials as matrix like ThO{sub 2}. ThO{sub 2} matrix has demonstrated its Pu burning efficiency and higher corrosion resistance than UO{sub 2}. Uranium-plutonium mixed oxide (MOX) fuel efficiency is low because the presence of U in MOX results in the creation of some new Pu under irradiation. The dissolution behaviour of irradiated (Th,Pu)O{sub 2} pellets with burn-up of 38.8 MWd/kg Th has been studied in carbonated (20 mM HCO{sub 3}{sup -}), deionised and granite ground water solution in a hot cell. The dissolution behaviour of Th, Pu, U and Np was studied in order to find out whether radionuclides release is depending on the matrix dissolution (solubility control). After irradiating the samples, K-ORIGEN and ORIGEN ARP codes were used to find out the theoretical inventory. Afterwards, fuel samples were dissolved completely and analyzed, in order to determine the experimental radionuclide inventory of the irradiated fuel. Th matrix alteration appears to reach an steady state and radionuclides dissolution shows dependence on the matrix behaviour as can be observed through the FIAP results. (authors)

  14. Determination of Pu Oxidation states in the HCl Media Using with UV-Visible Absorption Spectroscopic Techniques

    International Nuclear Information System (INIS)

    The spectroscopic characteristics of Pu (III, IV, V, VI) in the HCl media were investigated by measuring Pu oxidation states using a UV-Vis-NIR spectrophotometer (400-1200 nm) after adjusting Pu oxidation states with oxidation/reduction reagents. Pu in stock solution was reduced to Pu(III) with NH2OH · HCl, and oxidized to Pu(IV) and Pu(VI) with NaNO2 and HCIO4 , respectively. Also, Pu(V) was adjusted in the Pu(VI) solution with NH2OH · HCl. The major absorption peaks of Pu (IV) and Pu(III) were measured in the 470 nm and 600 nm, respectively. The major absorption peaks of Pu (VI) and Pu(V) were measured in the 830 nm and 1135 nm, respectively. There was not found to be significant changes of UV-V is absorption spectra for Pu(III), Pu(IV) and Pu(VI) with aging time, except that an unstable Pu(V) immediately reduced to Pu(III).

  15. A rapid NDA method (NWCC) for determination of Pu content in MOX powders

    International Nuclear Information System (INIS)

    A NDA method based on coincidence neutron counting has been used for the determination of Pu content in mixed UO2-PuO2 powders of known isotopic compositions. Pu in MOX powders could be determined quickly with a precision of ±2.5%. (author). 3 refs., 2 tabs

  16. 238Pu fuel form processes. Final report, January-September 1983

    International Nuclear Information System (INIS)

    Progress is reported on the following: analytical studies of weld-quench cracking in DOP-26 iridium alloy, iridium/238PuO2 compatibility test, surface area measurements of 238PuO2 using the Blaine air permeability apparatus, and helium release from 238PuO2

  17. Preliminary Study on the Determination of ~(235)U and ~(239)Pu Using Delayed Neutron Counting Method

    Institute of Scientific and Technical Information of China (English)

    2011-01-01

    The preliminary study on the fast measurements of 235U and 239Pu in samples containing 235U, 239Pu and 235U-239Pu mixture using delayed neutron counting method is introduced. All samples were irradiated for 30 s using the 30 kW Miniature Neutron

  18. Subcellular binding of 239Pu in the liver of selected species of rodents

    International Nuclear Information System (INIS)

    The subcellular distribution of 239Pu in the liver of selected rodent species was investigated as well as the relation between 239Pu and the iron metabolism. The goal of the investigation was to find out why the liver discharge of 239Pu from the liver varies so much between species. (orig.)

  19. Role of protracted exposure on the toxicology of inhaled 239PuO2

    International Nuclear Information System (INIS)

    Studies were initiated to examine in rats the effects of a protracted exposure to inhaled 239PuO2. Graphs are presented to show effect of multiple exposures to 239PuO2 on the deposition and clearance of 239Pu in the alveoli

  20. Transcription factor PU.1 is expressed in white adipose and inhibits adipocyte differentiation

    Science.gov (United States)

    PU.1 transcription factor is a critical regulator of hematopoiesis and leukemogenesis. Because PU.1 interacts with transcription factors GATA-2 and C/EBPa, both of which are involved in the regulation of adipogenesis, we investigated whether PU.1 also plays a role in the regulation of adipocyte diff...

  1. Sommerfeld coefficient of δ-Pu determined via a low-temperature specific heat Pu-Ce study

    Czech Academy of Sciences Publication Activity Database

    Havela, L.; Javorský, P.; Shick, Alexander; Kolorenč, Jindřich; Colineau, E.; Rebizant, J.; Wastin, F.; Griveau, J.C.; Jolly, L.; Texier, G.; Delaunay, F.; Baclet, N.

    2010-01-01

    Roč. 82, č. 15 (2010), 155140/1-155140/5. ISSN 1098-0121 R&D Projects: GA ČR(CZ) GAP204/10/0330 Institutional research plan: CEZ:AV0Z10100520 Keywords : Sommerfeld coefficient γ * δ-Pu Subject RIV: BM - Solid Matter Physics ; Magnetism Impact factor: 3.772, year: 2010

  2. The redox potential of Pu containing acidic solutions and the fate of "Pu(IV)-colloids": Direct measurement versus optical absorption spectroscopy

    Science.gov (United States)

    Icker, M.; Walther, C.; Neck, V.; Geckeis, H.

    2010-03-01

    Redox potentials were measured in acidic aqueous solutions (-log10[H+]=0.7) containing different fractions of tri- and tetravalent plutonium. Eh values measured directly by a Pt electrode vs Ag/AgCl reference electrode agree very well with the redox potential calculated from the oxidation state distribution Pu(III)/Pu(IV). By monitoring the solutions over 120 days the kinetics of redox state distribution and dissolution of initially present Pu(IV)-colloids were studied. In solutions of Eh>950mV colloids dissolve and form Pu(VI), whereas at lower Eh the dissolution of colloids leads to formation of Pu(III). These findings corroborate the assumption that colloids are an integral part of the aqueous Pu redox chemistry and that formation and dissolution can be fully understood by means of Eh / pH stability calculations.

  3. Anaerobic Biotransformation and Mobility of Pu and of Pu-EDTA

    International Nuclear Information System (INIS)

    The enhanced mobility of radionuclides by co-disposed chelating agent, ethylenediaminetetraacetate (EDTA), is likely to occur only under anaerobic conditions. Our extensive effort to enrich and isolate anaerobic EDTA-degrading bacteria has failed. Others has tried and also failed. To explain the lack of anaerobic biodegradation of EDTA, we proposed that EDTA has to be transported into the cells for metabolism. A failure of uptake may contribute to the lack of EDTA degradation under anaerobic conditions. We demonstrated that an aerobic EDTA-degrading bacterium strain BNC1 uses an ABC-type transporter system to uptake EDTA. The system has a periplasmic binding protein that bind EDTA and then interacts with membrane proteins to transport EDTA into the cell at the expense of ATP. The bind protein EppA binds only free EDTA with a Kd of 25 nM. The low Kd value indicates high affinity. However, the Kd value of Ni-EDTA is 2.4 x 10-10 nM, indicating much stronger stability. Since Ni and other trace metals are essential for anaerobic respiration, we conclude that the added EDTA sequestrates all trace metals and making anaerobic respiration impossible. Thus, the data explain the lack of anaerobic enrichment cultures for EDTA degradation. Although we did not obtain an EDTA degrading culture under anaerobic conditions, our finding may promote the use of certain metals that forms more stable metal-EDTA complexes than Pu(III)-EDTA to prevent the enhanced mobility. Further, our data explain why EDTA is the most dominant organic pollutant in surface waters, due to the lack of degradation of certain metal-EDTA complexes.

  4. Synthesis and identification of (NH4)2PuCI6 and (NH4)2UCI6 and preparation of PuCI3

    International Nuclear Information System (INIS)

    This paper reports that plutonium trichloride and uranium tetrachloride can be prepared at low temperatures from the reaction of PuO2 and UO2 with NH4Cl and HCl. The intermediate salts (NH4)2PuCl6 and (NH4)2UCl6 have been isolated and identified. These salts may then be thermally decomposed to anhydrous PuCl3 and UCl4, respectively

  5. Structural, magnetic, electronic and optical properties of PuC and PuC0.75: A hybrid density functional study

    Science.gov (United States)

    Yang, Rong; Tang, Bin; Gao, Tao; Ao, BingYun

    2016-05-01

    We perform first principles calculations to investigate the structural, magnetic, electronic and optical properties of PuC and PuC0.75. Furthermore, we examine the influence of carbon non-stoichiometry on plutonium monocarbide. For the treatment of strongly correlated electrons, the hybrid density functionals like PBE0, Fock-0.25 are used and we compare the results with the generalized gradient approximation (GGA), local density approximation (LDA), LDA + U and experimental ones. The optimized lattice constant a0 = 4.961 Å for PuC in the Fock-0.25 scheme is the most close to the experimental data. The ground states of PuC and PuC0.75 are found to be anti-ferromagnetic. Our results indicate that additional removal of a C atom make lattice contract and new DOS peak appear in the near-Fermi region. We also compute and compare the optical properties of PuC and PuC0.75. The difference in optical properties between PuC and PuC0.75 should also be the influence of carbon vacancies.

  6. Transport process of Pu isotope in marginal seas of the western North Pacific Ocean

    International Nuclear Information System (INIS)

    Significant quantities of Pu isotopes have been released into the marine environment as the result of atmospheric nuclear weapons testing. Most radionuclides globally dispersed in atmospheric nuclear weapons testing were released into the environment during the 1950's and 1960's. In the western North Pacific Ocean, the principal source can be further distinguished as two distinct sources of Pu: close-in tropospheric fallout from nuclear weapons testing at the Pacific Proving Grounds (PPG) in the Marshall Islands and global stratospheric fallout. Since the 240Pu/239Pu atom ratio is characteristic for the Pu emission source, information on Pu isotopic signature is very useful to better understand the transport process in the oceans and to identify the sources of Pu. The mean atom ratio of 240Pu/239Pu from the global stratospheric fallout is 0.180 ±0.014 based on soil sample data, whereas that from close-in tropospheric fallout from the PPG is 0.33 - 0.36. The 240Pu/239Pu atom ratios in seawater samples collected in marginal seas of the western North Pacific Ocean will provide important and useful data for understanding the process controlling Pu transport and for distinguishing future Pu sources. The objectives of this study were to measure the 239+240Pu concentrations and 240Pu/239Pu atom ratios in seawater from the Sea of Okhotsk, Japan Sea, South China Sea and Sulu Sea and to discuss the transport process of Pu. Large-volume seawater samples (250 L each) were collected from the surface to the bottom in marginal seas of the western North Pacific Ocean with acoustically triggered quadruple PVC sampling bottles during the R/V Hakuho-Maru cruise. The 239Pu and 240Pu concentrations and 240Pu/239Pu atom ratios were measured with a double-focusing SF-ICP-MS, which was equipped with a guard electrode to eliminate secondary discharge in the plasma and to enhance overall sensitivity. In the Sea of Okhotsk, the 239+240Pu concentration was 2.8 mBq m-3 in the surface water

  7. AFS-2 FLOWSHEET MODIFICATIONS TO ADDRESS THE INGROWTH OF PU(VI) DURING METAL DISSOLUTION

    Energy Technology Data Exchange (ETDEWEB)

    Crapse, K.; Rudisill, T.; O' Rourke, P.; Kyser, E.

    2014-07-02

    In support of the Alternate Feed Stock Two (AFS-2) PuO{sub 2} production campaign, Savannah River National Laboratory (SRNL) conducted a series of experiments concluding that dissolving Pu metal at 95°C using a 6–10 M HNO{sub 3} solution containing 0.05–0.2 M KF and 0–2 g/L B could reduce the oxidation of Pu(IV) to Pu(VI) as compared to dissolving Pu metal under the same conditions but at or near the boiling temperature. This flowsheet was demonstrated by conducting Pu metal dissolutions at 95°C to ensure that PuO{sub 2} solids were not formed during the dissolution. These dissolution parameters can be used for dissolving both Aqueous Polishing (AP) and MOX Process (MP) specification materials. Preceding the studies reported herein, two batches of Pu metal were dissolved in the H-Canyon 6.1D dissolver to prepare feed solution for the AFS-2 PuO{sub 2} production campaign. While in storage, UV-visible spectra obtained from an at-line spectrophotometer indicated the presence of Pu(VI). Analysis of the solutions also showed the presence of Fe, Ni, and Cr. Oxidation of Pu(IV) produced during metal dissolution to Pu(VI) is a concern for anion exchange purification. Anion exchange requires Pu in the +4 oxidation state for formation of the anionic plutonium(IV) hexanitrato complex which absorbs onto the resin. The presence of Pu(VI) in the anion feed solution would require a valence adjustment step to prevent losses. In addition, the presence of Cr(VI) would result in absorption of chromate ion onto the resin and could limit the purification of Pu from Cr which may challenge the purity specification of the final PuO{sub 2} product. Initial experiments were performed to quantify the rate of oxidation of Pu(IV) to Pu(VI) (presumed to be facilitated by Cr(VI)) as functions of the HNO{sub 3} concentration and temperature in simulated dissolution solutions containing Cr, Fe, and Ni. In these simulated Pu dissolutions studies, lowering the temperature from near boiling

  8. Relative solubiolity in simulated biological fluids of PuO2 on air sampler filters

    International Nuclear Information System (INIS)

    An ultrafiltration method was developed to estimate the solubility of PuO2 on an air filter in simulated lung fluid (SLF), simulated gastric juice (SGJ), and in 1% DTPA. After a very rapid early appearance in the filtrate, both 238Pu and 239Pu showed similar rates of low ultrafilterability. The amount of 239Pu appearing during the first day of ultrafiltration was 10 times less in SLF than in SGJ or DTPA, although the amount of 238Pu was similar for the three solvents. The method used to estimate solubility requires only about 1000 dpm of plutonium alpha radiation per sample

  9. Inhaled 239PuO2 in rats with pulmonary emphysema

    International Nuclear Information System (INIS)

    The modifying effects of a pre-existing lung disease (emphysema) on the deposition, distribution, retention, and effects of inhaled 239PuO2 in the rat are being investigated. Preliminary observations indicated that the deposition and retention patterns for 239Pu particles inhaled by rats with emphysema and control rats were similar, but the distribution of inhaled 239Pu immediately after exposure was different. Respiratory function measured through one year after exposure to 239Pu was consistent with emphysema and was not altered by the 239Pu lung burden. Long-term observations are continuing. 4 references, 2 tables

  10. Investigation on the spectroscopic characteristics for Pu oxidation state in acid and alkali medium

    International Nuclear Information System (INIS)

    The absorption spectra of Pu in stock solution were measured using a UV-Vis-NIR spectrophotometer after dissolving PuO2 with HNO3, HF and HCIO4. The spectroscopic characteristics of Pu (III, IV, VI) in acidic, neutral and alkali media were investigated. Also, the intensities and position of major peaks for Pu(VI) were observed with increasing acidic and alkali concentration. The variation of oxidation states of Pu(VI) with an adding reducing reactant was investigated in HCI and NaOH medium

  11. The Application of Hydroxyurea in the Separation of U and Pu

    Institute of Scientific and Technical Information of China (English)

    2001-01-01

    The present paper suggests a novel salt-free organic agent to separate U and Pu in HNO3 solution. This agent is hydroxyurea(HU) which has strong reduction ability and also is a good chelating agent with a relatively simple structure. HU can rapidly reduce Pu(IV) to Pu(III) in HNO3 solution. The reduction can be to such extent that almost 100% Pu(IV) can be reduced to Pu(III) in 0.5 mol/L and 3.0 mol/L HNO3 solution. With the concentration less than 1.0 mol/L, HU has

  12. Mass effect and Pu removal from rats with Ca- or Zn-DTPA

    International Nuclear Information System (INIS)

    Eight percent of an intramuscular injection of 27.6 nCi of 237Pu(NO3)4 was retained by rats at the injection site, after 22 days. More than 30% is usually retained following injection of more massive quantities of 239Pu. Treatment with Ca- or Zn-DTPA showed the former to be more effective when treatments were initiated 1 hr after Pu administration. When treatments were begun 7 days after the Pu injection, 416 nmol Ca-DTPA/kg was more effective in removing Pu than 28.7 nmol/kg (human dose level) of Zn- or Ca-DTPA. Due to its high specific activity and ease of detection, 237Pu permits facile experimentation in small animals at Pu mass levels comparable to those encountered in most human exposures

  13. Measurement of the fission cross section of 238Pu

    International Nuclear Information System (INIS)

    The fission cross sections of 238Pu have been measured from 0.1 eV to 80 keV energy range using the Rensselaer Intense Neutron Spectrometer. The cross sections were normalized to the 235U ENDF/B-V data broadened to the resolution of the Rensselaer Intense Neutron Spectrometer system. The fission areas and widths were determined for the resolved low-energy resonances. The ENDF/B-V fission cross sections for the 238Pu isotope are, in general, not in good agreement with the measured cross sections and a new evaluation is recommended. The observations of structure in the unresolved fission cross sections is suggestive of the existence of intermediate structure. 18 refs., 1 fig., 1 tab

  14. Design of a Pu-238 waste incineration process

    International Nuclear Information System (INIS)

    Combustible 238Pu waste is generated as a result of normal operation and decommissioning activity at the Savannah River Plant and is being retrievably stored at the Plant. As part of the long-term plan to process the stored waste and current waste in preparation for future disposition, a 238Pu incinceration process is being cold-tested at SRL. The incineration process consists of a continuous-feed preparation system, a two-stage, electrically fired incinerator, and a filtration off-gas system. Process equipment has been designed, fabricated, and installed for nonradioactive testing and cold run-in. Design features to maximize the ability to remotely maintain the equipment were incorporated into the process. Interlock, alarm, and control functions are provided by a programmable controller. Cold testing is scheduled to be completed in 1986

  15. Non-magnetic ground state of PuO2

    International Nuclear Information System (INIS)

    In order to fully utilize the potential of nuclear power, maintaining at the minimum level the risks associated with the deployment of this technology, it is necessary to solve the problems of characterization, treatment, and disposal of high-level nuclear waste. On the time scale of several hundred years, the waste from the open fuel cycle will predominantly contain Pu and minor actinides. Their geological disposal requires a waste handling technology of exceptional durability, with highly reduced risk of accidental events. That is why the comprehensive knowledge of the physical and chemical properties of actinide-based oxides (AnO2, An = Th, U, Np, Pu, Am, Cm), which constitute the main part of the long-lived nuclear waste, remains a key topic of condensed matter theory

  16. Simultaneous determination of U and Pu isotopes by alpha spectrometry

    International Nuclear Information System (INIS)

    Determination of actinides by alpha spectrometry is usually carried out after full separation of each of the components of the sample. The procedure presented in this paper permits U and Pu isotopes to be measured together allowing faster sample processing and measurement. The method consists in the extraction with tributyl phosphate of U and Pu isotopes from the rest of the matrix, followed by a cathodic electrodeposition to obtain alpha spectrometry suitable pieces. It can be applied to various environmental samples, such as water, filters and soil (about 0.5 g of solid sample for the described conditions). High-quality electroplated discs are essential for simultaneous processing, so a technique to achieve this requirement is also explained. (authors)

  17. 239 240Pu in Lake Michigan: 1971 to 1978

    International Nuclear Information System (INIS)

    The plutonium concentration data presented previously have consisted primarily of results from studies of short-term variations, i.e., the annual plutonium cycle conducted at Lake Michigan station ANL-5, 12 km SW of Grand Haven, Michigan. In this report, mean annual concentrations of total plutonium in unfiltered water from far off-shore (> 30 km) stations for the period 1971 through 1977, and from station ANL-5 (1975 through 1978) are summarized to establish the long-term trend in plutonium concentration in Lake Michigan. The results presented show that the mean annual concentration in the water column is similar at ANL-5 and at offshore stations and has decreased at the rate of only 6% per year during the period 1972 through 1978. The nearly constant concentration indicates that steady-state equilibria exist between plutonium inputs to the lake and the loss of plutonium from the water column. Observations suggest the existence of an active redox cycle for Pu in Lake Michigan. In this cycle, Pu IV atoms in solution are continually taken up by particulate materials but may be oxidized within microzones of the particles such as freshly deposited manganese coatings and also in solution by agents such as dissolved oxygen. In turn, the concentration of Pu VI in solution may be limited by reaction with reducing constituents of the coloidal-sized fraction (or decomposer organisms such as bacteria or fungi, which might have been present after filtration) and with planktonic organisms in the environment to produce Pu IV and thus maintain the cycle

  18. Pu-238 assay performance with the Canberra IQ3 system

    International Nuclear Information System (INIS)

    Canberra Industries has recently completed a demonstration project at the Westinghouse Savannah River Site (WSRC) to characterize 55-gallon drums containing Pu-238 contaminated waste. The goal of this project was to detect and quantify Pu-238 contaminated waste. The goal of this project was to detect and quantify Pu-238 waste to detection limits of less than 50 nCi/g using gamma assay techniques. This would permit reclassification of these drums from transuranic (TRU) waste to low-level waste (LLW). The instrument used for this assay was a Canberra IQ3 high sensitivity gamma assay system, mounted in a trailer. The results of the measurements demonstrate achievement of detection levels as low as 1 nCi/g for low density waste drums, and good correlation with known concentrations in several test drums. In addition, the data demonstrates significant advantages for using large area low-energy germanium detectors for achieving the lowest possible MDAs for gamma rays in the 80-250 keV range. 1 fig., 2 tabs

  19. Pu-238 assay performance with the Canberra IQ3 system

    Energy Technology Data Exchange (ETDEWEB)

    Booth, L.; Gillespie, B.; Seaman, G.

    1997-11-01

    Canberra Industries has recently completed a demonstration project at the Westinghouse Savannah River Site (WSRC) to characterize 55-gallon drums containing Pu-238 contaminated waste. The goal of this project was to detect and quantify Pu-238 contaminated waste. The goal of this project was to detect and quantify Pu-238 waste to detection limits of less than 50 nCi/g using gamma assay techniques. This would permit reclassification of these drums from transuranic (TRU) waste to low-level waste (LLW). The instrument used for this assay was a Canberra IQ3 high sensitivity gamma assay system, mounted in a trailer. The results of the measurements demonstrate achievement of detection levels as low as 1 nCi/g for low density waste drums, and good correlation with known concentrations in several test drums. In addition, the data demonstrates significant advantages for using large area low-energy germanium detectors for achieving the lowest possible MDAs for gamma rays in the 80-250 keV range. 1 fig., 2 tabs.

  20. Uso de contraceptivos por puérperas adolescentes

    Directory of Open Access Journals (Sweden)

    Fernanda Schulz da Rosa

    2014-07-01

    Full Text Available Objetivo: Indagar el uso de métodos contraceptivos por las puérperas adolescentes a fin de relacionar su (desuso con el embarazo en la adolescencia. Método: Estudio transversal, descriptivo, realizado por medio de un instrumento estructurado con 181 puérperas adolescentes que tuvieron sus partos en el hospital participante de la investigación. Los datos fueron recolectados en el período de diciembre de 2008 a diciembre de 2009. Resultados: El 64,1% de las puérperas usaba algún método contraceptivo antes del embarazo; los métodos más utilizados fueron el anticoncepcional oral (51% y el preservativo masculino (29%. Para el 75% de las adolescentes el embarazo fue planeado y justificado por el deseo y la voluntad propia de experimentar la maternidad. Conclusión: Considerando que casi la mitad de las adolescentes entrevistadas deseaba el embarazo, se deduce que investigar y discutir apenas el uso o no de los métodos contraceptivos no es adecuado. Es necesario profundizar las investigaciones acerca de los significados de ser madre en la adolescencia.

  1. Meaning and safety of Pu-thermal utilization

    International Nuclear Information System (INIS)

    Application of plutonium at a thermal neutron reactor, so-called Pu-thermal is increasing a weight of position sharing a part of the nuclear fuel cycle policy in Japan, under present condition where development and actual use of a high breeder reactor were extremely delayed by unintended plan. On the other hand, as seen discussions on referendum at a site of nuclear power station, Pu-thermal is not always acquired on understanding of common peoples, and without deeper discussion at scientific and technical sides based on expected advancement its developmental affairs are felt to show its progress. Under such condition, here were reviewed on the following items on the meaning and safety of Pu-thermal utilization based on knowledges and informations at present point; 1) MOX fuel utilization in LWRs in nuclear fuel cycle, 2) nuclear properties of MOX fuel, 3) thermal properties and safety evaluation of MOX fuel, 4) behavior of MOX fuel, and 5) present condition on production technologies of MOX fuel. (G.K.)

  2. Polonium 210Po, uranium (234U, 238U and plutonium (238Pu, 239+240Pu bioaccumulation in marine birds

    Directory of Open Access Journals (Sweden)

    Strumińska-Parulska D. I.

    2013-04-01

    Full Text Available The aim of this work was the determination of 210Po, 234U, 238U, 238Pu and 239+240Pu concentration in marine birds which permanently or temporally live in the southern Baltic Sea coast. We chose 11 species of seabirds: three species permanently residing at southern Baltic Sea, four species of wintering birds and three species of migrating birds. The results show that analyzed radionuclides are non-uniformly distributed in the marine birds. The highest activities of 210Po were observed in feathers, muscles and liver. The highest uranium content was found in liver, rest of viscera and feathers, while plutonium in the digestion organs and feathers. Omnivore seabirds accumulated more polonium, plutonium than species that feed on fish, while herbivore seabirds accumulated more uranium than carnivore.

  3. Radiation chemistry of Pu and Np aqueous solutions

    International Nuclear Information System (INIS)

    Radiochemical reduction of NpO22+ and PuO22+ and oxidation of Np4+ in H2SO4 and HNO3 solutions under the action of γ- and α-radiation have been investigated. It has been shown that with increasing concentration [H2SO4] from 10-2 to 2x10-1M at dose rate I=2x1017 eV/ml.min the yields of the reduced ions G(-NpO22+) and G(-PuO22+) during γ-radiatiolysis decrease from 5.0 to 3.0 and from 3.5 to 1.2 ions/100 eV, respectively ([Me]=10-3M). When Isub(γ)=2x1015 ev/ml.min, G(-PuO22+) changes from 5.0 to 2.4 ions/100 eV in the same region of [H2SO4] ([Me]=10-2M). When [HNO3] changes from 10-2 to 10-1M, G(-PuO22+) falls down from 2.5 to 0.0 ions/100 eV (I=2x1017 eV/ml.min; [Me] = 10-3M). Dependences of the reduction yields on [H+], I, and [Me] in nitric and sulphuric acid solutions ( -1M) are explained by competition between the reactions proceeding in the bulk of the solution: MeO22+ + H2O2; MeO22+ + HO2; MeO22+ + OH+,a OH + OH, H2O2 + OH; H2O+OH. In HNO3 solution with concentration more than 10-2 M, the reaction H2O2+HNO2 plays a significant role. In HNO3 solution the dependence is found of G(-PuO22+) on [H+], Iα, and [Me] determined by competition between the reactions MeO22+ + H2O2, MeO22+ + HNO2, H2O2 + HNO2. The oxidation → of Np4+ ions in aerated solutions of H2SO4 and HNO3 (10-1-1.0M) change during γ-radiolysis from 14 to 15.5 and from 8.0 to 0.0 ions/100 eV. The mechanism of radiation oxidation of Np4+ ions has been considered

  4. 240Pu(n,f), 242Pu(n,f), 237Np(n,f), neutron fission cross sections, Esub(n) = 2.5 MeV

    International Nuclear Information System (INIS)

    Measurements of the absolute neutron fission cross section of 240Pu, 242Pu and 237Np have been made at 2.5 MeV using a hybrid detector. The fission events were detected in an ionization chamber (2π) and the neutron flux was determined by a proton recoil telescope and a directional long counter. Our values are compared to previous data

  5. Influence of the allotropic beta to alpha transformation and of oxygen on the distribution of plutonium in Zr-Pu and Ti-Pu dilute alloys

    CERN Document Server

    Languille, A; Remy, C

    1972-01-01

    Ti-Pu, Zr-Pu and Ti-U alloys, annealed above the transformation point, can show major segregation after cooling. The segregations increase with oxygen content. Annealing at high temperatures followed by severe quenching can cause them to disappear. (7 refs).

  6. Perturbation in the 240Pu/239Pu global fallout ratio in local sediment following the nuclear accidents at Thule (Greenland) and Palomares (Spain)

    International Nuclear Information System (INIS)

    It is well established that the main source of the plutonium found in marine sediments throughout the Northern Hemisphere is global stratospheric fallout, characterized by a typical 240Pu/239Pu atom ratio of ∼0.18. Measurements of perturbations in this ratio at various sites which had been subjected to close-in fallout, mainly from surface-based testing, has confirmed the feasibility of using this ratio to distinguish plutonium from different fallout sources. In the present study, the 240Pu/239Pu ratio has been examined in samples of sediment collected at Thule (Greenland) and Palomares (Spain), where accidents involving the release and dispersion of plutonium from fractured nuclear weapons occurred in 1968 and 1966, respectively. The 240Pu/239Pu ratio was measured by high-resolution alpha spectrometry and spectral deconvolution. The analytical results showed that at Thule the mean 240Pu/239Pu atom ratio was 0.033±0.004, while at Palomares the equivalent ratio appeared to be significantly higher at 0.056±0.003. Both ratios are consistent with those reported for soils samples at the Nevada site and Nagasaki, and are clearly indicative of weapons-grade plutonium. 27 refs., 1 fig., 2 tabs

  7. Early retention and distribution of monomeric 237Pu(IV) and 239Pu(IV) in C57BL/Do mice

    International Nuclear Information System (INIS)

    The early metabolism of monomeric Pu may depend upon its in vivo concentration, since in higher concentrations it may polymerize forming radiocolloids and be subject to phagocytosis. In this study the early biological behavior of 237Pu(IV) and 239Pu(IV), administered by intraperitoneal injection in citrate solution into C57BL/Do mice, is compared with the in vivo concentrations of these two nuclides differing by a factor of 105. 237Pu is also used as a γ-ray tracer of the α-emitting 239Pu in order to determine the latter's biological retention and tissue distribution. The results show no significant difference in the metabolism of the two nuclides throughout a 91 day serial sacrifice schedule. However, there is a significant sex dependence in the total body retention of Pu primarily due to a factor of 2.7 greater quantity of Pu excreted by the female during the first 24 hours post-injection. Furthermore, the half-time for removal of Pu from the livers of males is 42.7 +- 5.5 days and from livers of females 29.0 +- 2.7 days

  8. Using uncertainty analyses to test for differences in fractional transfers of 238Pu and 239+240Pu to cattle grazing a contaminated arid environment

    International Nuclear Information System (INIS)

    This paper reports the results of Monte Carlo uncertainty and sensitivity analyses of the modeled fractional transfers of 238Pu and 239+240Pu from the gastrointestinal tract to the tissues of cattle that grazed a plutonium contaminated arid site near the Nevada Test Site. The analyses were conducted to assess the uncertainty in model parameters for the purpose of testing if the fractional transfer of 238Pu was greater than that of 239+240Pu to the tissues of the cattle. A sensitivity analysis of the fractional transfer model indicated that the Pu tissue concentration was the model parameter that had the highest correlation with computed fractional transfers. It was shown that accurate information on the variability of tissue concentrations is needed to obtain accurate estimates of the uncertainty of modeled fractional transfers. 34 refs., 3 figs., 5 tabs

  9. Thermodynamic assessments of the Pu–Zn and La–Pu systems

    International Nuclear Information System (INIS)

    Highlights: • The Pu–Zn and La–Pu binary systems have been assessed by using the CALPHAD method for the first time. • The intermetallic compounds which have homogeneity range were described by the two-sublattice model. • The parameters of the Pu–Zn and La–Pu binary systems can serve as a part of the thermodynamic database for nuclear materials. • The calculated results are in good agreement with the experimental data. - Abstract: The thermodynamic description of the Pu–Zn and La–Pu systems were obtained using the CALPHAD (Calculation of Phase Diagrams) method on the basis of experimental information for phase equilibria and thermodynamic properties. The Gibbs free energies of the liquid, (εPu), (δ′Pu), (δPu), (γLa) and (βLa) phases were described by the subregular solution model. Seven intermetallic compounds (PuZn2, Pu13Zn58, Pu3Zn22, Pu2Zn17, κ, κ′, and λ) were modeled by the sublattice model. A reasonable agreement between the present calculated results and experimental data has been achieved with a set of optimized parameters

  10. Current research into the self-irradiation effects of δ-phase Pu-Ga alloys

    International Nuclear Information System (INIS)

    Delta-phase Pu-Ga alloys (δ-Pu) radiogenically age unlike most face-centered cubic (FCC) metals such as austenitic steels, Al, Cu, and other structural alloys when exposed to irradiation. If it did, it would exhibit void swelling at 20-40 years of age or 2-4 dpa. Why doesn't δ-Pu void swell? Will aging δ-Pu start to void swell sometime in the future? Currently, we don't know the answers to these questions. Pu is a notoriously unstable metallic element with multiple phases and the properties of technological Pu alloys are changing with time due to Pu α-decay. The most influential drivers for radiogenic change in δ-Pu are He ingrowth, radiation-induced lattice defect accumulation and phase instability of δ-Pu. Each of these drivers induces changes that depend on temperature, Ga concentration, radioactive α-decay dose, and α-decay rate and have profound implications for materials chemistry, physics and engineering. How do these radiogenic products interact with each other with an inherently unstable lattice? When lattice damage recovery processes do occur, is it complete or do residual effects remain? Because each driver has a different dependence on these controllable variables, the appropriate set of theory, computation and experiments can provide a unique opportunity to determine accurately the strength of each driver in determining the response of Pu to radiogenic processes

  11. Pb-210 and Pu-239,240 in nearshore Gulf of Mexico sediments

    International Nuclear Information System (INIS)

    Pb-210, Ra-226, and Pu-239,240 activities were measured in nearshore Gulf of Mexico sediments. Sediment cores were collected from the Mississippi delta, and the western Gulf of Mexico shelf. Mississippi delta cores which exhibit significantly higher sedimentation rates show larger inventories of Pb-210. The measured Pu levels from the western shelf are lower than from the delta at comparable depths. In three of the western shelf cores, the observed Pu inventory is considerably less than predicted from atmospheric flux. Therefore, Pu is not being removed to the sediment, or is being released following deposition. A key difference between these isotopes is that Pu exists in a less particle-reactive state. The ratio of excess Pb-210 to Pu levels increases with water depth in the delta and the western shelf. Water depth acts as an integrator of depth-sensitive processes. Pu scavenging is more sensitive to these processes. A sub-surface Pu maximum has been observed. Excess Pb-210 and Pu levels correlate well with sedimentation rates. This suggests that particle flux is important in removal of Pb-210 and Pu to the sediment. The flux of Mn out of the sediment is correlated with inventory data, suggesting that redox cycling of Mn may play a role in increasing Pb-210 and Pu sediment inventories. It is unclear whether the effects of increased sedimentation rates and increased Mn fluxes can be evaluated independently. Mixing of surface sediment correlates with inventory data. Increased sediment mixing allows for additional scavenging of Pb-210 and Pu from overlying waters. Mixing of sediment at depths below the mixed surface layer may play a role in increasing sediment inventories of Pb-210 and Pu

  12. Disposition of weapon-grade plutonium with pebble bed type HTGRs using Pu burner balls and Th breeder balls

    International Nuclear Information System (INIS)

    A concept of reactor system was developed with which weapons-grade plutonium could be made perfectly worthless in use for weapons. It is a pebble bed type HTGR using Pu burner ball fuels and Th breeder ball fuels. The residual amounts of 239Pu in spent Pu balls become less than 1% of the initial loading. Furthermore, a method was found that the power coefficient could be made negative by heavy Pu loading in the Pu burner ball fuels

  13. Sequential determination of 239,240Pu, 238 Pu, 241 Am and 90Sr in radioactive wastes using SPE sorbents Analig Pu02, AnaLig Sr01 and TRU Resin

    International Nuclear Information System (INIS)

    A simple and rapid method of the sequential determination of radionuclides 239,240Pu, 238 Pu, 241 Am and 90Sr in radioactive sludge from the NPP Bohunice A1 with high radiochemical yields and efficient removal of interfering components from a matrix was developed. Separation method combines SPE sorbents Analig Pu02, AnaLig Sr01 made by IBC Advanced Technologies and TRU Resin (Eichrom Technologies) placed in tandem. Advantage of a single-stage column located on the vacuum box with a rapid flow is an effective pre-concentration and separation of radionuclides and minimization of sample separation time. (authors)

  14. Reaction kinetics of irradiation prepolymerized MMA-PU IPN by 5DXC FTIR

    International Nuclear Information System (INIS)

    The reaction kinetics of irradiation-prepolymerized MMA-PU (polyether) IPNs have been studied by FTIR. The results indicate that the polymerization of each component in the IPN follows its normal distinct reaction mechanism with no mutual interference. Increasing the concentration of TMPTAM (crosslinking agent of PMMA) increased the formation rate of PMMA, while the formation rate of PU networks remained almost the same. Increasing the concentration of TMP (crosslinking agent of PU) increased the formation rate of PU, while the formation rate of PMMA networks decreased. The formation rate of PU was obviously faster than that of PMMA. A theory for the cage effect of the PU network has been proposed. (author)

  15. Fabrication of gamma sources using the neutron-gamma reactions of 238Pu13C

    International Nuclear Information System (INIS)

    A production campaign for 238Pu13C sources with gamma fluence ranging from 2500 to 4500 gamma/s/4π at 6.13 MeV was carried out in 2002 in Atalante. An experimental study was undertaken to prepare the 238PuC mixture, which is the most delicate step. This procedure is described together with the other steps in the source fabrication process: purification of a plutonium oxide batch, preparation of a nitric solution of 238Pu, measurement of the gamma fluence of the PuC mixture before and after insertion into each of the two stainless steel capsules that constitute a PuN2O package, welding of the second envelope followed by leak testing, final measurement of the gamma fluence of the sealed source. This PuC sources fabrication procedure is effective: all the sources include the required gamma activity with an uncertainty on the gamma fluence of less than 10%. (authors)

  16. Low level 239PuO2 life-span studies

    International Nuclear Information System (INIS)

    The purpose of this projet is to determine the dose-response curve for lung-tumor incidence in rats following inhalation of 239PuO2 at levels producing a lifespan radiation dose of 2 to 100 rad. In preliminary studies, rats were intratracheally instilled with, or inhaled 169Yb-239PuO2 or 169Yb-Yb2O3 particles. Whole-body, excreta and tissue levels of 169Yb were determined by external gamma counting; 239Pu levels were determined radiochemically by scintillation counting. It was found that 169Yb dissociated from 239PuO2 and was cleared more rapidly from the lung and the whole body. Despite this fact, however, whole-body counts performed at 7 days after exposure to 169Yb-239PuO2 gave a reproducible measure of the 239Pu lung burden

  17. Disposition of plutonium with HTGRs using Pu burner balls and Th breeder balls

    International Nuclear Information System (INIS)

    A concept of reactor system was developed with which weapons-grade Plutonium could be made perfectly worthless in use for weapons. It is a pebble bed type HTGR using Pu burner ball fuels and Th breeder ball fuels. The residual amounts of 239Pu in spent Pu balls become less than 1% of the initial loading. The power coefficient was made negative by reducing the parasitic neutron absorption reaction rate of 135Xe. (author)

  18. Plutonium Usage and Management in PWR and Computing and Physical Methods to Calculate Pu

    International Nuclear Information System (INIS)

    Main limitations due to the enhancement of the plutonium content are related to the coolant void effect as the spectrum becomes faster, the neutron flux in the thermal region tends towards zero and is concentrated in the region from 10 keV to 1 MeV. Thus, all captures by Pu240 and Pu242 in the thermal and epithermal resonance disappear and the Pu240 and Pu242 contributions to the void effect become positive. The higher the Pu content and the poorer the Pu quality, the larger the void effect. -The core control in nominal or transient conditions. Pu enrichment leads to a decrease in βeff. and the efficiency of soluble boron and control rods. Also, the Doppler effect tends to decrease when Pu replaces U, so, that in case of transients the core could diverge again if the control is not effective enough. -As for the voiding effect, the plutonium degradation and the Pu240 and Pu242 accumulation after multiple recycling lead to spectrum hardening and to a decrease in control. -One solution would be to use enriched boron in soluble boron and shutdown rods. -In this paper I discuss and show the advanced computing and physical methods to calculate Pu inside the nuclear reactors and glovebox and the different solutions to be used to overcome the difficulties that affect on safety parameters and on reactor performance, and analysis the consequences of plutonium management on the whole fuel cycle like Raw materials savings, fraction of nuclear electric power involved in the Pu management. All through two types of scenario, one involving a low fraction of the nuclear park dedicated to plutonium management, the other involving a dilution of the plutonium in all the nuclear park. (author)

  19. Extraction and recovery of Pu from oxalate bearing waste solutions using CMPO

    International Nuclear Information System (INIS)

    A mixture of octyl (phenyl)-N-N-diisobutyl carbamoyl methyl phosphine oxide (CMPO) and tri butyl phosphate (TBP) in dodecane has been deployed for the extraction and recovery of Pu from solutions containing various Pu, oxalic acid and nitric acid concentrations. Pu could be efficiently extracted from such solutions. It could be almost quantitatively recovered from the organic phase by precipitating with oxalic acid containing calcium nitrate as the carrier. (author). 3 refs., 3 tabs

  20. A biamperometric method for the determination of uranium in PuO2

    International Nuclear Information System (INIS)

    The Ti(III) reduction and biamperometric titration method for U determination has been evaluated for determinations in the 5 to 50 μg range in pure solutions as well as in presence of Pu up to a U : Pu ratio of 1: 500. This simple titrimetric method has been employed for the determination of U present as low as 0.2% in PuO2 samples without separation. (author)

  1. Pu(V) reduction and enhancement of particle-water partitioning by exopolymeric substances

    International Nuclear Information System (INIS)

    Central to understanding the environmental behavior of Pu in vadose- and saturated-zones, as well as waste streams, is the contribution of colloidal natural organic mater (NOM), e.g., biopolymeric exopolymeric substances (EPS) from Pseudomonas fluorescens Biovar II and geopolymeric humic acids (HA), to Pu speciation. Because Pu(V) and Pu(IV) are present in aquatic systems at sub-pM concentrations, many established techniques for chemical speciation and oxidation state determination are not available. However, the two redox states of Pu can be distinguished through their tendency to form colloidal species. Controlled laboratory experiments with low-colloid background solutions of 0.1 M NaClO4 with an inert buffer (Tris) and 5 μm silica particles of high specific surface area (500 m2/g) and small (3 nm) pores investigated the ability of NOM compounds for their binding and redox qualities showed that: (1) Pu(V) and Pu(IV) tracers at pM concentrations could be distinguished by their tendency to bind to colloidal species (≥ 1 kDa), with binding extent being high for Pu(IV), and low for Pu(V); (2) EPS can significantly enhance particle- (or colloid-) water partition coefficients to silica particles (Kd, Kdc), quickly (1 day) for Pu(IV) and slowly (1 month) for Pu(V); (3) Pu(V), in the presence of EPS and silica particles can become associated with particles and colloids over periods of months, likely indicating reduction: (4) Kd values can be affected by the reaction sequence of tracer addition to the solution containing silica particles and NOM compounds (e.g., EPS or HA). (orig.)

  2. Automated homogeneous oxalate precipitation of Pu(III)

    International Nuclear Information System (INIS)

    Homogeneous oxalate precipitation using diethyl oxalate was compared to precipitating Pu(III) oxalate with solid oxalic acid. The diethyl oxalate technique at 75 degree C is better because it gives 50% less plutonium in the filtrate with a reasonable filtering time. Also, the procedure for the homogeneous precipitation is easier to automate because the liquid diethyl oxalate is simpler to introduce into the precipitator than solid oxalic acid. It also provides flexibility because the hydrolysis rate and therefore the precipitation rate can be controlled by varying the temperature. 5 refs., 3 figs., 3 tabs

  3. DOE plutonium disposition study: Pu consumption in ALWRs

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE's System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE's Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document Volume 2, provides a discussion of: Plutonium Fuel Cycle; Technology Needs; Regulatory Considerations; Cost and Schedule Estimates; and Deployment Strategy

  4. Neutron Resonance Parameters and Covariance Matrix of 239Pu

    Energy Technology Data Exchange (ETDEWEB)

    Derrien, Herve [ORNL; Leal, Luiz C [ORNL; Larson, Nancy M [ORNL

    2008-08-01

    In order to obtain the resonance parameters in a single energy range and the corresponding covariance matrix, a reevaluation of 239Pu was performed with the code SAMMY. The most recent experimental data were analyzed or reanalyzed in the energy range thermal to 2.5 keV. The normalization of the fission cross section data was reconsidered by taking into account the most recent measurements of Weston et al. and Wagemans et al. A full resonance parameter covariance matrix was generated. The method used to obtain realistic uncertainties on the average cross section calculated by SAMMY or other processing codes was examined.

  5. A 233U/236U/242Pu/244Pu spike for isotopic and isotope dilution analysis by mass spectrometry with internal calibration

    International Nuclear Information System (INIS)

    The Khlopin Radium Institute prepared on behalf of the IAEA a synthetic mixture of 233U, 236U, 242Pu and 244Pu isotopes. The isotopic composition and elemental concentration of uranium and plutonium were certified on the basis of analyses done by four laboratories of the IAEA Network, using mass spectrometry with internal standardization. The certified values for 233U/236U ratio and the 236U chemical concentration have a coefficient of variation of 0.05%. The latter is fixed by the uncertainty in the 235U/238U ratio of NBS500 used as internal standard. The coefficients of variation of the 244Pu/242Pu ratio and the 242Pu chemical concentration are respectively 0.10% and 0.16% and limited by the uncertainty in the 240Pu/239Pu ratio of NBS947. This four isotope mixture was used as an internal standard as well as a spike, to analyze 30 batches of LWR spent fuel solutions. The repeatability of the mass spectrometric measurements have a coefficient of variation of 0.025% for the uranium concentration, and of 0.039% for the plutonium concentration. The spiking and treatment errors had a coefficient of variation of 0.048%. (author). Refs, figs and tabs

  6. The AS-76 interlaboratory experiment on the alpha spectrometric determination of Pu-238. Pt. 3

    International Nuclear Information System (INIS)

    Four plutonium samples containing 0.2, 0.8, 1.6 and 0.9 Atom% of 238Pu have been prepared for the Interlaboratory Experiment AS-76. Of these, three were input solutions from a reprocessing plant. The fourth sample was from a plutonium product solution. These samples have been characterized by two alpha spectrometry laboratories and two mass spectrometry laboratories to certify the ratio of alpha activities 238Pu/(239Pu + 240Pu) and the isotopic composition, respectively. (orig.) 891 HP/orig. 892 MKO

  7. Determination of plutonium in nitric acid solution by spectrophotometry of Pu(VI), (2)

    International Nuclear Information System (INIS)

    Effects of co-existing agent and of Pu(IV)-polymer formation on the oxidation of Pu(IV) to Pu(VI) by Ce(IV) has been investigated in connection with the spectrophotometric determination of plutonium in nitric acid solution which includes the measurement of absorbance at 833 nm due to Pu(VI) after oxidizing plutonium ion into Pu(VI). Hydrogen peroxide and nitrite ions were dealt with as interfering species because these are most main radiolysis products in nitric acid solution. If 4 times or more concentration of Ce(IV) than that of hydrogen peroxide or nitrite ion is added to the sample solution, plutonium ion can be converted to Pu(VI) quantitatively even in the presence of these agents. Plutonium(IV) forming its polymer is hard to be oxidized to Pu(VI) by Ce(IV). The oxidation rate of Pu(IV)-polymer increases with the increase of the acid concentration of the solution. It takes, however, more than 1 hour to attain complete oxidation of polymer into Pu(VI) even in 3 M nitric acid solution. (author)

  8. Mass spectrometric studies of the vapour phase in the (Pu + O) system

    International Nuclear Information System (INIS)

    Highlights: → Vapour pressure measurements performed at high temperatures on PuO2-x samples. → Experimental facility consisted of a Knudsen cell coupled with a mass spectrometer. → Partial pressures of gaseous species were assessed from ionisation efficiency curves. → (Pu + O) system was studied for stoichiometry corresponding to O/M from 1.5 to 2.0. - Abstract: Vapour pressure measurements at high temperatures have been performed on plutonium oxide samples using a Knudsen cell coupled with a mass spectrometer. Different experimental conditions were applied for the derivation of the solid-gas phase relations for three composition in the Pu-O phase diagram: the (Pu2O3-PuO2-x) two-phase domain, the congruent vapourisation composition and near stoichiometric PuO2.00. The partial pressures of the gaseous species PuO2, PuO, and Pu were assessed from ionisation efficiency curves recorded at constant temperature. The vapour pressure results for different phase fields were discussed together with all the available literature data.

  9. PU.1 Suppresses Th2 Cytokine Expression via Silencing of GATA3 Transcription in Dendritic Cells

    OpenAIRE

    Yashiro, Takuya; Kubo, Masato; Ogawa, Hideoki; Okumura, Ko; Nishiyama, Chiharu

    2015-01-01

    The transcription factor PU.1 is predominantly expressed in dendritic cells (DCs) and is essential for DC differentiation. Although there are several reports that PU.1 positively regulates the expression of DC-specific genes, whether PU.1 also has a suppressive effect on DCs is largely unknown. Here we demonstrate that PU.1 suppresses the expression of Th2 cytokines including IL-13 and IL-5 in bone marrow-derived DCs (BMDCs), through repression of the expression of GATA3, which is a master re...

  10. Plutonium(IV) peroxide formation in nitric medium and kinetics Pu(VI) reduction by hydrogen peroxide

    International Nuclear Information System (INIS)

    Reduction of plutonium (VI) to Pu(IV) with hydrogen peroxide is a step in industrial processes used to purify plutonium nitrate solutions. This operation must be carefully controlled, in order to avoid any formation of the Pu(IV) peroxide green precipitate and to obtain exclusively Pu(IV). This led us to study the acidity and Pu and H2O2 concentrations influences on the precipitate appearance and to perform a Pu(VI) reduction kinetic study on a wide range of acidities ([HNO3]: 0.5 to 8 M), plutonium concentrations ([Pu(VI)]: 0.1 to 0.8 M) and [H2O2]/[Pu(VI)] ratio (from 1 to 8). Thus, the domain of Pu(IV) peroxide formation and the reactional paths were established. With the exception of 0.5 M nitric acid medium, the kinetic curves show two distinct regims: the first one corresponds to an induction period where the Pu(VI) concentration doesn't change, the second corresponds to a linear decrease of Pu(VI). An increase of the temperature greatly accelerates the Pu(VI) reduction rate while [H2O2]/[Pu(VI)] has almost no influence. The Pu(VI) total reduction time decreases when initial concentration of plutonium increases. By increasing nitric acid concentration from 0.5 M to 6 M, the total Pu(VI) reduction time decreases. This time increases when [HNO3] varies from 6 M to 8 M. (orig.)

  11. Indication of single-crystal PuO2 oxidation from O 1s x-ray absorption spectra

    Science.gov (United States)

    Modin, A.; Yun, Y.; Suzuki, M.-T.; Vegelius, J.; Werme, L.; Nordgren, J.; Oppeneer, P. M.; Butorin, S. M.

    2011-02-01

    The electronic structure of single-crystal PuO2 is studied using O 1s x-ray absorption (XA) and x-ray emission. Interpretation of the experimental data is supported by extensive first-principles calculations on the basis of the densityfunctionaltheory+U approach. The measured XA spectra show a significant difference in intensity for the first two peaks between different spots or areas on the single crystal. Our theoretical simulations show that the first peak, at ~531 eV, can be attributed to O 2p-Pu 5f hybridization, while the second peak, at ~533.4 eV, is due to hybridization of O 2p with Pu d states. The reasons for the observed differences in the O 1s XA spectra are explored by calculating a number of defect structures PuO2±x as well as by simulating the existence of Pu(V) sites. Our results indicate the presence of oxidation states higher than Pu(IV) in some areas of the single crystal. The findings also suggest that plutonium oxide with a Pu fraction in an oxidation state higher than Pu(IV) consists of inequivalent Pu sites with Pu(IV)O2 and Pu(V)O2 rather than representing a system where the Pu oxidation state is constantly fluctuating between Pu(IV) and Pu(V).

  12. Perturbation in the 240Pu/239Pu global fallout ratio in local sediments following the nuclear accidents at Thule (Greenland) and Palomares (Spain).

    Science.gov (United States)

    Mitchell, P I; León Vintró, L; Dahlgaard, H; Gascó, C; Sánchez-Cabeza, J A

    1997-08-25

    It is well established that the main source of the plutonium found in marine sediments throughout the Northern Hemisphere is global stratospheric fallout, characterized by a typical 240Pu/239Pu atom ratio of approximately 0.18. Measurement of perturbations in this ratio at various sites which had been subjected to close-in fallout, mainly from surface-based testing (e.g. Bikini Atoll, Nevada test site, Mururoa Atoll), has confirmed the feasibility of using this ratio to distinguish plutonium from different fallout sources. In the present study, the 240Pu/239Pu ratio has been examined in samples of sediment (and soil) collected at Thule (Greenland) and Palomares (Spain), where accidents involving the release and dispersion of plutonium from fractured nuclear weapons occurred in 1968 and 1966, respectively. The 240Pu/239Pu ratio was measured by high-resolution alpha spectrometry and spectral deconvolution, and confirmed in the case of the most active samples by high-resolution X-ray spectrometry. Only samples which displayed plutonium heterogeneities, i.e. hot particles or concentrations well in excess (at least two orders of magnitude) of those expected from global fallout, were selected for analysis. The analytical results showed that at Thule the mean 240Pu/239Pu atom ratio was 0.033 +/- 0.004 (n = 4), while at Palomares the equivalent ratio appeared to be significantly higher at 0.056 +/- 0.003 (n = 4). Both ratios are indicative of low burn-up plutonium and are consistent with those reported for weapons-grade plutonium. It is noteworthy that the mean 238Pu/239Pu activity ratio in the Thule samples, at 0.0150 +/- 0.0017 (n = 4), was also lower than that measured in the Palomares samples, namely, 0.0275 +/- 0.0012 (n = 4). The 241Pu/239Pu ratios were similarly different. Finally, the data show, in contrast to Palomares, that not all of the samples from the Thule accident site were contaminated with plutonium of identical isotopic composition. PMID:9241884

  13. Characterization of a neutron source of 239PuBe

    International Nuclear Information System (INIS)

    The spectrum equivalent dose and environmental equivalent dose f a 239PuBe source have been determined. The appropriate handling of a neutron source depends on the knowledge of its characteristics, such as its energy distribution, total rate of flowing and dosimetric magnitudes. In many facilities have not spectrometer that allows to determine the spectrum and then area monitors are used that give a dosimetric magnitude starting from measuring the flowing rate and the use of conversion factors, however this procedure has many limitations and it is preferable to measure the spectra and starting from this information the interest dosimetric magnitudes are calculated. In this work a Bonner sphere spectrometer has been used with a 6LiI(Eu) scintillator obtaining the count rates that produce, to a distance of 100 cm, a 239PuBe source of 1.85E(11) Bq. The spectrum was reconstructed starting from the count rates using BUNKIUT code and response matrix UTA4. With the spectrum information was calculated the source intensity, total flow, energy average, equivalent dose rate, environmental equivalent dose rate, equivalent dose coefficient and environmental equivalent dose coefficient. By means of two area monitors for neutrons, Eberline ASP-1 and LB 6411 of Berthold the equivalent dose and environmental equivalent dose were measured. The determinate values were compared with those reported in literature and it found that are coincident inside 17%. (Author)

  14. Electrodialysis of Pu-contaminated ammonium nitrate solution

    International Nuclear Information System (INIS)

    Ammonium nitrate is the major component of Pu-contaminated liquid waste generated at the Pu-fuel facilities, and its safe decomposition was experimented by the method of electrodialysis. The process consists of two steps. The one is the electrodialysis of ammonium nitrate to ammonium nitrite in aqueous solution, and the other is the thermal decomposition of the ammonium nitrite to water and nitrogen gas also in aqueous solution. A thermal decomposition column and a heat exchanger were used for the continuous decomposition experiments. The membrane was a cation exchange membrane, the anolyte was 0.1 - 0.5 mol nitric acid, the catholyte was 10 - 50 weight % ammonium nitrate, and the current density was 10 - 50 amp/dm2. The experimental results of the pH and temperature effects on the current efficiency show that electrodialysis is preferable in alkaline region and at lower temperature. It is important to control such minor reactions as ammonium hydroxide byproduction as little as possible. The minor reaction of nitrogen gas generation greatly reduces the current efficiency of ammonium nitrite production. The best current efficiency achieved in the experiments was 85% by selecting the best operating conditions. In order to achieve high current efficiency in electrodialysis, the selection of electrolyzer composition, anode, cation exchange membrane, etc. is indispensable. It is generally preferable to choose the metal which has high hydrogen overvoltage to achieve high current efficiency by controlling hydrogen gas generation. (Wakatsuki, Y.)

  15. Ionospheric perturbations before Pu'er earthquake observed on DEMETER

    Institute of Scientific and Technical Information of China (English)

    ZHU Rong; YANG Dong-mei; JING Feng; YANG Jun-ying; OUYANG Xin-yan

    2008-01-01

    A destructive shock with magnitude of 6.3 occurred on 2 June 2007 at 21h34min56s UT in Pu'er region (23.0°N, 101.1°E), Yunnan Province, China. The data from DEMETER satellite during the period from 23 May to 2 June, i.e., ten days before the earthquake and one day just on the day of earthquake occurrence, were analyzed. Among the 284 orbits of DEMETER during the period, 29 orbits with the trace passing through the region within 1 888 km from the epicenter were selected to be studied. Seven anomalous events were found on the dataset of the seven orbits among the 29 ones. There existed synchronous perturbations on the variations of the spectrogram of the electric field and the variations of the density and temperature of the ions and electron, in contrast with the variations of its surrounding area. And five events appeared in the space within 1 888 km from the epicenter while the other two were out of the studied area. Electrostatic turbulences were also recorded with the synchronous perturbations with that in the electron density and ions density in plasma in the region near the epicenter in the five events, which seems to suggest that there be some physical relation between these events and the preparation processes of Pu'er earthquake.

  16. Decommissioning of a 239Pu contaminated incinerator facility

    International Nuclear Information System (INIS)

    In early 1978, a plutonium contaminated incinerator facility at the Los Alamos Scientific Laboratory (LASL), Los Alamos, New Mexico, was decommissioned. The project involved dismantling the facility and disposal by burial or by retrievable storage of the debri at an on-site waste disposal area. Contaminated soil from the 0.5 hectare area was buried. The facility was constructed in 1951 to incinerate plutonium contaminated wastes. It was later used as a decontamination facility. The major features included a 185 m2 control building, incinerator, cyclone dust collector, spray cooler, venturi scrubber, air filter bank, ash separator, and two 140,000 litres ash storage tanks. Preliminary soil contamination surveys were performed by a LASL developed portable phoswich detector system. Final soil contamination levels were measured with a zinc sulphide gross alpha scintillation system. Six hundred cubic metres of debris and 1200 m3 of soil contaminated with less than 10 nCi 239 Pu/g were buried at the LASL disposal area. Five cubic metres of 239 Pu contaminated ash residues were packed and stored to meet the Department of Energy's 20 year retrievable storage criteria. (author)

  17. On the Multi-Reference Nature of Plutonium Oxides: PuO$_2^{2+}$, PuO$_2$, PuO$_3$ and PuO$_2$(OH)$_2$

    CERN Document Server

    Boguslawski, Katharina; Tecmer, Paweł; Duperrouzel, Corinne; Gomes, André Severo Pereira; Legeza, Örs; Ayers, Paul W; Vallet, Valérie

    2016-01-01

    Actinide-containing complexes present formidable challenges for electronic structure methods due to the large number of degenerate or quasi-degenerate electronic states arising from partially occupied 5f and 6d shells. Conventional multi-reference methods can treat active spaces that are often at the upper limit of what is required for a proper treatment of species with complex electronic structures, leaving no room for verifying their suitability. In this work we address the issue of properly defining the active spaces in such calculations, and introduce a protocol to determine optimal active spaces based on the use of the Density Matrix Renormalization Group algorithm and concepts of quantum information theory. We apply the protocol to elucidate the electronic structure and bonding mechanism of volatile plutonium oxides (PuO$_3$ and PuO$_2$(OH)$_2$), species associated with nuclear safety issues for which little is known about the electronic structure and energetics. We show how, within a scalar relativisti...

  18. Calibration of the ERL cavity FPC and PU couplers

    Energy Technology Data Exchange (ETDEWEB)

    Hahn, H.; Johnson, E.; Kayran, D.

    2010-04-05

    The performance parameters of a superconducting cavity, notably accelerating field and quality factor, are first obtained in a cryogenic vertical test Dewar, and again after the final assembly in its cryostat. The tests involve Network Analyzer (NA) measurements in which the cavity is excited through an input coupler and the properties are obtained from the reflected signal at the input and the transmitted signal from the output coupler. The interpretation of the scattering coefficients in terms of field strength requires the knowledge of the Fundamental Power Coupler (FPC) and Pick-Up (PU) coupler strength, as expressed by their 'external' and Q{sub FPC} Q{sub PU}. The coupler strength is independent of the field level or cavity losses and thus can be determined at low levels with the scattering coefficients S{sub 11} and S{sub 21}, assuming standard 50 {Omega} terminations in the network analyzer. Also needed is the intrinsic cavity parameter, R{sub a} /Q{sub 0} {triple_bond} {l_brace}R/Q{r_brace}, a quantity independent of field or losses which must be obtained from simulation programs, such as the Microwave Studio.

  19. Thermal Analysis of ZPPR High Pu Content Stored Fuel

    International Nuclear Information System (INIS)

    The Zero Power Physics Reactor (ZPPR) operated from April 18, 1969, until 1990. ZPPR operated at low power for testing nuclear reactor designs. This paper examines the temperature of Pu content ZPPR fuel while it is in storage. Heat is generated in the fuel due to Pu and Am decay and is a concern for possible cladding damage. Damage to the cladding could lead to fuel hydriding and oxidizing. A series of computer simulations were made to determine the range of temperatures potentially occuring in the ZPPR fuel. The maximum calculated fuel temperature is 292°C (558°F). Conservative assumptions in the model intentionally overestimate temperatures. The stored fuel temperatures are dependent on the distribution of fuel in the surrounding storage compartments, the heat generation rate of the fuel, and the orientation of fuel. Direct fuel temperatures could not be measured but storage bin doors, storage sleeve doors, and storage canister temperatures were measured. Comparison of these three temperatures to the calculations indicates that the temperatures calculated with conservative assumptions are, as expected, higher than the actual temperatures. The maximum calculated fuel temperature with the most conservative assumptions is significantly below the fuel failure criterion of 600°C (1,112°F)

  20. Complicaciones en las puérperas laparotomizadas de urgencia

    Directory of Open Access Journals (Sweden)

    Victor Manuel Sierra Alfonso

    2014-11-01

    Full Text Available La presencia de una complicación intrabdominal postoperatoria después de una laparotomía agrava el estado de salud del paciente y ensombrece el pronóstico, a pesar del uso adecuado de antimicrobianos, de la correcta nutrición y de las ventajas de los cuidados intensivos. Se realizó un estudio retrospectivo descriptivo, con el objetivo de caracterizar las complicaciones en las puérperas, a las que se les practicaron laparotomías de urgencia. Se analizaron las referidas pacientes atendidas en el Hospital Ginecoobstétrico “Piti Fajardo” y en el Hospital General Docente “Aleida Fernández Chardiet”, en el periodo comprendido entre enero del 2010 y diciembre del 2012. La muestra quedó conformada por nueve pacientes. Las complicaciones más presentadas fueron los trastornos hidroelectrolíticos y los trastornos del equilibrio ácido básico. No hubo muerte materna ni fetal. Las puérperas que más complicaciones presentaron fueron las de 35 años y más, con diagnóstico de placenta acreta, hematoma de la cúpula vaginal y atonía uterina. El tiempo de evolución hasta el tratamiento definitivo fue menor de 12 horas

  1. Study of new U(VI) and Pu(VI) coprecipitation methods for the preparation of (U,Pu)O2

    International Nuclear Information System (INIS)

    Two U(VI) and Pu(VI) coprecipitation methods have been studied, for the definition of new processes to prepare (U,Pu)O2 mixed oxides suitable for making MoX fuels or fast breeder reactor fuels. The first system is based on the coprecipitation of a new U(VI), Pu(VI) compound; ammonium uranoplutonate, where as a second system is related to the precipitation of uranyl plutonyl monocarbonate. Experimental conditions to optimize the precipitation and the filtration steps of these two systems have been determined. After calcination under reducing conditions, the mixed oxides obtained are characterized according to different techniques: granulometry, thermogravimetry, solubility in boiling HNO3 solutions. The properties of such oxides are excellent. The possible processes for preparing (U, Pu)O2 using these new routes are compared with those actually exploited

  2. Alpha-n and spontaneous fission sources and spectra from individual plutonium isotopes in PuF4 and PuO2

    International Nuclear Information System (INIS)

    Plutonium-containing compounds vary widely in isotopic content, and as a result, the dose as function of isotopic content also varies considerably. Determination of the dose from neutrons, decay and capture gammas from plutonium in the form of compounds thus requires that the spontaneous fission and (α,n) source and spectra from each individual isotope be known. To facilitate dose calculations from plutonium-containing compounds, we have calculated the spontaneous fission and (α,n) sources and spectra for 1 g of each of the plutonium isotopes in the form of either PuF4 or PuO2. As 241Am is often a component in a mixture of plutonium isotopic compounds, the source and spectra from 1 g of 241Am mixed with PuF4 or PuO2 has also been determined. Using these results, the neutron source and spectra may be determined for any sample composition. 2 refs., 3 tabs

  3. Bioreduction amenability testing of actinide contaminated soils. The systems: Am241-Pu238, Am241-Pu239/40, U

    International Nuclear Information System (INIS)

    Bioreductive processing of actinide contaminated soils can achieve extraction levels in excess of 97% for both plutonium and uranium contaminants. Reasonable reaction rates of 4 to 6 day resident times for Pu-Am have been demonstrated on 4 gram sample charges. Longer reaction times of 17 days required for uranium extraction can be improved by soil sample preconditioning and/or an increase in process reagent concentrations. The environmentally benign treatment process operates at pH 6--7, preserves the original soil matrix, and utilizes standard processing equipment. The process reagent component (inoculum SD-1 and biological growth medium PX100 trademark) are available for utilization in an integrated system. Process techniques developed by MBX, involving graduated volume bioreactors have been proven to alleviate biological toxicity problems in treatment leachates. Bioreduction processing of actinide contaminated soils, preconditioning of soil charges, and recycling or vegetation of unacceptable tailings can be combined to provide an effective and environmentally attractive method of remediation. The soil test program was designed to determine the applicability of the MBX bioreductive technology to solubilize Pu and Am from RFP, Mound and LANL soils and uranium from Hanford and Fernald soils

  4. Evaluation of the thermal-neutron constants for 233U, 235U, 239Pu and 241Pu

    International Nuclear Information System (INIS)

    A consistent set of best values of the 2200 meter/second neutron cross sections, Westcott g-factors, and fission neutron yields for 233U, 235U, 239Pu and 241Pu are presented. A least squares fitting program, LSF, is used to obtain the best fit and to estimate the sensitivity of these fissile parameters to the quoted uncertainties in experimental data. The half-lives of the uranium and plutonium nuclides have been evaluated and these have been used to reassess the significant experimental data. The latest revision of the spontaneous fission neutron yield anti nu, of 252Cf and the foil thickness corrections to the fission neutron yield ratios of fissile nuclei to 252Cf are included. These lead to greater consistency in the data used for anti nu (252Cf). Similarly, the 234U half-life as revised leads to improved consistency in the 235U fission cross section. Comparison is made with the values from ENDF/B-V and other evaluations

  5. Neutron-induced transmutation reactions in 237Np, 238Pu, and 239Pu at the massive natural uranium spallation target

    International Nuclear Information System (INIS)

    Transmutation reactions in the 237Np, 238Pu, and 239Pu samples were investigated in the neutron field generated inside a massive (m = 512 kg) natural uranium spallation target. The uranium target assembly QUINTA was irradiated with the deuteron beams of kinetic energy 2, 4, and 8 GeV provided by the Nuclotron accelerator at the Joint Institute for Nuclear Research (JINR) in Dubna. The neutron-induced transmutation of the actinide samples was measured off-line by implementing methods of gamma-ray spectrometry with HPGe detectors. Results of measurement are expressed in the form of both the individual reaction rates and average fission transmutation rates. For the purpose of validation of radiation transport programs, the experimental results were compared with simulations of neutron production and distribution performed by the MCNPX 2.7 and MARS15 codes employing the INCL4-ABLA physics models and LAQGSM event generator, respectively. In general, a good agreement between the experimental and calculated reaction rates was found in the whole interval of provided beam energies

  6. ZPR-6 assembly 7 high {sup 240}Pu core experiments : a fast reactor core with mixed (Pu,U)-oxide fuel and a centeral high{sup 240}Pu zone.

    Energy Technology Data Exchange (ETDEWEB)

    Lell, R. M.; Morman, J. A.; Schaefer, R.W.; McKnight, R.D.; Nuclear Engineering Division

    2009-02-23

    ZPR-6 Assembly 7 (ZPR-6/7) encompasses a series of experiments performed at the ZPR-6 facility at Argonne National Laboratory in 1970 and 1971 as part of the Demonstration Reactor Benchmark Program (Reference 1). Assembly 7 simulated a large sodium-cooled LMFBR with mixed oxide fuel, depleted uranium radial and axial blankets, and a core H/D near unity. ZPR-6/7 was designed to test fast reactor physics data and methods, so configurations in the Assembly 7 program were as simple as possible in terms of geometry and composition. ZPR-6/7 had a very uniform core assembled from small plates of depleted uranium, sodium, iron oxide, U{sub 3}O{sub 8} and Pu-U-Mo alloy loaded into stainless steel drawers. The steel drawers were placed in square stainless steel tubes in the two halves of a split table machine. ZPR-6/7 had a simple, symmetric core unit cell whose neutronic characteristics were dominated by plutonium and {sup 238}U. The core was surrounded by thick radial and axial regions of depleted uranium to simulate radial and axial blankets and to isolate the core from the surrounding room. The ZPR-6/7 program encompassed 139 separate core loadings which include the initial approach to critical and all subsequent core loading changes required to perform specific experiments and measurements. In this context a loading refers to a particular configuration of fueled drawers, radial blanket drawers and experimental equipment (if present) in the matrix of steel tubes. Two principal core configurations were established. The uniform core (Loadings 1-84) had a relatively uniform core composition. The high {sup 240}Pu core (Loadings 85-139) was a variant on the uniform core. The plutonium in the Pu-U-Mo fuel plates in the uniform core contains 11% {sup 240}Pu. In the high {sup 240}Pu core, all Pu-U-Mo plates in the inner core region (central 61 matrix locations per half of the split table machine) were replaced by Pu-U-Mo plates containing 27% {sup 240}Pu in the plutonium

  7. {sup 241}Pu concentrations in water, plankton and fish from the southern Baltic Sea

    Energy Technology Data Exchange (ETDEWEB)

    Struminska-Parulska, D.I.; Skwarzec, B. [Gdansk, Univ. (Poland). Facuty of Chemistry

    2013-08-01

    The aim of the work was to determine {sup 241}Pu activities in different components (water, plankton and fish) of the southern Baltic Sea ecosystem. Measurement of {sup 241}Pu in the samples was done indirectly by determining the increment in {sup 241}Am from the decay of the {beta}-emitting {sup 241}Pu in samples collected 10-15 years after the Chernobyl accident. Enhanced levels of {sup 241}Pu were observed in all analyzed Baltic samples. The highest {sup 241}Pu concentrations in fish were found in Perciformes: benthic round goby (0.863 {+-} 0.066 mBq/g ww) and pelagic perch (0.666 {+-} 0.001 mBq/g ww). Plutonium is also non-uniformly distributed in the organs and tissues of the analyzed fish; especially pelagic herring and cod as well as benthic flounder. Most of {sup 241}Pu in flounder, herring and cod is located in soft tissues, especially digestive organs (stomach, intestine, liver). The annual individual effective doses calculated on the basis of {sup 241}Pu concentrations in fish indicated that the impact of the consumption of {sup 241}Pu containing Baltic fish on the annual effective dose for a statistical inhabitant of Poland was very small. (orig.)

  8. Adsorption and diffusion of Pu in soils. Progress report, April 1, 1975--December 1975

    International Nuclear Information System (INIS)

    Adsorption, desorption, and diffusion coefficients of 238Pu were determined for three contrasting soils, Fuquay sand, Hanford sandy loam, and Muscatine silt loam. Aqueous diffusion of 238Pu was determined for solutions of nitric acid, and calcium and cerium nitrate salt solutions

  9. Highly accurate measurements of the spontaneous fission half-life of 240,242Pu

    Science.gov (United States)

    Salvador-Castiñeira, P.; Bryś, T.; Eykens, R.; Hambsch, F.-J.; Moens, A.; Oberstedt, S.; Sibbens, G.; Vanleeuw, D.; Vidali, M.; Pretel, C.

    2013-12-01

    Fast spectrum neutron-induced fission cross-section data for transuranic isotopes are of special demand from the nuclear data community. In particular highly accurate data are needed for the new generation IV nuclear applications. The aim is to obtain precise neutron-induced fission cross sections for 240Pu and 242Pu. To do so, accurate data on spontaneous fission half-lives must be available. Also, minimizing uncertainties in the detector efficiency is a key point. We studied both isotopes by means of a twin Frisch-grid ionization chamber with the goal of improving the present data on the neutron-induced fission cross section. For the two plutonium isotopes the high α-particle decay rates pose a particular problem to experiments due to piling-up events in the counting gas. Argon methane and methane were employed as counting gases, the latter showed considerable improvement in signal generation due to its higher drift velocity. The detection efficiency for both samples was determined, and improved spontaneous fission half-lives were obtained with very low statistical uncertainty (0.13% for 240Pu and 0.04% for 242Pu): for 240Pu, T1/2,SF=1.165×1011 yr (1.1%), and for 242Pu, T1/2,SF=6.74×1010 yr (1.3%). Systematic uncertainties are due to sample mass (0.4% for 240Pu and 0.9% for 242Pu) and efficiency (1%).

  10. Quantative autoradiography of inhaled 239PuO2 in the lung

    International Nuclear Information System (INIS)

    PuO2 particles behaved similarly in the lungs of rat and hamster. The relative concentrations of PuO2 up to 1-yr postexposure were 1.0 for lung parenchyma, 1.3 for subpleural areas, 0.5 for peribronchiolar regions and 0.2 for perivascular regions in the lungs

  11. Thermal ionization mass spectrometric study of U-Pu-O system

    International Nuclear Information System (INIS)

    First inference from a thermal ionization mass spectrometric study of samples corresponding to the ternary U-Pu-O system, especially if high surface ionization temperatures are employed, is likely to be at variance with that from equilibrium vaporization thermodynamic studies, that the atomic species U and Pu dominate the vapor phase

  12. Recommendations for the 242Pu content evaluation using a new algorithm

    International Nuclear Information System (INIS)

    Plutonium isotopic determination by gamma spectrometry is an important nondestructive assay (NDA) method widely used by laboratories, operators, and safeguards directorates. Significant improvements have been made in the last few years on plutonium gamma-ray analysis, which have led to a very low discrepancy between gamma measurement and mass spectrometry (≤ ±2%) for the detectable isotopes. This leads to the fact that one important source of error is now the 242Pu content evaluation using correlation with the other isotopes. Moreover, the 242Pu content on the total plutonium is not negligible for typical burnup (it can reach 8 to 10% for burnup of ∼40 GWd/tonne U). This means that a lack of knowledge on the 242Pu content evaluation will generate an important error on the total plutonium mass estimation. The correlation used by many codes (like MGA) is as follows: 242Pu = C240Pu/Pu239241Pu/239Pu. This correlation leads to an average difference between NDA evaluation and mass spectrometry of ∼20%

  13. Isotherm of Pu/Goethite System: Linearity and the Sorbent Surface Characterization

    Science.gov (United States)

    Zhao, P.; Zavarin, M.; Tumey, S. J.; Williams, R.; Dai, Z.; Kips, R.; Kersting, A. B.

    2010-12-01

    A major challenge in predicting the mobility and transport of plutonium (Pu) is determining the dominant geochemical processes that control its behavior in the subsurface. An improved understanding of coupled processes, from the mineral surface to the field scale, under relevant environmental conditions is essential for significant breakthroughs in Pu transport conceptual model. However, systematic studies under relevant environmental conditions are lacking. We performed Pu(IV) and Pu(V) batch sorption isotherms in 0.7 mM NaHCO3/5 mM NaCl (pH ~8) solution with goethite over a ten order of magnitude concentration range. Pu(V) is expected to reduce to Pu(IV) on the goethite surface. Aqueous Pu concentrations and surface loadings ranged from 10-7 to 10-17 M and >100% to epitaxis of Pu nano-particles were found on goethite mineral surfaces. This work was performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Security, LLC under Contract DE-AC52-07NA27344.

  14. R-matrix analyses of the 235U and 239Pu neutron cross sections

    International Nuclear Information System (INIS)

    The resonance parameter analysis code SAMMY was used to perform consistent resonance analyses of several 235U and 239Pu fission and capture cross section and transmission measurements up to 110 eV for 235U and up to 1 keV for 239Pu. The method of analysis, the measurement selection and the results are briefly outlined in this paper

  15. Observations of surface-mediated reduction of Pu(VI) to Pu(IV) on hematite nanoparticles by ATR FT-IR

    Energy Technology Data Exchange (ETDEWEB)

    Emerson, Hilary P. [Florida International Univ., Applied Research Center, Miami, FL (United States); Powell, Brian A. [Clemson Univ., Dept. of Enviromental Engineering and Earth Sciences, Anderson, SC (United States)

    2015-07-01

    Previous studies have shown that mineral surfaces may facilitate the reduction of plutonium though the mechanisms of the reduction are still unknown. The objective of this study is to use batch sorption and attenuated total reflectance Fourier transform infrared spectroscopy experiments to observe the surface-mediated reduction of plutonium on hematite nanoparticles. These techniques allow for in situ measurement of reduction of plutonium with time and may lead to a better understanding of the mechanisms of surface mediated reduction of plutonium. For the first time, ATR FT-IR peaks for Pu(VI) sorbed to hematite are measured at ∝ 916 cm{sup -1}, respectively. The decrease in peak intensity with time provides a real-time, direct measurement of Pu(VI) reduction on the hematite surface. In this work pseudo first order rate constants estimated at the high loadings (22 mg{sub Pu}/g{sub hematite}, 1.34 x 10{sup -6} M{sub Pu}/m{sup 2}) for ATR FT-IR are approximately 10 x slower than at trace concentrations based on previous work. It is proposed that the reduced rate constant at higher Pu loadings occurs after the reduction capacity due to trace Fe(II) has been exhausted and is dependent on the oxidation of water and possibly electron shuttling based on the semiconducting nature of hematite. Therefore, the reduction rate at higher loadings is possibly due to the thermodynamic favorability of Pu(IV)-hydroxide complexes.

  16. Deposition of [sup 210]Pb, [sup 137]Cs, [sup 239+240]Pu, [sup 238]Pu, and [sup 241]Am in the Antarctic peninsula area

    Energy Technology Data Exchange (ETDEWEB)

    Roos, P.; Holm, E.; Persson, R.B.R. (Lund Univ. (Sweden). Dept. of Radiation Physics); Aarkrog, A.; Nielsen, S.P. (Risoe National Lab., Roskilde (Denmark))

    1994-01-01

    [sup 210]Pb, [sup 137]Cs, [sup 239+240]Pu, [sup 238]Pu, and [sup 241]Am were analysed in lichen, moss, grass and soil samples, as well as in lake sediments, from the South Shetland Islands, the Antarctic, in order to evaluate the flux and deposition of these elements. Average inventories of the analysed radionuclides in 1988 are given. The ratios [sup 238]Pu/[sup 239+240]Pu and [sup 241]Am/[sup 239+240]Pu of 0.21 [+-] 0.04 and 0.35 [+-] 0.08 respectively agree well with expected values in this area. A significant difference in [sup 137]Cs/[sup 239+240]Pu ratios between lichens and moss/grass/soil is observed which may be an effect of submerging and melt water altering radionuclide ratios. From one of three lakes studied it is possible to perform [sup 210]Pb dating with reasonable accuracy showing an average annual sediment accumulation in this lake of about 45 g m[sup -2]. (author).

  17. Chronology of Pu isotopes and {sup 236}U in an Arctic ice core

    Energy Technology Data Exchange (ETDEWEB)

    Wendel, C.C., E-mail: cato.wendel@umb.no [Isotope Laboratory, Department of Plant and Environmental Sciences, Agricultural University of Norway, P.O. Box 5003, N-1432 Aas (Norway); Oughton, D.H., E-mail: deborah.oughton@umb.no [Isotope Laboratory, Department of Plant and Environmental Sciences, Agricultural University of Norway, P.O. Box 5003, N-1432 Aas (Norway); Lind, O.C., E-mail: ole-christian.lind@umb.no [Isotope Laboratory, Department of Plant and Environmental Sciences, Agricultural University of Norway, P.O. Box 5003, N-1432 Aas (Norway); Skipperud, L., E-mail: lindis.skipperud@umb.no [Isotope Laboratory, Department of Plant and Environmental Sciences, Agricultural University of Norway, P.O. Box 5003, N-1432 Aas (Norway); Fifield, L.K., E-mail: keith.fifield@anu.edu.au [Department of Nuclear Physics, Australian National University, Canberra ACT 0200 (Australia); Isaksson, E., E-mail: elisabeth.isaksson@npolar.no [Norwegian Polar Institute, Fram Centre, Hjalmar Johansens Gate 14, N9296 Tromsø (Norway); Tims, S.G., E-mail: steve.tims@anu.edu.au [Department of Nuclear Physics, Australian National University, Canberra ACT 0200 (Australia); Salbu, B., E-mail: brit.salbu@umb.no [Isotope Laboratory, Department of Plant and Environmental Sciences, Agricultural University of Norway, P.O. Box 5003, N-1432 Aas (Norway)

    2013-09-01

    In the present work, state of the art isotopic fingerprinting techniques are applied to an Arctic ice core in order to quantify deposition of U and Pu, and to identify possible tropospheric transport of debris from former Soviet Union test sites Semipalatinsk (Central Asia) and Novaya Zemlya (Arctic Ocean). An ice core chronology of {sup 236}U, {sup 239}Pu, and {sup 240}Pu concentrations, and atom ratios, measured by accelerator mass spectrometry in a 28.6 m deep ice core from the Austfonna glacier at Nordaustlandet, Svalbard is presented. The ice core chronology corresponds to the period 1949 to 1999. The main sources of Pu and {sup 236}U contamination in the Arctic were the atmospheric nuclear detonations in the period 1945 to 1980, as global fallout, and tropospheric fallout from the former Soviet Union test sites Novaya Zemlya and Semipalatinsk. Activity concentrations of {sup 239+240}Pu ranged from 0.008 to 0.254 mBq cm{sup −2} and {sup 236}U from 0.0039 to 0.053 μBq cm{sup −2}. Concentrations varied in concordance with {sup 137}Cs concentrations in the same ice core. In contrast to previous published results, the concentrations of Pu and {sup 236}U were found to be higher at depths corresponding to the pre-moratorium period (1949 to 1959) than to the post-moratorium period (1961 and 1962). The {sup 240}Pu/{sup 239}Pu ratio ranged from 0.15 to 0.19, and {sup 236}U/{sup 239}Pu ranged from 0.18 to 1.4. The Pu atom ratios ranged within the limits of global fallout in the most intensive period of nuclear atmospheric testing (1952 to 1962). To the best knowledge of the authors the present work is the first publication on biogeochemical cycles with respect to {sup 236}U concentrations and {sup 236}U/{sup 239}Pu atom ratios in the Arctic and in ice cores. - Highlights: • Concentrations and atom ratios of Pu and {sup 236}U determined in an Arctic ice core. • Concentrations of U and Pu found to be higher pre- than post-moratorium. • U and Pu concentrations

  18. Analysis of 241Pu radioactivity by isotope dilution-extraction liquid scintillation spectrometer

    International Nuclear Information System (INIS)

    The radionuclide 241Pu decays predominantly by β emission with a half-life 14.29 a. The branching ratio of its α-emission is negligibly small. However, it is difficult to measure the radioactivity of 241Pu in a Pu containing complicated sample because of its low β energy. A method for determination of 241Pu in high level liquid waste (HLLW) was developed. It consists of the following steps. The first step is to separate and purify plutonium from HLLW. The chemical yield of plutonium is higher than 95%. Secondly, a determination method by using modern liquid scintillation spectrometry combined with isotope dilution, solvent extraction, and ion exchange chromatography was established to analyze the 241Pu content in HLLW. (authors)

  19. Development of a method for zirconium determination in (Pu, U) Zr alloy samples

    International Nuclear Information System (INIS)

    (Pu,U)Zr alloys are the proposed fuel for fast reactor and precise determination of Zr in (Pu,U)Zr alloy samples is required for nuclear fuel quality control. A method for Zr determination in (Pu,U) Zr alloy samples based on selective precipitation of Zirconium at microgram (300-1500 μg) level followed by spectrophotometric measurement is developed. The interference of Plutonium in Zr mandelate precipitation was studied in different oxidation state of Pu. The method was applied for the actual (Pu,U) Zr alloy samples. The reproducibility of the method was within 2% and the complete analysis of 12 samples required 3-4 hrs. The method was compared with Zr determination by ICP-AES after matrix separation by Zr-mandelate precipitation. (author)

  20. Determination of the 241Pu(n,f) reaction cross sections by surrogate ratio method

    International Nuclear Information System (INIS)

    In a recent work, direct measurement of neutron induced fission cross section of 241Pu(T1/2 = 14.1 yrs), has been carried out using neutron time of flight. Differences between the reported experimental measurement and evaluation by standard libraries exceeds by 30%, thus it is suggested to carry out further confirmatory measurements on 241Pu(n,f) cross sections. In this paper, we report the use of 238U(6Li,d)242Pu and 232Th(6Li,d)236U transfer reactions as surrogate of 241Pu(n,f) and 235U(n,f) compound nuclear reactions respectively. By employing the surrogate ratio method (SRM) and taking 235U(n,f) as reference, the 241Pu(n,f) cross sections have been determined in the equivalent neutron energy range of 11.0 MeV-16.0 MeV

  1. Neutron-induced Fission Cross Section of 240242Pu up to En = 3 MeV

    Science.gov (United States)

    Salvador-Castiñeira, P.; Bryś, T.; Hambsch, F.-J.; Oberstedt, S.; Pretel, C.; Vidali, M.

    2014-05-01

    The neutron-induced fission cross sections of 240,242Pu have been measured at JRC-IRMM with incident neutron energy from 0.2 MeV up to 3 MeV. A Twin-Frisch Grid Ionization Chamber (TFGIC) has been used in a back-to-back geometry. The measurements have been performed using the secondary standards 237Np and 238U as a reference. The purity of the plutonium samples was 99.89% for 240Pu and 99.97% for 242Pu. The results obtained follow the ENDF/B-VII.1 evaluation for 240Pu, but some discrepancies are visible around E/n = 1 MeV for 242Pu. In addition, the spontaneous fission half-life has been measured for both isotopes.

  2. Simultaneous measurement of {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, and {sup 242}Pu by high resolution inductively coupled plasma mass spectrometer (HR ICP-MS) in marine sediments; Mesure des isotopes du plutonium des sediments marins par spectrometrie de masse a plasma couple inductivement haute resolution (HR ICP-MS)

    Energy Technology Data Exchange (ETDEWEB)

    Bruneau, F

    1999-07-01

    Transuranics elements are of particular interest in radioecological studies because of their radiotoxicity and their potential use to decipher source fingerprints and transport processes. The simultaneous measurement of {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, and {sup 242}Pu in environmental samples requires a specific chemical procedure. This work deals with an analytical procedure which yields a very high grade of purification of Pu suitable for ultra low level detection by HR ICP-MS, from marine sediments. After the elimination of major elements (Fe, Al, Mg...) by a first chromatographic separation, a new device of purification by solvent extraction and concentration by a second chromatographic separation is used to obtain a concentrated and high purified solution of plutonium. The chemical procedure have been validated on IAEA certified sediment samples and on sediment samples collected in the roads of Cherbourg which had been previously analysed by other techniques (a spectrometry and thermo-ionisation mass spectrometer). (author)

  3. Inhaled 239PuO2 in rats with pulmonary emphysema. II

    International Nuclear Information System (INIS)

    The modifying effects of pre-existing pulmonary emphysema on deposition, distribution, retention, and effects of inhaled 239PuO2 in the rat were investigated. The presence of emphysema in the rats tested was indicated by respiratory function measurements and confirmed microscopically. Initial lung burdens of 239Pu per kg body weight were less in rats with emphysema than in control rats; however, the retention of 239Pu was similar in emphysematous and control rats. Survival and lung tumor occurrence were similar in emphysematous and control rats exposed to 239PuO2. We concluded that rats with pre-existing pulmonary emphysema were not more sensitive to the effects of inhaled 239PuO2 than control rats. (author)

  4. TEM identification of subsurface phases in ternary U-Pu-Zr fuel

    Science.gov (United States)

    Aitkaliyeva, Assel; Madden, James W.; Papesch, Cynthia A.; Cole, James I.

    2016-05-01

    Phases and microstructure in as-cast, annealed at 850 °C, and subsequently cooled U-23Pu-9Zr fuel were characterized using scanning and transmission electron microscopy techniques. SEM examination shows formation of three phases in the alloy that were identified in TEM using selective area diffraction pattern analysis: α-Zr globular and elongated δ-UZr2 inclusions and a thick oxide layer formed on top of β-Pu phase, which has been initially assumed to be ζ-(U, Pu). However, further examination of the cross-sectional TEM specimens identified the matrix phases as δ-UZr2, β-Pu, and (U, Zr)ht. Two types of inclusions were observed in the immediate vicinity of the specimen surface and they were consistent with α-Zr and ζ-(U, Pu).

  5. Sorption of Pu(IV) from nitric acid by bifunctional anion-exchange resins

    International Nuclear Information System (INIS)

    Anion exchange is attractive for separating plutonium because the Pu(IV) nitrate complex is very strongly sorbed and few other metal ions form competing anionic nitrate complexes. The major disadvantage of this process has been the unusually slow rate at which the Pu(IV) nitrate complex is sorbed by the resin. The paper summarizes the concept of bifunctional anion-exchange resins, proposed mechanism for Pu(IV) sorption, synthesis of the alkylating agent, calculation of Kd values from Pu(IV) sorption results, and conclusions from the study of Pu(IV) sorption from 7M nitric acid by macroporous anion-exchange resins including level of crosslinking, level of alkylation, length of spacer, and bifunctional vs. monofunctional anion-exchange resins

  6. Status of the PuMa-ECR (Pulsed Magnetic field)

    International Nuclear Information System (INIS)

    Synchrotrons like the heavy ion synchrotron SIS at GSI need an efficient low duty cycle injector (typical 1 pulse/s and 200 μs pulse length). To improve the peak current, an ECR ion source has been designed using a pulsed magnetic field to force ion extraction. We replaced the hexapole of a 10 GHz MINIMAFIOS ECR ion source by a vacuum chamber containing a watercooled bilayered solenoid coil and a decapole permanent magnetic structure. A pulse line feeds the solenoid with a 250 μs pulse which increases the magnetic field in the minimum B region by 0.3 Tesla. This process opens the magnetic bottle along the beam axis resulting in an extracted ion pulse. First tests of the PuMa-ECR configuration in cw and pulsed operation are presented and analysed. (orig.)

  7. Reassessing the melting temperature of PuO2

    Directory of Open Access Journals (Sweden)

    Franck De Bruycker

    2010-11-01

    Full Text Available The melting behavior is a fundamental property of a material, closely related to its structure and thermodynamic stability, and has therefore been a crucial subject of research for ages. The melting point is also an important engineering parameter, as it defines the operational limits of a material in its application environment. This point becomes critical in nuclear engineering where the thermo-mechanical stability of a nuclear fuel element is a key factor determining fuel performance and safety. However, experimental difficulties stemming from the extreme temperatures, complex pressure-temperature-composition relations, and the high radioactivity make the study of melting of refractory actinide compounds particularly challenging. As a consequence, experimental data are rare and subject to large uncertainties, and more reliable experimental techniques are badly needed. A novel experimental approach is presented here, yielding new data and allowing a re-assessment of the PuO2 melting behaviour.

  8. Nonmagnetic ground state of PuO2

    Science.gov (United States)

    Shick, A. B.; Kolorenč, J.; Havela, L.; Gouder, T.; Caciuffo, R.

    2014-01-01

    The correlated band theory implemented as a combination of the local density approximation with the exact diagonalization of the Anderson impurity model is applied to PuO2. We obtain an insulating electronic structure consistent with the experimental photoemission spectra. The calculations yield a band gap of 1.8 eV and a nonmagnetic singlet ground state that is characterized by a noninteger filling of the plutonium f shell (nf≈4.5). Due to sizable hybridization of the f shell with the p states of oxygen, the ground state is more complex than the four-electron Russell-Saunders 5I4 manifold split by the crystal field. The inclusion of hybridization improves the agreement between the theory and experiment for the magnetic susceptibility.

  9. Fast reactor calculational route for Pu burning core design

    International Nuclear Information System (INIS)

    This document provides a description of a calculational route, used in the Reactor Physics Research Section for sensitivity studies and initial design optimization calculations for fast reactor cores. The main purpose in producing this document was to provide a description of and user guides to the calculational methods, in English, as an aid to any future user of the calculational route who is (like the author) handicapped by a lack of literacy in Japanese. The document also provides for all users a compilation of information on the various parts of the calculational route, all in a single reference. In using the calculational route (to model Pu burning reactors) the author identified a number of areas where an improvement in the modelling of the standard calculational route was warranted. The document includes comments on and explanations of the modelling assumptions in the various calculations. Practical information on the use of the calculational route and the computer systems is also given. (J.P.N.)

  10. Multilevel analysis of the low energy 239Pu cross sections

    International Nuclear Information System (INIS)

    It is well known that the ENDF/B-V representation of the 239Pu resonance region is not satisfactory: below 1 eV the cross sections are given by smooth files (file 3) rather than by resonance parameters. Above 1 eV the single-level formalism used in ENDF/B-V necessitates a structured file 3 contribution. The present paper presents the results of an R-matrix multilevel analysis of several recent data sets as well as of the older data. The analysis is concerned with the region up to 30 eV, an energy region that is important for thermal reactors and for which no recent multilevel analyses had previously been available

  11. Developing the Pulsed Fission-Fusion (PuFF) Engine

    Science.gov (United States)

    Adams, Robert B.; Cassibry, Jason; Bradley, David; Fabisinski, Leo; Statham, Geoffrey

    2014-01-01

    In September 2013 the NASA Innovative Advanced Concept (NIAC) organization awarded a phase I contract to the PuFF team. Our phase 1 proposal researched a pulsed fission-fusion propulsion system that compressed a target of deuterium (D) and tritium (T) as a mixture in a column, surrounded concentrically by Uranium. The target is surrounded by liquid lithium. A high power current would flow down the liquid lithium and the resulting Lorentz force would compress the column by roughly a factor of 10. The compressed column would reach criticality and a combination of fission and fusion reactions would occur. Our Phase I results, summarized herein, review our estimates of engine and vehicle performance, our work to date to model the fission-fusion reaction, and our initial efforts in experimental analysis.

  12. DOE Plutonium Disposition Study: Pu consumption in ALWRs

    International Nuclear Information System (INIS)

    The Department of Energy (DOE) has contracted with Asea Brown Boveri-Combustion Engineering (ABB-CE) to provide information on the capability of ABB-CE's System 80 + Advanced Light Water Reactor (ALWR) to transform, through reactor burnup, 100 metric tonnes (MT) of weapons grade plutonium (Pu) into a form which is not readily useable in weapons. This information is being developed as part of DOE's Plutonium Disposition Study, initiated by DOE in response to Congressional action. This document, Volume 1, presents a technical description of the various elements of the System 80 + Standard Plant Design upon which the Plutonium Disposition Study was based. The System 80 + Standard Design is fully developed and directly suited to meeting the mission objectives for plutonium disposal. The bass U02 plant design is discussed here

  13. Intralaboratory comparison experiments for plutonium determination in working reference material K4Pu (SO4)4: coulometry and biamperometry

    International Nuclear Information System (INIS)

    Accurate and precise determination of Pu in reactor fuel materials is essential for the characterization of the fuel as well as for fissile material accounting. Electroanalytical methods like Coulometry, Potentiometry , and Biamperometry based on the redox reactions are widely employed for determination of Pu at milligram levels. Controlled potential coulometry is a well established routinely employed technique for precise and accurate determination of plutonium. A biamperometric method based on the Pu(VI)-Pu(IV) redox couple has been in routine use for Pu determination in a variety of nuclear fuel materials in our laboratory for past 25 years. In order to validate the status of the methodologies employed for Pu determination an intralaboratory comparison experiments involving Pu determination in working reference material K4Pu(SO4)4 was conducted. Results of these studies are presented in this paper

  14. U.S.-Russian experts NATO collaborative research grant exchange visit meeting on excess Pu ceramics formulations and characterizations

    Energy Technology Data Exchange (ETDEWEB)

    Jardine, L.J., LLNL

    1998-11-24

    This document contains the agenda and meeting notes. Topics of discussion included US Pu disposition ceramics activities, Russian experience and proposals in Pu ceramics, and development of possible Russian ceramic proposals or collaborations.

  15. Distribution of Np and Pu in Swedish lichen samples (Cladonia stellaris) contaminated by atmospheric fallout

    Energy Technology Data Exchange (ETDEWEB)

    Lindahl, Patric E-mail: patric.lindahl@radfys.lu.se; Roos, Per; Eriksson, Mats; Holm, Elis

    2004-07-01

    The activity concentrations of {sup 237}Np and the two Pu isotopes, {sup 239}Pu and {sup 240}Pu, were determined in lichen samples (Cladonia stellaris) contaminated by fallout from atmospheric nuclear test explosions and the Chernobyl accident. The samples were collected at 18 locations in Sweden, from north to south, between 1986 and 1988 and analysed with high-resolution inductively coupled plasma mass spectrometry (HR-ICP-MS) and alpha spectrometry. Data on the activity ratios {sup 238}Pu/{sup 239+240}Pu and {sup 134}Cs/{sup 137}Cs measured previously were also included in this study for comparison. The {sup 237}Np activity concentration ranged from 0.08{+-}0.01 to 2.08{+-}0.17 mBq kg{sup -1}, depending on the location of the sampling site and time of collection. The {sup 239+240}Pu activity concentration ranged from 0.09{+-}0.01 to 4.09{+-}0.15 Bq kg{sup -1}, with the {sup 240}Pu/{sup 239}Pu atomic ratio ranging between 0.16{+-}0.01 and 0.44{+-}0.03, the higher ratios indicating a combination of weapons test fallout and Chernobyl fallout. The {sup 237}Np/{sup 239}Pu atomic ratios ranged between 0.06{+-}0.01 and 0.42{+-}0.04, the lower ratios indicating combination of weapons test fallout and Chernobyl fallout. At a well-defined sampling site at Lake Rogen (62.32 deg. N, 12.38 deg. E), additional lichen samples were collected between 1987 and 1998 to study the distribution of Np and Pu in different layers. The concentrations of the two elements follow each other quite well in the profile.

  16. Helium release from 238PuO2 fuel particles

    International Nuclear Information System (INIS)

    Coated plutonia fuel particles have recently been proposed for potential use in future space exploration missions that employ radioisotope power systems and/or radioisotope heater units (RHUs). The design of this fuel form calls for full retention of the helium generated by the natural radioactive decay of 238Pu, with the aid of a strong zirconium carbide coating. This paper reviews the potential release mechanisms of helium in small-grain (7-40 μm) plutonia pellets currently being used in the General Purpose Heat Source (GPHS) modules and RHUs, during both steady-state and transient heating conditions. The applicability of these mechanisms to large-grain and polycrystalline 238PuO2 fuel kernels is examined and estimates of helium release during a re-entry heating pulse up to 1723 K are presented. These estimates are based on the reported data for fission gas release from granular and monocrystal UO2 fuel particles irradiated at isothermal conditions up to 6.4 at.% burnup and 2030 K. It is concluded that the helium release fraction from large-grain (≥300 μm) plutonia fuel kernels heated up to 1723 K could be less than 7%, compared to ∼80% from small-grain (7-40 μm) fuel. The helium release fraction from polycrystalline plutonia kernels fabricated using Sol-Gel techniques could be even lower. Sol-Gel fabrication processes are favored over powder metallurgy, because of their high precision and excellent reproducibility and the absence of a radioactive dust waste stream, significantly reducing the fabrication and post-fabrication clean-up costs

  17. Consistent Data Assimilation of Isotopes: 242Pu and 105Pd

    Energy Technology Data Exchange (ETDEWEB)

    G. Palmiotti; H. Hiruta; M. Salvatores

    2012-09-01

    In this annual report we illustrate the methodology of the consistent data assimilation that allows to use the information coming from integral experiments for improving the basic nuclear parameters used in cross section evaluation. A series of integral experiments are analyzed using the EMPIRE evaluated files for 242Pu and 105Pd. In particular irradiation experiments (PROFIL-1 and -2, TRAPU-1, -2 and -3) provide information about capture cross sections, and a critical configuration, COSMO, where fission spectral indexes were measured, provides information about fission cross section. The observed discrepancies between calculated and experimental results are used in conjunction with the computed sensitivity coefficients and covariance matrix for nuclear parameters in a consistent data assimilation. The results obtained by the consistent data assimilation indicate that not so large modifications on some key identified nuclear parameters allow to obtain reasonable C/E. However, for some parameters such variations are outside the range of 1 s of their initial standard deviation. This can indicate a possible conflict between differential measurements (used to calculate the initial standard deviations) and the integral measurements used in the statistical data adjustment. Moreover, an inconsistency between the C/E of two sets of irradiation experiments (PROFIL and TRAPU) is observed for 242Pu. This is the end of this project funded by the Nuclear Physics Program of the DOE Office of Science. We can indicate that a proof of principle has been demonstrated for a few isotopes for this innovative methodology. However, we are still far from having explored all the possibilities and made this methodology to be considered proved and robust. In particular many issues are worth further investigation: • Non-linear effects • Flexibility of nuclear parameters in describing cross sections • Multi-isotope consistent assimilation • Consistency between differential and integral

  18. Analytical studies of plutonium containing solutions by Laser-Raman-Spectroscopy (LRS) with special regard to the Pu(IV)-Ru(III)-HNO3 and Pu(VI)-H2O2-reactions

    International Nuclear Information System (INIS)

    In spent nuclear fuel reprocessing by the Purex process it is attempted to apply as far as possible automated analytical equipment, which is directly coupled to the process stream. This paper describes the optical coupling of Laser-Raman-Spectroscopy (LRS) with commercial fiber optics in a 900 geometry to a test apparatus within a glovebox. It was possible to show that in nitric acid solutions Pu(VI), Pu(V), U(VI), and nitrate can be detected simultaneously without interference. The suitability of LRS for the Pu(VI) and Pu(V) detection was demonstrated by the example of two reactions, namely the oxidation of Pu(IV) to Pu(VI) in nitric acid solution in the presence of Ru(NO)-complexes and the reduction of Pu(VI) to Pu(V) by H2O2. In the study of the Pu(IV)-Ru(NO)-reaction the temperature and the concentrations of the individual reactants were varied and in addition the concentration of F-, which as a strong complexing agent for Pu(IV) exerts a considerable influence on the reaction rate. The results of these experiments were used to estimate the reaction orders for the individual reactants by the method of initial rates. The course of the reduction of Pu(VI) to Pu(V) with H2O2 was studied for different temperatures, pH-values and F--concentrations. (orig./RB)

  19. The AS-76 interlaboratory experiment on the alpha spectrometric determinaion of Pu-238. Part 3: Preparation and characterization of samples

    International Nuclear Information System (INIS)

    Four plutonium samples containing 0.2, 0.8, 1.6 and 0.9 atom % of 238Pu have been prepared for the Interlaboratory Experiment AS-76. Of these three were input solutions from a reprocessing plant. The fourth sample was from a plutonium product solution. These samples have been characterized by two alpha spectrometry laboratories and two mass spectrometry laboratories to certify the ratio of alpha activities 238Pu/(239Pu + 240Pu) and the isotopic composition, respectively

  20. Characterization of U/Pu particles originating from the nuclear weapons accidents at Palomares, Spain, 1966 and Thule, Greenland, 1968

    OpenAIRE

    Lind, O. C.; Salbu, B.; Janssens, K.; Proost, K.; Garcia-Leon, M.; R. Garcia-Tenorio

    2007-01-01

    Following the USAF B-52 bomber accidents at Palomares, Spain in 1966 and at Thule, Greenland in 1968, radioactive particles containing uranium (U) and plutonium (Pu) were dispersed into the environment. To improve long-term environmental impact assessments for the contaminated ecosystems, particles from the two sites have been isolated and characterized with respect to properties influencing particle weathering rates. Low (239)Pu/(235)U (0.62-0.78) and (240)Pu/(239)Pu (0.055-0.061) atom ratio...

  1. Research of water-base nano-PU paint for heat insulation

    Science.gov (United States)

    Jwo, Ching-Song; Jeng, Lung-Yue; Cheng, Ho; Chen, Sih-Li

    2008-12-01

    The purpose of this study is to research and produce water-base nano-PU paint with energy conservation, environmental consciousness and high efficiency of heat insulation, which can be enhance the traditional PU paint for performance improvement of heat insulation and range of application. In this study, research will be held on the two-stage synthesis method. The SiO2 nanoparticles are added into the water-base PU paint to improve the properties of traditional PU paint. Next, the fundamental properties of this paint, including water resistance, weather rsistance, weak acid solvent resistance, and heat insulation rate, will be measured and analyzed, and the performance of heat insulation will be evaluated in order to confirm the performance and practicability of the heat insulation of water-base nano-PU paint in this study. The experimental results show that for the SiO2/W-PU composite nanopaint prepared by two-stage synthesis method, the dispersion of SiO2 powder in the water-base PU (W-PU) paint is even. For the SiO2/W-PU nanocomposite paint prepared by adding SiO2 powder at 8% wt. to the marketed water-base PU, the water absorption of its experimental sample is enhanced by around 10.1 times, whereas its weak acid dissolve erosion rate is increased by 3.3 times. However, the average heat insulation rate in the thermal properties is also increased, increasing around 24.22% for the W-PU paint without SiO2 powder. Through the multilayered coating construction, the water-base nano-PU paint added with SiO2 powder can be used on any facility of heat insulation, including vehicle, safety helmet, umbrella, drapes, and outer wall of building. The newly developed water-base nano-PU paint with high thermal resistance is especially suitable for application to the shell coating of air conditioner and cooling tower,. Due to the better thermal resistance of this nanopaint, the problems of poor heat transfer and temperature rise of cooling water caused by direct sunlight can be

  2. Barrier function of the placenta and microdistribution of 238Pu in the feto-placental complex of the rat

    International Nuclear Information System (INIS)

    Investigation materials, methods and results are presented. The aim of the investigation was to determine mechanisms of 238Pu transfer through pregnant rats depending on pregnancy time and to determine peculiarities of 238Pu microdistribution in feature tissues and placenta structures. 238Pu distribution in amnious, fetal placenta labyrinthine part and maternal placenta is shown

  3. Feedback on 239Pu and 240Pu nuclear data and associated covariances through the CERES integral experiments

    International Nuclear Information System (INIS)

    Benchmark measurements of irradiated and un-irradiated fuel samples were performed in the framework of the CERES collaborative program between AEA (UK Atomic Energy Agency) and CEA (French Atomic Energy Commission). These experiments provide relevant data for the validation of fuel burn-up and criticality-safety calculations for the whole fuel cycle. As part of this program, pile-oscillation measurements were carried out on a range of mixed-oxide samples with plutonium of various mass and isotopic contents, both in the MINERVE and DIMPLE reactors. Four core configurations, two over-thermalized situations and two pressurized water reactor (PWR)-type situations, were constituted with different forward and adjoint flux spectra, emphasizing fission and/or capture contributions. The experiments were analyzed using reference TRIPOLI4 calculations with the JEFF-3.1.1 library, using exact three-dimensional models of the core configurations. In a first step, calculations of each DIMPLE configuration were performed and compared with the experiment, showing very good agreements with a maximum C-E of -230 pcm. In the second step, reactivity worth experiments were analyzed, using recently developed exact-perturbation capabilities in TRIPOLI4. A consistent assimilation of calculation over experiment discrepancies was performed with the CONRAD code, using the integral data assimilation method. Covariance matrix on multigroup neutron cross sections and multiplicities were generated and significant trends were identified, especially on the 239Pu and 240Pu capture cross sections in the thermal energy range (E < 0.1 eV). Further investigations should be required to confirm these conclusions, due to the strong dependence of these trends and of posterior covariances to prior covariances. (author)

  4. Influence of initial lung deposit on absorption parameters of Pu and am: application to (U, Pu)O2 powder after inhalation in the baboon

    International Nuclear Information System (INIS)

    Full text of publication follows: In cases of contamination by inhalation, risk assessment would be performed taking into account recommendations of the International Commission of Radiological Protection (ICRP) Human Respiratory Tract Model (H.R.T.M.) described in Publication 66 (ICRP 66, 1994). The use of absorption parameter values specific to each component is recommended when available for dose calculation in order to provide a more realistic assessment of risk. The solubility of Pu and Am deposited in the respiratory tract after inhalation is a relevant parameter that can aid the identification of target organs. The aim of this study is to show the influence of the initial lung deposit (I.L.D.) on absorption parameters after inhalation of Mixed oxides (Mox) powder (7.14 % Pu w/w) in baboons. Daily urinary excretion of Pu/Am was measured for 3 months which allowed the estimation of the removal of the soluble fraction from lungs to blood and in particular a proportion of absorption parameters. Urinary excretion on 3 -month period were represented by biphasic curves which were directly reliable to physicochemical properties of compounds. Males baboon were exposed to I.L.D.: 40 to 860 kBq. Results obtained show that urinary excretions progress in the reverse order of I.L.D. Moreover, significant differences in the behaviour of Pu and Am were also observed in the target organs (liver and skeleton) and especially Am was more soluble than Pu for the compound studied. So, hypothesis of a more important dissolution of Am compare to Pu combines to a special affinity of Am for target organs seem to be involve. This result was very important in case of dismantling operation mainly in the usury of fuel since 241 Am is a filiation product of 241 Pu. In conclusion, this work contributes to support the usefulness of experimental data in radioprotection to estimate level of radiological exposition of worker. (authors)

  5. Study of phase equilibria in function of temperature in UO2-PuO2-Pu2O3 system for nuclear ceramics with high plutonium contents

    International Nuclear Information System (INIS)

    In the UO2-PuO2-Pu2O3 section, a monophasic (U1-y,Puy)O2-x domain is stable for y≤0,20 at 25 C and up to solid-liquid equilibrium. At higher Pu content, phase equilibria are more unclear with a phase separation process. The main objective of this work consisted in upgrading the representation of this system for 0,15≤y≤0,65 and 25≤T(C)≤1500. At 25 C, a miscibility gap composed by two different (U1-y,Puy)O2-x phases has been observed for y≤0,45, with one very closed to stoichiometric state (Oxygen/Metal=2) and one other very reduced. For the first time, a triphasic domain has been characterized at higher Pu contents, with two (U1-y,Puy)O2-x phases near y=0,45 and one (U1-y,Puy)2O3 phase with a low U content inside. Concerning the study in function of temperature, we have demonstrated that phase separation temperature increase when Pu content grows. Several representations have been established. At 200 C, the representation is closed to that at 25 C. At 400 C, the phase separation have been specified at a lower Pu content than that of literature: y=0,35. At 600 C, our results have clarified the section, until then very unclear, with a phase separation appearing at y=0,60.The microstructural analysis has clearly demonstrated the significant impact of the phase separation on the material. Indeed many cracks have been observed in our samples, and quantity of these defects increases when Pu content grows. (author)

  6. DFT and two-dimensional correlation analysis methods for evaluating the Pu3+–Pu4+ electronic transition of plutonium-doped zircon

    International Nuclear Information System (INIS)

    Highlights: • Effect of Pu f-shell electron on the electronic property of zircon is calculated via DFT and 2D-CA techniques. • Reasons of Pu f-shell electron influencing on electronic properties are systematically discussed. • Phase transitions are found at two point 2.8 mol% and 7.5 mol%. - Abstract: Understanding how plutonium (Pu) doping affects the crystalline zircon structure is very important for risk management. However, so far, there have been only a very limited number of reports of the quantitative simulation of the effects of the Pu charge and concentration on the phase transition. In this study, we used density functional theory (DFT), virtual crystal approximation (VCA), and two-dimensional correlation analysis (2D-CA) techniques to calculate the origins of the structural and electronic transitions of Zr1−cPucSiO4 over a wide range of Pu doping concentrations (c = 0–10 mol%). The calculations indicated that the low-angular-momentum Pu-fxy-shell electron excites an inner-shell O-2s2 orbital to create an oxygen defect (VO-s) below c = 2.8 mol%. This oxygen defect then captures a low-angular-momentum Zr-5p65s2 electron to form an sp hybrid orbital, which exhibits a stable phase structure. When c > 2.8 mol%, each accumulated VO-p defect captures a high-angular-momentum Zr-4dz electron and two Si-pz electrons to create delocalized Si4+ → Si2+ charge disproportionation. Therefore, we suggest that the optimal amount of Pu cannot exceed 7.5 mol% because of the formation of a mixture of ZrO8 polyhedral and SiO4 tetrahedral phases with the orientation (10-1). This study offers new perspective on the development of highly stable zircon-based solid solution materials

  7. Influence of self-irradiation damages on the superconducting behaviour of Pu-based compounds

    Energy Technology Data Exchange (ETDEWEB)

    Jutier, Frederic [European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, Karlsruhe 76125 (Germany)]. E-mail: frederic.jutier@itu.fzk.de; Griveau, Jean-Christophe [European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, Karlsruhe 76125 (Germany); Colineau, Eric [European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, Karlsruhe 76125 (Germany); Rebizant, Jean [European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, Karlsruhe 76125 (Germany); Boulet, Pascal [European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, Karlsruhe 76125 (Germany); Wastin, Franck [European Commission, Joint Research Centre, Institute for Transuranium Elements, Postfach 2340, Karlsruhe 76125 (Germany); Simoni, Eric [Institut de Physique Nucleaire, Orsay cedex 91406 (France)

    2005-04-30

    Ageing effects on the critical parameters (T{sub c}, H{sub c2}) of the superconductors PuCoGa{sub 5} and PuRhGa{sub 5} are presented. A linear diminution of the critical temperature versus sample ageing is observed. The diminution rate of T{sub c} is larger for PuRhGa{sub 5} ({delta}T{sub c}/{delta}{approx}-0.39K/month) than for PuCoGa{sub 5} ({delta}T{sub c}/{delta}t{approx}-0.24K/month). The damages created by self-irradiation (from {sup 239}Pu decay) also act as pinning centres, enhancing H{sub c2}(0) with ageing. After 532 days, the PuCoGa{sub 5} sample shows an increase of its H{sub c2}(0) up to1350kOe, whereas in the case of PuRhGa{sub 5}, the damages produced after only 323 days of ageing destroy the superconductivity. These results suggest that both compounds are surprisingly not equally sensitive to radiation damages.

  8. Sequential process test for metal pyro-processing using U, Pu, and Am

    Energy Technology Data Exchange (ETDEWEB)

    Masaki Kurata; Noboru Yahagi [Central research Institute of Electric Power Industry, Iwadokita 2-11-1, Komae, Tokyo 201-8511 (Japan); Shinichi Kitawaki; Akira Nakayoshi; Mineo Fukushima [Japan Atomic Energy Agency, Muramatsu 4-33, Tokai-mura, Naka-gun, Ibaraki 319-1194 (Japan)

    2008-07-01

    The Central Research Institute of Electric Power Industry (CRIEPI) and the Japan Atomic Energy Agency (JAEA) are continuing a collaboration study for metal pyro-processing, in which sequential process tests have been performed under practical conditions using {approx}1 kg of molten salt baths. Recent results on two kinds of sequential process test are reported. The former is the electro-chemical reduction test of MOX pellet in order to form U-Pu alloy ingots. The latter is the electrolysis test using a combination of U-Pu alloy anode and solid or liquid cadmium cathode to recover U-product or U-Pu-Am alloy product, respectively. Variation in electrode potentials, current efficiency, molten salt composition, Pu- or Am-impurity in the U-product, U/Pu or Am/Pu separation factor in the U-Pu alloy product, and etc. were measured. These tests reproduced practical operating conditions at a scale of {approx}1/1000 that of the actual process. (author)

  9. The removal of inhaled 239Pu from beagle dogs by bronchopulmonary lavage and chelation therapy

    International Nuclear Information System (INIS)

    The efficacy of bronchopulmonary lavage and chelatan therapy for removing 239Pu from beagle dogs after inhalation of 239Pu aerosols having different solubilities has been investigated. The four aerosols used were nebulized from a solution of 239PuCl4 and heat treated at temperatures of 325, 600, 900 and 11500C. Groups of six beagle dogs were exposed to each of the aerosols. Subsequently, three dogs in each group were treated by lavage and intravenous injections of DTPA. The remaining three dogs in each group served as untreated controls. It was found that bronchopulmonary lavage treatment was effective in removing nearly half of the 239Pu activity from the lung regardless of the aerosol production temperature. This early removal of 239Pu activity resulted in a significant reduction in daily dose rate and therefore cumulative α dose to lung. The effectiveness of DTPA treatment depended on aerosol production temperature, and was effective in reducing accumulation of 239Pu in liver and skeleton of the dogs that inhaled aerosols produced at 3250 and 6000C by enhancing urinary excretion of 239Pu. (U.K.)

  10. Modeling of constituent redistribution and fission product migration in fast reactor U-Pu-Zr fuel

    International Nuclear Information System (INIS)

    Radial constituent redistribution in a fast reactor U-Pu-Zr fuel is an important phenomenon that occurs because the fuel alloy has thermal gradients and poly-phase fields at the typical operation temperature. In a typical temperature range (500-700degC), Zr moves from the mid-radius region to the fuel center region and the fuel surface region. Because of this phenomenon, the homogeneous fuel at beginning of life turns into locally heterogeneous fuel. Most of the thermophysical properties change locally, as does fuel performance. Fuel constituent redistribution of U-Pu-Zr is modeled by treating Pu as sessile element and therefore by assuming a pseudo-binary system. Fission product lanthanides (LA) migrate to the fuel surface. LA migration appears to be due both to direct vapor transport and diffusion through the fuel matrix. Large pores at the low Zr zone and fuel periphery may support for LA precipitates. LA diffusion through Pu also contributes to observed LA migration. Because Pu is relatively sessile, however, LA migration by diffusion through the fuel matrix is relatively small. Upon migration to the fuel surface, LA and Pu react with Fe-base alloy cladding such as HT9 and D9 whereas U and Zr do not. The LA and Pu reaction with cladding is via interdiffusion. (author)

  11. Modeling of Pu(IV) extraction and HNO3 speciation in nuclear fuel reprocessing

    International Nuclear Information System (INIS)

    The PUREX process is a solvent extraction method dedicated to the reprocessing of irradiated nuclear fuel in order to recover pure uranium and plutonium from aqueous solutions of concentrated nitric acid. The tri-n-butylphosphate (TBP) is used as the extractant in the organic phase. The aim of this thesis work was to improve the modeling of liquid-liquid extraction media in nuclear fuel reprocessing. First, Raman and 14N NMR measurements, coupled with theoretical calculations based on simple solutions theory and BIMSA modeling, were performed in order to get a better understanding of nitric acid dissociation in binary and ternary solutions. Then, Pu(IV) speciation in TBP after extraction from low nitric acid concentrations was investigated by EXAFS and vis-NIR spectroscopies. We were able to show evidence of the extraction of Pu(IV) hydrolyzed species into the organic phase. A new structural study was conducted on An(VI)/TBP and An(IV)/TBP complexes by coupling EXAFS measurements with DFT calculations. Finally, extraction isotherms modeling was performed on the Pu(IV)/HNO3/H2O/TBP 30%/dodecane system (with Pu at tracer scale) by taking into account deviation from ideal behaviour in both organic and aqueous phases. The best modeling was obtained when considering three plutonium (IV) complexes in the organic phase: Pu(OH)2(NO3)2(TBP)2, Pu(NO3)4(TBP)2 and Pu(NO3)4(TBP)3. (author)

  12. Bilateral MOX projects for W-grade Pu disposition: Safety implications

    International Nuclear Information System (INIS)

    Beginning from 1992 a number of studies were performed in Russia in the field of peaceful utilization of the excess Weapon-derived Plutonium (W-Pu). Very important results were obtained from Russian-German, Russian-French, Russian-Canadian Feasibility Studies and from the US-Russian Projects. These Studies have demonstrated technical feasibility of W-Pu conversion into MOX-fuel and its utilization in certain power reactors. Technical feasibility implies safety assurance for all stages of W-Pu management. All safety-related aspects (e.g. reactor safety, nuclear criticality, fire and explosion safety, protective barriers reliability, etc.) have to be taken into account for implementation of W-Pu utilization through MOX-route. Safety has to be guarantied for such W-Pu-related activities as: Plutonium interim storage; Plutonium conversion from metal to oxide; MOX fuel fabrication and transportation; MOX irradiation in power reactor; MOX spent fuel management; Pu-bearing waste minimization and waste management; Radiological protection of the personnel and environment. Paper addresses to safety-related issues of W-Pu conversion into oxide form and MOX- fuel fabrication. Some results of Russian-German and Russian-French (AIDA-MOX 1) Studies are discussed. (author)

  13. Minimal PU.1 reduction induces a preleukemic state and promotes development of acute myeloid leukemia.

    Science.gov (United States)

    Will, Britta; Vogler, Thomas O; Narayanagari, Swathi; Bartholdy, Boris; Todorova, Tihomira I; da Silva Ferreira, Mariana; Chen, Jiahao; Yu, Yiting; Mayer, Jillian; Barreyro, Laura; Carvajal, Luis; Neriah, Daniela Ben; Roth, Michael; van Oers, Johanna; Schaetzlein, Sonja; McMahon, Christine; Edelmann, Winfried; Verma, Amit; Steidl, Ulrich

    2015-10-01

    Modest transcriptional changes caused by genetic or epigenetic mechanisms are frequent in human cancer. Although loss or near-complete loss of the hematopoietic transcription factor PU.1 induces acute myeloid leukemia (AML) in mice, a similar degree of PU.1 impairment is exceedingly rare in human AML; yet, moderate PU.1 inhibition is common in AML patients. We assessed functional consequences of modest reductions in PU.1 expression on leukemia development in mice harboring DNA lesions resembling those acquired during human stem cell aging. Heterozygous deletion of an enhancer of PU.1, which resulted in a 35% reduction of PU.1 expression, was sufficient to induce myeloid-biased preleukemic stem cells and their subsequent transformation to AML in a DNA mismatch repair-deficient background. AML progression was mediated by inhibition of expression of a PU.1-cooperating transcription factor, Irf8. Notably, we found marked molecular similarities between the disease in these mice and human myelodysplastic syndrome and AML. This study demonstrates that minimal reduction of a key lineage-specific transcription factor, which commonly occurs in human disease, is sufficient to initiate cancer development, and it provides mechanistic insight into the formation and progression of preleukemic stem cells in AML. PMID:26343801

  14. Biokinetics aand dosimetry of inhaled 238PuO2 in the beagle dog: An update

    International Nuclear Information System (INIS)

    The temporal and spatial distributions of 238Pu have been measured during the course of a dose-response study of the biological effects of inhaled 238PuO2 in Beagle dogs. These measurements were done on the dose-response study animals, as well as a separate group of dogs exposed to similar aerosols and killed serially out to 4 y after exposure. The data from this latter group provided the basis for the development of a biokinetic/dosimetric model for 238PuO2 in dogs. Since the publication of this model, several important findings have been made that affected the dosimetric evaluations. The first involved the discovery of significant quantities of natural uranium (U) in the feces samples. The U was measured with the plutonium (Pu), which inflated the values for purported Pu in feces. The second finding involved the addition of Pu biokinetics data from the dose-response dogs, which increased the period of observation from 4 y to 15 y; these later data were not consistent with the earlier model predictions. The purpose of this investigation was (1) to remove the analytical bias in the 238Pu radiochemical data due to the U and (2) to modify the original model of Mewhinney and Diel, taking into account all data from both studies

  15. Nuclear safe Pu - ceramics defects and behavior during self-irradiation

    Energy Technology Data Exchange (ETDEWEB)

    Timofeeva, L.F.; Filin, V.M.; Shishkov, N.V.; Bulkin, V.I.; Zhmak, V.A.; Krivova, V.I.; Semova, E.A. [FGUP VNIINM, Moscow (Russian Federation)

    2002-11-01

    Methods of X-ray diffraction analysis and positron spectroscopy are used to study initial stages of self-irradiation of nuclear safe homogeneous and heterogeneous type ceramics (Hf, Pu) and (Hf, Pu, Y). Different character of the change in FCC lattice parameter of binary (Hf{sup +4}, Pu{sup +4}) and ternary (Hf{sup +4}, Pu{sup +4}, Y{sup +3}) oxide solid solutions during storage is shown. Three micro-defect types are detected with the method of positron lifetime. The effective positron lifetime (T{sub f}) individual for each sample depends on displacement dose (dpa during storage): it is increases {approx}1.5 times faster in PuO{sub 2} than in (Hf, Pu) and (Hf, Pu, Y) ceramics. Another positron annihilation spectrum characteristic, i.e. spectrum half-width at half maximum, T{sub 1/2}, depends on the displacement dose and is changes in different manner for different types ceramics. (author)

  16. Concentrations of sup(239,240)Pu and 241Am in drinking water and organic fertilizer

    International Nuclear Information System (INIS)

    As part of an investigation of the chemistry and aquatic distribution of fallout-derived sup(239,240)Pu and 241Am in the aquatic environment a study has been made of the concentration of these nuclides in the drinking water and organic fertilizer, distributed to the populace of the Chicago area. The results clearly indicate that the concentration of sup(239,240)Pu is always lower in the water which has been treated at the Chicago Central Water Filtration Plant than in the raw water before treatment. Raw water levels are consistent with normal levels of sup(239,240)PU found in Lake Michigan waters which are approx 6 orders of magnitude below the maximum permissible concentration standard for drinking water. An additional possible source of sup(239,240)Pu and 241Am to humans can be through the distribution of the organic fertilizer, 'Nu Earth', by the Metropolitan Sanitary District, free of charge, for the use in home gardens. 'Nu Earth' consists primarily of sediment from an Imhoff Process which has been air-dried and aged in large, open-air piles. Samples of this organic fertilizer were analysed for sup(239,240)Pu and 241Am. The results indicate that there is little evidence to indicate that sup(239,240)Pu in drinking water or sup(239,240)Pu and 241Am from organic sludge will be health hazards in the Chicago area under current conditions. (U.K.)

  17. Contribution to the study of U-Ti and U-Pu-Ti carbides; Contribution a l'etude des carbures U-C-Ti et (U, Pu) - C-Ti

    Energy Technology Data Exchange (ETDEWEB)

    Milet, C.A. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    After having discussed the reasons to use (U,Pu) carbides as fast reactor fuel, we examine the influence of the addition of titanium to these carbides. A preliminary study has been done on the system of U-C-Ti and some properties have been measured such as: density, thermal expansion, electrical resistivity, atmospheric corrosion and compatibility with stainless steel. The systems U-Pu-C-Ti (Pu/U + Pu equal to 15 per cent) and U-C-Ti have been found to be very similar. There exists a two phases region (U,Pu)C + TiC, an eutectic between (U,Pu)C and TiC for approximately 15 at %. The solubilities of U + Pu in TiC and of Ti in (U,Pu)C is less than 1 % at. The addition of titanium does not markedly change thermal expansion coefficients of (U,Pu)C. However the resistance to atmospheric corrosion and compatibility with stainless steel is improved. Thermal conductivity, calculated from electrical resistivity, has increased. On the other side, the density of fissile material is lowered. The combination of (U,Pu)C + TiC seems to be the most promising alloy for application as nuclear fuel. (author) [French] Apres avoir rappele les problemes poses par un combustible pour les reacteurs a neutrons rapides et l'interet des carbures U-Pu-C comme combustible, on examine l'influence de l'addition de titane dans ces carbures. Une etude preliminaire sur le systeme U-C-Ti a ete effectuee et quelques proprietes sont indiquees: densite, coefficients de dilatation, resistivite electrique, tenue a la corrosion atmospherique, compatibilite avec l'acier inoxydable. Le systeme U-Pu-C-Ti (Pu/U + Pu egal a 15 pour cent) presente de grandes analogies avec le systeme U-C-Ti. Il existe un domaine biphase (U,Pu)C + TiC, un eutectique entre (U,Pu)C et TiC pour environ 15 at % Ti; les solubilites de U + Pu clans TiC et de Ti dans (U,Pu)C sont inferieures a 1 at %. Par rapport a la phase (U,Pu)C, l'addition de titane est sans effets importants sur les coefficients de

  18. Sediment core record of global fallout and Bikini close-in fallout Pu in Sagami Bay, Western Northwest Pacific margin.

    Science.gov (United States)

    Zheng, Jian; Yamada, Masatoshi

    2004-07-01

    The total 239-240Pu activity and 240Pu/239Pu atom ratio in the sediments in Sagami Bay of the western Northwest Pacific margin were investigated using ICP-MS with a shield torch system. 239+240Pu inventories in the examined sediment cores were found to be much higher than those predicted from atmospheric global fallout (42 MBq/km2) at the same latitude. In addition, elevated 240Pu/239Pu atom ratios ranging from 0.22 to 0.28 were observed in the sediment samples. On the basis of the vertical profiles of 239+240Pu and characterized 240Pu/239Pu atom ratios in a sediment core collected in the center of Sagami Bay, we identified two distinct sources of fallout Pu in the bay: the global stratospheric fallout with characteristic 240Pu/239Pu ratio of 0.18 and the transported close-in fallout derived from Bikini and Enewetak surface nuclear weapon test series in the 1950s. We propose that the Pu transportation was mainly due to oceanic processes (for example, through the North Equatorial Current and the Kuroshio Current). Using a two fallout end-member model, we find that the contribution of Bikini close-in fallout Pu ranged from 44 to 59% in Sagami Bay sediments. To the best of our knowledge, this is the first report that Pu contamination, which originated from Bikini and Enewetak nuclear weapon test series in the 1950s, has extended westwards as far as the Japanese coast. PMID:15296298

  19. Application of a canine {sup 238}Pu dosimetry model to human bioassay data

    Energy Technology Data Exchange (ETDEWEB)

    Hickman, A.W. Jr. [Florida Univ., Gainesville, FL (United States)

    1991-08-01

    Associated with the use of 2{sup 238}Pu in thermoelectric power sources for space probes and power supplies for cardiac devices is the potential for human exposure to {sup 238}Pu, primarily by inhalation. In the event of human internal exposure, a means is needed for assessing the level of intake and calculating radiation doses. Several bioassay/dosimetry models have been developed for {sup 239}Pu. However, results from studies with laboratory animals have indicated that the biokinetics, and therefore the descriptive models, of {sup 238}Pu are significantly different from those for {sup 239}Pu. A canine model accounting for these differences has been applied in this work to urinary excretion data from seven humans occupationally exposed to low levels of an insoluble {sup 238}Pu compound. The modified model provides a good description of the urinary excretion kinetics observed in the exposed humans. The modified model was also used to provide estimates of the initial intakes of {sup 238}Pu for the seven individuals; these estimates ranged from 4.5 nCi (170 Bq) to 87 nCi (3200 Bq). Autopsy data on the amount and distribution of {sup 238}Pu retained in the organs may be used in the future to validate or refute both these estimates and the assumptions used to formulate the human model. Modification of the human model to simulate an injection exposure to {sup 239}Pu gave patterns of retention in the organs and urinary excretion comparable to those seen previously in humans; further modification of the model using fecal data (unavailable for the subjects of this study) is indicated.

  20. Plants as bio-monitors for Cs-137, Pu-238, Pu-239,240 and K-40 at the Savannah River Site.

    Science.gov (United States)

    Caldwell, Eric Frank; Duff, Martine C; Ferguson, Caitlin E; Coughlin, Daniel P

    2011-05-01

    The Savannah River Site was constructed in South Carolina to produce plutonium (Pu) in the 1950s. Discharges associated with these now-ceased operations have contaminated large areas within the site, particularly streams associated with reactor cooling basins. Evaluating the exposure risk of contamination to an ecosystem requires methodologies that can assess the bioavailability of contaminants. Plants, as primary producers, represent an important mode of transfer of contaminants from soils and sediments into the food chain. The objective of this study was to identify local area plants for their ability to act as bio-monitors of radionuclides. The concentrations of cesium-137 ((137)Cs), potassium-40 ((40)K), (238)Pu and (239,240)Pu in plants and their associated soils were determined using γ and α spectrometry. The ratio of contamination concentration found in the plant relative to the soil was calculated to assess a concentration ratio (CR). The highest CR for (137)Cs was found in Pinus palustris needles (CR of 2.18). The correlation of soil and plant (137)Cs concentration was strong (0.76) and the R(2) (0.58) from the regression was significant (p = 0.006). This suggests the ability to predict the degree of (137)Cs contamination of a soil through analysis of the pine needles. The (238)Pu and (239,240)Pu concentrations were most elevated within the plant roots. Extremely high CR values were found in Sparganium americanum (bur-reed) roots with a value of 5.86 for (238)Pu and 5.66 for (239,240)Pu. The concentration of (40)K was measured as a known congener of (137)C. Comparing (40)K and (137)C concentrations in each plant revealed an inverse relationship for these radioisotopes. Correlating (40)K and (137)Cs was most effective in identifying plants that have a high affinity for (137)Cs uptake. The P. palustris and S. americanum proved to be particularly strong accumulators of all K congeners from the soil. Some species that were measured, warrant further

  1. Routine radiochemical method for the determination of 90Sr, 238Pu, 239+240Pu, 241Am and 244Cm in environmental samples

    International Nuclear Information System (INIS)

    Routine analytical procedures have been developed for the reliable simultaneous determination of 90Sr, 238Pu, 239+240Pu, 241Am and 242-244Cm, Chernobyl derived radioisotopes and fallout after nuclear weapon tests in a wide range of environmental samples: soil (100-200 g), sediments, aerosols, water and vegetation. This procedure has been applied to thousands of soil and sediment samples and hundreds of biological and water samples taken in the exclusive zone of Chernobyl NPP and different regions of Ukraine from 1989 to the present. After the sample has been properly prepared and isotopic tracers added, plutonium, americium and curium are precipitated with calcium oxalate and then lanthanum fluoride. Plutonium is separated from americium and curium by anion-exchange. Americium and curium are separated from rare earths by cation-exchange with gradient elute α-hydroxy-iso-butyric acid. During projects by AQCS IAEA 'Evaluation of Methods for 90Sr in a Mineral Matrix' and 'Proficiency Test for 239Pu, 241Pu and 241Am Measurement in a Mineral Matrix' accuracy and precision for 90Sr, 239Pu and 241Am by present procedure was evaluated. Advantages, difficulties and limitations of the method are discussed. (author)

  2. Observations of surface-mediated reduction of Pu(VI) to Pu(IV) on hematite nanoparticles by ATR FT-IR

    International Nuclear Information System (INIS)

    Previous studies have shown that mineral surfaces may facilitate the reduction of plutonium though the mechanisms of the reduction are still unknown. The objective of this study is to use batch sorption and attenuated total reflectance Fourier transform infrared spectroscopy experiments to observe the surface-mediated reduction of plutonium on hematite nanoparticles. These techniques allow for in situ measurement of reduction of plutonium with time and may lead to a better understanding of the mechanisms of surface mediated reduction of plutonium. For the first time, ATR FT-IR peaks for Pu(VI) sorbed to hematite are measured at ∝ 916 cm-1, respectively. The decrease in peak intensity with time provides a real-time, direct measurement of Pu(VI) reduction on the hematite surface. In this work pseudo first order rate constants estimated at the high loadings (22 mgPu/ghematite, 1.34 x 10-6 MPu/m2) for ATR FT-IR are approximately 10 x slower than at trace concentrations based on previous work. It is proposed that the reduced rate constant at higher Pu loadings occurs after the reduction capacity due to trace Fe(II) has been exhausted and is dependent on the oxidation of water and possibly electron shuttling based on the semiconducting nature of hematite. Therefore, the reduction rate at higher loadings is possibly due to the thermodynamic favorability of Pu(IV)-hydroxide complexes.

  3. Monte Carlo analysis of Pu-H2O and UO2-PuO2-H2O critical assemblies with ENDF/B-IV data

    International Nuclear Information System (INIS)

    A set of critical experiments, comprising thirteen homogeneous Pu-H2O assemblies and twelve UO2-PuO2 lattices, was analyzed with ENDF/B-IV data and the RCPO1 Monte Carlo program, which modeled the experiments explicitly. Some major data sensitivities were also evaluated. For the Pu-H2O assemblies, calculated K/sub eff/ averaged 1.011. The large (2.7%) scatter of K/sub eff/ values for these assemblies was attributed mostly to uncertainties in physical specifications since no clear trends of K/sub eff/ were evident and data sensitivities were insignificant. The UO2-PuO2 lattices showed just one trend of K/sub eff/, which indicated an overprediction of U238 capture consistent with that observed for uranium-H2O experiments. There was however a approx. 1% discrepancy in calculated K/sub eff/ between the two sets of UO2-PuO2 lattices studied

  4. Molecular analysis of the interaction between the hematopoietic master transcription factors GATA-1 and PU.1

    DEFF Research Database (Denmark)

    Liew, Chu Wai; Rand, Kasper Dyrberg; Simpson, Raina J Y; Yung, Wendy W; Mansfield, Robyn E; Crossley, Merlin; Proetorius-Ibba, Mette; Nerlov, Claus; Poulsen, Flemming M; Mackay, Joel P

    2006-01-01

    GATA-1 and PU.1 are transcription factors that control erythroid and myeloid development, respectively. The two proteins have been shown to function in an antagonistic fashion, with GATA-1 repressing PU.1 activity during erythropoiesis and PU.1 repressing GATA-1 function during myelopoiesis. It has...... also become clear that this functional antagonism involves direct interactions between the two proteins. However, the molecular basis for these interactions is not known, and a number of inconsistencies exist in the literature. We have used a range of biophysical methods to define the molecular details...

  5. Overview of activities on Pu and minor actinides fuel research in JAERI

    Energy Technology Data Exchange (ETDEWEB)

    Arai, Yasuo; Yamashita, Toshiyuki [Japan Atomic Energy Research Inst., Tokai (Japan)

    1997-12-31

    Recent activities on Pu and minor actinides fuel research in JAERI is summarized. For oxide fuel, the solid state chemistry on U-Np-Pu-O system has been investigated. Further, Pu rock-like fuel has been developed from the viewpoint of disposing excess plutonium. For nitride fuel, research on fuel fabrication, property measurements, irradiation behavior and application to pyrochemical reprocessing has been carried out. These studies aim at contributing to the development of advanced fuel cycle and innovative fuel cycle toward the 21st century. (author). 25 refs.

  6. 'Static columns' for the assessment of the microbial solubilization of Pu in saturated systems

    International Nuclear Information System (INIS)

    Full text of publication follows: Over the last several years, mounting evidence has indicated that small amounts of Pu are mobile in saturated groundwater systems. For the most part, models of Pu transport via the 'colloid pathway' have focused on Pu transport by inorganic colloidal species [1]. However, it is clear from our recent laboratory studies that bacterial metabolic products such as citric, alginic and galacturonic acids, and extracellular polysaccharides (EPS), are capable of complexing Pu; such complexes have the potential of fostering the transport of Pu under advective flow conditions. In addition, microbial activity can alter the local geochemical environment through such processes as the reductive solubilization of Fe(III) oxides. We used batch reactors and 'static columns' [2] to examine the microbially-stimulated 'solubilization' of Pu. One advantage of the use of static columns over more traditional batch experiments is that they allow the assessment of the potential for Pu transport at solid / solution ratios appropriate for saturated groundwater systems without the complexity of full column studies. Batch and static columns were employed using soil from Rocky Flats, Colorado, USA, and stimulation of metabolic activity of indigenous soil microorganisms by the addition of electron donors. Soils under study have 239,240Pu activities ranging from 50 - 300 pCi / g. Amendments of soil isolates with glucose resulted in the production of Fe(II) and 'mobile' Pu (approximately 4 % of the soil Pu was found in the solution phase as compared to deionized water-amended controls). These results indicate that fermentative microbial activity can mobilize Pu as Pu colloids in contaminated soil, possibly due to dissolution of iron phases and or complexation with microbial exudates. [1] Honeyman, B.D. and J.F. Ranville (2002). Colloid properties and their effects on radionuclide transport through soil and groundwaters. Soil Geochemical Process of Radionuclides

  7. PU.1 can participate in an active enhancer complex without its transcriptional activation domain

    OpenAIRE

    Pongubala, Jagan M. R.; Atchison, Michael L.

    1997-01-01

    The transcription factor PU.1 is necessary for the development of multiple hematopoietic lineages and contributes to the activity of the immunoglobulin κ 3′ enhancer. A variety of proteins bind to the 3′ enhancer (PU.1, PIP, ATF1, CREM, c-Fos, c-Jun, and E2A), but the mechanism of 3′-enhancer activity and the proteins necessary for its activity are presently unclear. We show here that PU.1 participates with other transcription factors in forming a higher-order complex with 3′-enhancer DNA seq...

  8. Systematic Investigation of the Superconducting Behavior in Aged PuCoGa5

    International Nuclear Information System (INIS)

    In this work, we have undertaken to follow the evolution of the PuCoGa5 superconducting behavior as a function of the damages created by self-radiation effects induced from the Pu-decay. It is shown that the critical temperature is particularly sensitive with ageing. Ageing effects on fundamental parameters such as the lattice parameters of the PuCoGa5 and the electrical resistivity provide some new hints of the unconventional character of the superconductivity in this class of materials. (authors)

  9. Deposition of air-borne 238Pu near a chemical separation facility

    International Nuclear Information System (INIS)

    Three methods were compared to measure deposition of 238Pu released from a chemical separation facility at the Savannah River Plant, Aiken, SC. The following methods were used: adhesive paper; a collector of rain and dryfall; and soil samples. Excellent agreement among the three methods was found. The measured deposition for the particular source term and meteorological conditions at the Savannah River Plant is described by y proportional to x/sup -1.36/ where y is the pCi of 238Pu deposited per square meter per mC: 238Pu released, and x is distance in meters from the source

  10. PU.1 and C/EBPα/β convert fibroblasts into macrophage-like cells

    OpenAIRE

    Feng, Ru; Desbordes, Sabrina C.; Xie, Huafeng; Tillo, Ester Sanchez; Pixley, Fiona; Stanley, E. Richard; Graf, Thomas

    2008-01-01

    Earlier work has shown that the transcription factor C/EBPα induced a transdifferentiation of committed lymphoid precursors into macrophages in a process requiring endogenous PU.1. Here we have examined the effects of PU.1 and C/EBPα on fibroblasts, a cell type distantly related to blood cells and akin to myoblasts, adipocytes, osteoblasts, and chondroblasts. The combination of the two factors, as well as PU.1 and C/EBPβ, induced the up-regulation of macrophage/hematopoietic cell surface mark...

  11. 239+240Pu and 90Sr deposition densities in undisturbed surface soil in Vietnam

    International Nuclear Information System (INIS)

    The study's goal is determination of 239+240Pu and 90Sr deposition densities from known distribution of 137Cs deposition density. The tasks done include: simultaneous determination of 239+240Pu, 90Sr and 137Cs deposition densities in undisturbed surface soil layer having depth to 20 cm and use it as basis for determining the ratios of deposition densities 239+240Pu/137Cs and 90Sr/137Cs; studying the impact of soil parameters such as soil texture, content of organic matter, Humic, Fulvic as well as of geography parameters such as latitude, longitude, annual rainfall to the variation of these ratios. (NHA)

  12. Numerical prediction of 239Pu migration in unsaturated porous media under infiltration scenario

    International Nuclear Information System (INIS)

    In terms of the study on site selection of a radioactive waste disposal repository in northwest China, a numerical prediction of 239Pu migration for potential groundwater pollution in the unsaturated zone was conducted with the HYDRUS-1D model. The results showed that the groundwater will not be contaminated by the migration of soluble 239Pu. And there is little possibility that 239Pu migration through groundwater path might have an unacceptable impact on exosphere. Measurements of the distribution coefficient, Kd, are critical in the determination of sorption-induced retardation of radionuclide transport. (authors)

  13. Effects of pregnancy and lactation on the toxicity of 239Pu

    International Nuclear Information System (INIS)

    Nulliparous, pregnant, or lactating Wistar rats were injected intravenously with 0, 0.5 or 2.0 μCi of 239Pu per kilogram of body weight. Half of each group were repeatedly bred while the others were held for observation without further treatment. Treatment with either dose of 239Pu decreased the median time to appearance of mammary tumors. Repeated breeding tended to increase the mean time to appearance. Longevity was decreased in a dose-related fashion by Pu administration. Repeated breeding did not influence survival in a major way

  14. PU.1 Suppresses Th2 Cytokine Expression via Silencing of GATA3 Transcription in Dendritic Cells.

    Directory of Open Access Journals (Sweden)

    Takuya Yashiro

    Full Text Available The transcription factor PU.1 is predominantly expressed in dendritic cells (DCs and is essential for DC differentiation. Although there are several reports that PU.1 positively regulates the expression of DC-specific genes, whether PU.1 also has a suppressive effect on DCs is largely unknown. Here we demonstrate that PU.1 suppresses the expression of Th2 cytokines including IL-13 and IL-5 in bone marrow-derived DCs (BMDCs, through repression of the expression of GATA3, which is a master regulator of Th2 differentiations. When PU.1 siRNA was introduced into BMDCs, LPS-induced expression of IL-13 and IL-5 was increased along with upregulation of the constitutive expression of GATA2 and GATA3. The additional introduction of GATA3 siRNA but not of GATA2 siRNA abrogated PU.1 siRNA-mediated upregulation of IL-13 and IL-5. A chromatin immunoprecipitation assay showed that PU.1 bound to Gata3 proximal promoter region, which is more dominant than the distal promoter in driving GATA3 transcription in DCs. The degree of histone acetylation at the Gata3 promoter was decreased in PU.1 siRNA-introduced DCs, suggesting the involvement of PU.1 in chromatin modification of the Gata3 promoter. Treatment with a histone deacetylase (HDAC inhibitor, trichostatin A, increased the degree of histone H3 acetylation at the Gata3 promoter and induced the subsequent expression of GATA3. Experiments using HDAC inhibitors and siRNAs showed that HDAC3 suppressed GATA3 expression. The recruitment of HDAC3 to the Gata3 promoter was decreased by PU.1 knockdown. LPS-induced IL-13 expression was dramatically reduced in BMDCs generated from mice lacking the conserved GATA3 response element, termed CGRE, which is an essential site for the binding of GATA3 on the Il-13 promoter. The degree of H3K4me3 at CGRE was significantly increased in PU.1 siRNA-transfected stimulated DCs. Our results indicate that PU.1 plays pivotal roles in DC development and function, serving not only as a

  15. ZPR-6 assembly 7 high {sup 240} PU core : a cylindrical assemby with mixed (PU, U)-oxide fuel and a central high {sup 240} PU zone.

    Energy Technology Data Exchange (ETDEWEB)

    Lell, R. M.; Schaefer, R. W.; McKnight, R. D.; Tsiboulia, A.; Rozhikhin, Y.; Nuclear Engineering Division; Inst. of Physics and Power Engineering

    2007-10-01

    Over a period of 30 years more than a hundred Zero Power Reactor (ZPR) critical assemblies were constructed at Argonne National Laboratory. The ZPR facilities, ZPR-3, ZPR-6, ZPR-9 and ZPPR, were all fast critical assembly facilities. The ZPR critical assemblies were constructed to support fast reactor development, but data from some of these assemblies are also well suited to form the basis for criticality safety benchmarks. Of the three classes of ZPR assemblies, engineering mockups, engineering benchmarks and physics benchmarks, the last group tends to be most useful for criticality safety. Because physics benchmarks were designed to test fast reactor physics data and methods, they were as simple as possible in geometry and composition. The principal fissile species was {sup 235}U or {sup 239}Pu. Fuel enrichments ranged from 9% to 95%. Often there were only one or two main core diluent materials, such as aluminum, graphite, iron, sodium or stainless steel. The cores were reflected (and insulated from room return effects) by one or two layers of materials such as depleted uranium, lead or stainless steel. Despite their more complex nature, a small number of assemblies from the other two classes would make useful criticality safety benchmarks because they have features related to criticality safety issues, such as reflection by soil-like material. The term 'benchmark' in a ZPR program connotes a particularly simple loading aimed at gaining basic reactor physics insight, as opposed to studying a reactor design. In fact, the ZPR-6/7 Benchmark Assembly (Reference 1) had a very simple core unit cell assembled from plates of depleted uranium, sodium, iron oxide, U3O8, and plutonium. The ZPR-6/7 core cell-average composition is typical of the interior region of liquid-metal fast breeder reactors (LMFBRs) of the era. It was one part of the Demonstration Reactor Benchmark Program,a which provided integral experiments characterizing the important features of

  16. RAPID DETERMINATION OF 237 NP AND PU ISOTOPES IN WATER BY INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY AND ALPHA SPECTROMETRY

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, S.; Jones, V.; Culligan, B.; Nichols, S.; Noyes, G.

    2010-06-23

    A new method that allows rapid preconcentration and separation of plutonium and neptunium in water samples was developed for the measurement of {sup 237}Np and Pu isotopes by inductively-coupled plasma mass spectrometry (ICP-MS) and alpha spectrometry; a hybrid approach. {sup 238}U can interfere with {sup 239}Pu measurement by ICP-MS as {sup 238}UH{sup +} mass overlap and {sup 237}Np via peak tailing. The method provide enhanced removal of uranium by separating Pu and Np initially on TEVA Resin, then moving Pu to DGA resin for additional removal of uranium. The decontamination factor for uranium from Pu is almost 100,000 and the decontamination factor for U from Np is greater than 10,000. This method uses stacked extraction chromatography cartridges and vacuum box technology to facilitate rapid separations. Preconcentration is performed using a streamlined calcium phosphate precipitation method. Purified solutions are split between ICP-MS and alpha spectrometry so that long and short-lived Pu isotopes can be measured successfully. The method allows for simultaneous extraction of 20 samples (including QC samples) in 4 to 6 hours, and can also be used for emergency response. {sup 239}Pu, {sup 242}Pu and {sup 237}Np were measured by ICP-MS, while {sup 236}Pu, {sup 238}Pu, and {sup 239}Pu were measured by alpha spectrometry.

  17. Analytical method for the determination of Np and Pu in sea water by AMS with respect to the Fukushima accident

    Science.gov (United States)

    Hain, K.; Faestermann, T.; Famulok, N.; Fimiani, L.; Gómez-Guzmán, J. M.; Korschinek, G.; Kortmann, F.; Lierse v. Gostomski, Ch.; Ludwig, P.; Shinonaga, T.

    2015-10-01

    A chemical separation procedure for plutonium (Pu) and neptunium (Np) was developed using extraction chromatography, mass spectrometry and radiometric analysis to determine their concentrations and isotopic ratios in sea water. 241Am, which causes isobaric background to 241Pu in mass spectrometric measurements, was successfully separated from the Pu fraction by this method. Water samples which were spiked with 242Pu and 237Np or 239Np, respectively, were used for chemical yield determination. The chemical yields of Pu and Np, which were determined by alpha and gamma spectrometry at the Radiochemie München (RCM), of more than 85% were obtained. The developed method was applied to analyze the concentration of Pu and Np in the certified reference material, IAEA-443, by Accelerator Mass Spectrometry (AMS) at the Maier-Leibnitz-Laboratory (MLL) to check the applicability of the method to sea water samples. The concentrations of 240Pu, 241Pu and 237Np obtained in this study are in agreement with the certified and literature values within the uncertainties. Due to strong isotopic interference of 239Pu with 238U, it was not possible to analyze the concentration of 239Pu. Some modifications of the chemical separation method to suppress the uranium (U) fraction are under consideration. This method can be used for the analysis of Pu and Np in Pacific Ocean water samples collected after the Fukushima accident.

  18. Application of N,N-ethyl(hydroxyethyl) hydroxylamine in the separation of Pu from U in PUREX process

    International Nuclear Information System (INIS)

    The reduction back-extraction behavior of Pu(IV) from 30% TBP/OK with EHEH was investigated under conditions of different temperatures, different concentration of EHEH and HNO3, various contacting-time and phase ratios respectively. It is show that Pu(IV) from organic phase can be rapidly stripped into aqueous phase by EHEH; the batch stripping percentage of Pu(IV) approach 99% in contacting time of 5 seconds at phase ratio (o/a) 1:1, compared with 89% in 30 seconds at phase ratio (o/a) 4:1. It is also found that the higher reductant concentration, the lower acidity and the higher temperature could speed up the stripping extraction process of Pu. The application of EHEH to separate Pu from U in the 1 B contactor was studied by the 14-stages counter current cascade experiment. It is shown that the recovery percentage of U reaches over 99.999% and the recovery percentage of Pu reaches over 99.99% at phase ratio (1BX : 1BF : 1BS)1 : 4 : 1. The separation factor of Pu from U (α (Pu/U)) is 1.1 x 104; the separation factor of U from Pu(α(U/Pu)) is 3.2 x 105. The results show that EHEH as an organic reductant has obvious effect on the separation of Pu from U. (authors)

  19. Contribution to the study of the (U,Pu)C,N system; Contribution a l'etude du systeme (U,Pu)C,N

    Energy Technology Data Exchange (ETDEWEB)

    Lorenzelli, R. [Commissariat a l' Energie Atomique, Fontenay-aux-Roses (France). Centre d' Etudes Nucleaires

    1968-07-01

    The reactions of UC, PuC, (U,Pu)C, UC{sub 2} and U(C{sub 1-x}O{sub x}) with nitrogen at moderate temperatures (room temperature to 400 C) are described. The influence of the uptake of nitrogen by the powders necessary to sinter the carbides upon the nature of the final product has been investigated; it has been shown that the sintered carbides are hyper-stoichiometric. The reactions of carbon with UN, PuN and (U,Pu)N has also been studied. Under vacuum, carbon reacts on the nitrides at temperatures as low as 1100 C; nitrogen is replaced by carbon and the final product is a carbonitride. The reaction is: MN + x C {yields} MN{sub 1-x}C{sub x} + x/2N{sub 2}. The reaction is limited and the carbonitrides have a fixed composition in presence of M{sub 2}C{sub 3} or MC{sub 2}; hence it is impossible to produce pure MC using the reaction. The ternary diagram U-C-N, Pu-C-N and (U,Pu)C-N have been drawn. They show clearly that it is possible to obtain single phase carbonitrides in a wide domain of compositions. (author) [French] On decrit les reactions avec l'azote de UC, PuC,(U,Pu)C,UC{sub 2} et U(C{sub 1-x}O{sub x}), par action directe de l'azote a temperature moderee (de l'ambiante a 450 C). On a etudie l'influence de la contamination par l'azote des poudres de carbures necessaires au frittage sur la nature des produits frittes; on a montre que les carbures frittes obtenus sont hyperstoechiometriques. On a etudie parallelement les reactions du carbone avec UN, PuN et (U,Pu)N. Sous vide le carbone reagit sur les nitrures des 1100 C: le carbone se substitue a l'azote; l'azote libere est elimine et le produit final est un carbonitrure. La reaction s'ecrit: MN + x C {yields} MN{sub 1-x}C{sub x} + x/2N{sub 2}. La reaction est limitee et les carbonitrures obtenus ont une composition limite fixe en presence des carbures superieurs M{sub 2}C{sub 3} et MC{sub 2}; il est donc impossible d'obtenir MC pur par cette reaction. Les diagrammes

  20. Prompt Fission Neutron Emission in Resonance Fission of 239Pu

    Science.gov (United States)

    Hambsch, Franz-Josef; Varapai, Natallia; Zeinalov, Shakir; Oberstedt, Stephan; Serot, Olivier

    2005-05-01

    The prompt neutron emission probability from neutron-induced fission in the resonance region is being investigated at the time-of-flight facility GELINA of the IRMM. A double Frisch-gridded ionization chamber is used as a fission-fragment detector. For the data acquisition of both the fission-fragment signals as well as the neutron detector signals the fast digitization technique has been applied. For the neutron detection, large-volume liquid scintillation detectors from the DEMON collaboration are used. A specialized data analysis program taking advantage of the digital filtering technique has been developed to treat the acquired data. Neutron multiplicity investigations for actinides, especially in resonance neutron-induced fission, are rather scarce. They are, however, important for reactor control and safety issues as well as for understanding the basic physics of the fission process. Fission yield measurements on both 235U and 239Pu without prompt neutron emission coincidence have shown that fluctuation of the fission-fragment mass distribution exists from resonance to resonance, larger in the case of 235U. To possibly explain these observations, the question now is whether the prompt neutron multiplicity shows similar fluctuations with resonance energy.

  1. Experimental investigations of /sup 238/Pu behavior in soil columns

    Energy Technology Data Exchange (ETDEWEB)

    Nelson, G.B.; Herrera, B.; Stalnaker, N.D.; Coffelt, K.P.; Patterson, J.H.; Heaton, R.C.; Matlack, G.M.

    1984-05-01

    Two series of experiments were conducted to study the transport of plutonium through soils. The first series involved deposition of small quantities (2.0 to 3.5 mg) of particulate /sup 238/Pu oxide on soil columns containing silt loam soil. When deionized water was allowed to percolate through the columns, plutonium was released into the drainage at the rate of 8 to 15 pg/day. During the 6.8-y experiment, the total amount of plutonium released into the soil drainage amounted to less than 0.01% of the original source. Analysis of the soil as a function of depth at the end of the experiment revealed that more than 99% of the deposited source remained in the uppermost fraction (2.8 cm) of the column. The second series of experiments was performed by pumping water containing plutonium through columns of soil and comparing the amount of plutonium in the column effluents to that in the feed. For a loamy sand soil, the plutonium content of the effluent reached a steady state of 5% of the feed after 500 days. Analysis of the soil at the end of the experiment (1200 days) showed the columns to be approximately 50% saturated. Saturation of the soil with plutonium would require 13 ..mu..g/g and 6.6 y at the feed rate used (averaged of 1.2 ..mu..g/g into 300 g of soil).

  2. Experimental investigations of 238Pu behavior in soil columns

    International Nuclear Information System (INIS)

    Two series of experiments were conducted to study the transport of plutonium through soils. The first series involved deposition of small quantities (2.0 to 3.5 mg) of particulate 238Pu oxide on soil columns containing silt loam soil. When deionized water was allowed to percolate through the columns, plutonium was released into the drainage at the rate of 8 to 15 pg/day. During the 6.8-y experiment, the total amount of plutonium released into the soil drainage amounted to less than 0.01% of the original source. Analysis of the soil as a function of depth at the end of the experiment revealed that more than 99% of the deposited source remained in the uppermost fraction (2.8 cm) of the column. The second series of experiments was performed by pumping water containing plutonium through columns of soil and comparing the amount of plutonium in the column effluents to that in the feed. For a loamy sand soil, the plutonium content of the effluent reached a steady state of 5% of the feed after 500 days. Analysis of the soil at the end of the experiment (1200 days) showed the columns to be approximately 50% saturated. Saturation of the soil with plutonium would require 13 μg/g and 6.6 y at the feed rate used (averaged of 1.2 μg/g into 300 g of soil)

  3. MGA, Pu Isotope Abundance from Multichannel Analyzer Gamma Spectra

    International Nuclear Information System (INIS)

    1 - Description of program or function: The MGA (Multiple Group Analysis) program determines the relative abundances of plutonium and other actinide isotopes in different materials. The program analyzes spectra taken of such samples using a 4096-channel germanium (Ge) gamma-ray spectrometer. The code can be run in a one or two detector mode. The first spectrum which is required and must be taken at a gain of .075 keV/channel with a high resolution planar detector, contains the 0-300 keV energy region. The second spectrum, which is optional, must be taken at a gain of 0.25 keV/channel; it becomes important when analyzing high burnup samples (concentration of Pu(241) greater than one percent). Isotopic analysis precision of one percent or better can be obtained, and no calibrations are required. The system also measures the abundances of U(235,238), Np-237, and Am-241. A special calibration option is available to perform a one-time peak-shape characterization when first using a new detector system. 2 - Method of solution: The basic method for determining the relative abundance of the isotopes of plutonium is to measure the intensity of two or more peaks from gamma rays of similar energy, but arising from different isotopes. Since the gamma-ray emission probabilities and half-lives are known, the atom ratios can be calculated provided relative detection efficiencies for the peaks can be estimated

  4. Calculation of 239Pu neutron inelastic cross sections

    International Nuclear Information System (INIS)

    We have calculated cross sections for neutron-induced reactions on 239Pu between 0.001 and 5 MeV, with particular emphasis on inelastic scattering. Coupled-channel and Hauser-Feshbach statistical models were used. Within the coupled-channel calculations we employed neutron optical parameters derived from simultaneous fits to total, elastic, inelastic, and resonance data. The resulting transmission coefficients were used in Hauser-Feshbach statistical calculations having a fission channel based on a double-humped barrier representation. Barrier parameters and transition state enhancements needed to reproduce well the (n,f) cross sections between 0.001 and 5 MeV were in general agreement with those from other published analyses. Calculated compound-nucleus and direct-reaction components for inelastic scattering were combined incoherently, and the resultant cross sections agreed well with the Bruyeres-le-Chatel measurements for scattering from levels occupying the ground state rotational band. Our results are in substantial disagreement with ENDF/B-V values for these levels. We are presently performing DWBA calculations to determine direct-reaction components for states occupying higher-lying vibrational bands

  5. Drawing from experience of safeguarding French Pu-handling facilities

    International Nuclear Information System (INIS)

    Full text: COGEMA operates in France for several years several large Pu-handling facilities: a reprocessing plant: La Hague, and two MOX fuel fabrication facilities : MELOX and Cadarache. Those plants are safeguarded and the operator has gone to great length to allowing inspectorates to perform their duty with a maximum efficiency. While integrated safeguards is how to strengthen with a maximum efficiency, the current safeguarding of those facilities has already been designed in this very same objective. One of the key findings from experience is: the importance of inspectors knowledgeable of the plants and well informed on the specificity of those type of plants; the importance of continuous or nearly continuous presence of the inspectors on the site, allowing an intimate understanding of the facility, and a quick response to would-be anomalies; the enhanced transparency through the willingness of the operator to supply a lot of daily information on material management and making accessible to the inspectors some on-line data; those data shall be treated automatically to help the inspector; but the inspector must then make a judgement and a detailed analysis; the 'unannounced factor' in determining what to control on a given day, or the actual performance or not of a planed inspection, the limit being to avoid disturbing the smooth industrial operation of the plant. Those elements shall allow to reduce some costly measures such as sample taking or sample analyses. (author)

  6. 133Ba as a gamma-ray surrogate source for 1kg HEU and 10g 239Pu and 252Cf as a Neutron Surrogate for Pu

    International Nuclear Information System (INIS)

    Monte Carlo was performed for the purpose of relating gamma-ray signal strength from 1kg of HEU and 10g of 239Pu (as described in the ASTM standards) to the radiation emitted from an amount of 133Ba. A determination was made on the amount of 133Ba that could act as a surrogate for the specified amounts of HEU and Pu. 133Ba is not the ideal source to use as a surrogate for HEU because of its higher energies. 133Ba was chosen as the surrogate since it has a half-life of 10.54 years, rather then the more ideal surrogate of 57Co which has a half-life of 271 days. A similar Monte Carlo was performed for the purpose of relating neutron signal strength from 200g of Pu (as described in the ASTM standards) to the radiation emitted from an amount of shielded 252Cf. A determination was made on the amount of 252Cf necessary to act as a surrogate for the 200g of Pu. An ASTM standard source is a metallic sphere, cube, or right cylinder of SNM having maximum self-attenuation of its emitted radiation. For plutonium, the source should be at least 93% 239Pu, less than 6.5% 240Pu, and less than 0.5% impurities. A cadmium filter of at least 0.08cm thick should be used to reduce the impact of 241Am. For uranium, the source should contain at least 95% 235U and less than 0.25% impurities. For neutron detector testing, the neutron source shall be placed in a lead shielding container that reduces the gamma radiation from the source to 1% of its unshielded value

  7. Synthesis and structures of plutonyl nitrate complexes: is plutonium heptavalent in PuO3(NO3)2(-) ?

    Science.gov (United States)

    Maurice, Rémi; Renault, Eric; Gong, Yu; Rutkowski, Philip X; Gibson, John K

    2015-03-01

    Gas-phase plutonium nitrate anion complexes were produced by electrospray ionization (ESI) of a plutonium nitrate solution. The ESI mass spectrum included species with all four of the common oxidation states of plutonium: Pu(III), Pu(IV), Pu(V), and Pu(VI). Plutonium nitrate complexes were isolated in a quadrupole ion trap and subjected to collision-induced dissociation (CID). CID of complexes of the general formula PuOx(NO3)y(-) resulted in the elimination of NO2 to produce PuOx+1(NO3)y-1(-), which in most cases corresponds to an increase in the oxidation state of plutonium. Plutonyl species, Pu(V)O2(NO3)2(-) and Pu(VI)O2(NO3)3(-), were produced from Pu(III)(NO3)4(-) and Pu(IV)(NO3)5(-), respectively, by the elimination of two NO2 molecules. CID of Pu(VI)O2(NO3)3(-) resulted in NO2 elimination to yield PuO3(NO3)2(-), in which the oxidation state of plutonium could be VII, a known oxidation state in condensed phase but not yet in the gas phase. Density functional theory confirmed the nature of Pu(V)O2(NO3)2(-) and Pu(VI)O2(NO3)3(-) as plutonyl(V/VI) cores coordinated by bidentate equatorial nitrate ligands. The computed structure of PuO3(NO3)2(-) is essentially a plutonyl(VI) core, Pu(VI)O2(2+), coordinated in the equatorial plane by two nitrate ligands and one radical oxygen atom. The computations indicate that in the ground spin-orbit free state of PuO3(NO3)2(-), the unpaired electron of the oxygen atom is antiferromagnetically coupled to the spin-triplet state of the plutonyl core. The results indicate that Pu(VII) is not a readily accessible oxidation state in the gas phase, despite that it is stable in solution and solids, but rather that a Pu(VI)-O· bonding configuration is favored, in which an oxygen radical is involved. PMID:25695878

  8. 238PuO2 surface contamination of radioisotopic heat sources

    International Nuclear Information System (INIS)

    Surface contamination and cleaning characteristics of two radioisotopic heat sources are discussed. The Milliwatt Generator is a small (41/2 W) heat source which is successfully cleaned by hand in a series of hot acid baths.The Multi-Hundred Watt Isotopic Heat Source presents additional problems in removing the surface contamination because of its large size (100 W) and its grit-blasted surface. A study has characterized the behavior of the Pu during aging of the surface at the heat source service temperature of 13500C. Results from this study show that normal decontamination effectively removes the superficial Pu but does not extract the Pu which is deep within the grit-blasted structure. Subsequent heating results in migration of microcurie amounts of Pu out of the grit-blasted surface

  9. The influence of defects on magnetic properties of fcc-Pu

    International Nuclear Information System (INIS)

    The influence of vacancies and interstitial atoms on magnetism in Pu is considered in the framework of the density functional theory. The crystal structure relaxation arising due to various types of defects is calculated using the molecular dynamics method with a modified embedded atom model. The local density approximation with explicit inclusion of Coulomb and spin-orbit interactions is applied in matrix invariant form to describe correlation effects in Pu with these types of defects. The calculations show that both vacancies and interstitials give rise to local moments in the f-shell of Pu in good agreement with experimental data for aged Pu. Magnetism appears due to the destruction of a delicate balance between spin-orbit and exchange interactions

  10. Differences in the initial deposition of Pu and Ra in the skeleton

    International Nuclear Information System (INIS)

    The ratio (still unknown) relating the experimentally determined effects of Pu and Ra in some animal species to observed effects of various isotopes of Ra in man presently provides the most reasonable basis for an assessment of the risk resulting to man from Pu. Extensive studies with the beagle have shown that an evaluation of this ratio on the basis of average skeletal radiation dose is complicated by several factors, one of which is the difference in the initial (gross) distribution of Pu and Ra between the various skeletal parts. Studies on the initial deposition of Pu and Ra in the whole skeleton and in individual parts of the skeleton after injection of the two nuclides as citrates demonstrated that significant differences in the distribution within the various skeletal parts exist, although the total deposition of the two nuclides in the whole skeleton is practically the same

  11. Characterization and property evaluation of U-15 wt%Pu alloy for fast reactor

    Science.gov (United States)

    Kaity, Santu; Banerjee, Joydipta; Ravi, K.; Keswani, R.; Kutty, T. R. G.; Kumar, Arun; Prasad, G. J.

    2013-02-01

    The characterization and high temperature behaviour of U-15 wt%Pu alloy has been investigated in this study for the first time. U-15 wt%Pu alloy sample for this study was prepared by following melting and casting route. Microstructural characterization of the alloy was carried out by XRD and optical microscopy. The thermophysical properties like phase transition temperatures, coefficient of thermal expansion and hot hardness of the above alloy were determined. Eutectic temperature between T91 and U-15 wt%Pu was established. Apart from that, the fuel-cladding chemical compatibility of U-15 wt%Pu alloy with T91 grade steel was studied by diffusion couple experiment.

  12. Characterization of Pu colloidal and aqueous species in Yucca Mountain groundwater surrogate

    International Nuclear Information System (INIS)

    The speciation and formation of Pu intrinsic colloids from an initial solution of Pu(V) were studied at pH 1, pH 3, pH 6, pIH 8, and pH 11. The medium was a surrogate Yucca Mountain groundwater from well J-l 3 under air atmosphere. The solutions were monitored for several months. Samples were analyzed using liquid scintillation counting, ultra filtration, solvent extraction: photon correlation spectroscopy, and laser-induced photo-acoustic breakdown and emission spectroscopy. Redox potentials were measured periodically. The time dependencies of soluble and colloidal Pu concentrations are reported. The size and concentration of Pu colloid particles were estimated

  13. Study of Pretreatment Method for Measurement of Small Quantity of U, Np, Pu in 1AW

    Institute of Scientific and Technical Information of China (English)

    DENG; Wei-qin; TAN; Shu-ping; WU; Ji-zong; TAO; Miao-miao

    2012-01-01

    <正>The analysis of U, Np, Pu in 1AW plays an important role on monitoring of plutonium and uranium recovery and neptunium distribution in co-decontamination cycle. Due to the high radioactivity and the

  14. Feasibility of Burning Civilian Grade Pu in the Modular HTR with Th Fuel Cycle

    Institute of Scientific and Technical Information of China (English)

    许云林; 经荥清

    2001-01-01

    The Modular High Temperature Gas-Cooled Reactor (HTR) can be usedto burn plutonium fuel to reduce Pu stockpiles because of its inherent safety characteristics and ability to burn a variety of fuel mixtures. The equilibrium core is calculated and analyzed for Pu enriched fuel. Fuel spheres with 7 g heavy metal including the civilian grade Pu and thorium are loaded into the reactor. An enrichment of 11% is chosen to provide the desired equilibrium core reactivity. The fuel and moderator temperature coefficients are both negative. The maximum fuel element temperature during normal operation and during a loss of coolant accident is less than 1500 ℃. 92% of 239Pu will be burnt during nomal operation. Therefore, a thorium fuel cycle in the modular HTR is an effective method for burning civilian grade plutonium.

  15. Characterization of Pu colloidal and aqueous species in Yucca Mountain groundwater surrogate

    Energy Technology Data Exchange (ETDEWEB)

    Bourcier, W L; Brachmann, A; Jardine, L J; Palmer, C E; Romanovski, V V; Shaw, H F

    1999-08-11

    The speciation and formation of Pu intrinsic colloids from an initial solution of Pu(V) were studied at pH 1, pH 3, pH 6, pIH 8, and pH 11. The medium was a surrogate Yucca Mountain groundwater from well J-l 3 under air atmosphere. The solutions were monitored for several months. Samples were analyzed using liquid scintillation counting, ultra filtration, solvent extraction: photon correlation spectroscopy, and laser-induced photo-acoustic breakdown and emission spectroscopy. Redox potentials were measured periodically. The time dependencies of soluble and colloidal Pu concentrations are reported. The size and concentration of Pu colloid particles were estimated.

  16. Status of irradiation testing and pie of MOX (Pu-containing) fuel

    International Nuclear Information System (INIS)

    This paper describes AECL's mixed oxide (MOX) fuel-irradiation and post-irradiation examination (PIE) program. Post-irradiation examination results of two major irradiation experiments involving several (U, Pu)02 fuel bundles are highlighted. One experiment involved bundles irradiated to burnups ranging from 400 to 1200 MWh/kgHE in the Nuclear Power Demonstration (NPD) reactor. The other experiment consisted of several (U, Pu)02 bundles irradiated to burnups of up to 500 MWh/kgHE in the National Research Universal (NRU) reactor. Results of these experiments demonstrate the excellent performance of CANDU MOX fuel. This paper also outlines the status of current MOX fuel irradiation tests, including the irradiation of various (U, Pu)02 and (Th, Pu)02 bundles. The strategic importance of MOX fuel to CANDU fuel-cycle flexibility is discussed. (author)

  17. Production enhancement and quality degradation of Pu produced in FBR blankets

    International Nuclear Information System (INIS)

    Full text: For smooth deployment of FBR in near future, securing economy and non-proliferation are pivotal factors. This study has two main objectives related to these two key factors. One is to enhance Pu production efficiency in blanket region of fast breeder reactor core. The other is Pu composition degradation to improve the proliferation resistance of FBR fuel cycle. The former contributes to reduce amount of blanket fuels to be fabricated and reprocessed to gain the same quantity of Pu, consequently it is expected to improve the fuel cycle economy. The composition of Pu generated in FBR blanket generally has very high quality, namely, equal to weapon or super grade. The latter objective is to deteriorate the quality of generated Pu by adjusting neutron spectrum in the blanket region and the initial composition of blanket fuels. A conceptual core design of MOX fueled, sodium cooled FBR with 1500MWe rating is performed by using SLAROM and CIRATION code with nuclear data set prepared for fast reactors of JFS-3-J3.2. The initial fuels in the active core region contains 5% of minor actinides produced in UO2-fueled PWR with enrichment of 4.1% and burnup of 43GWd/t after 10 years cooling. A index FIR (fissile inventory ratio at EOC and BOC) is used to measure the net fissile balance that is suited for fuel cycle mass balance analysis in addition to the BR (breeding ratio) in the standard definition. The moderator material used to tailor the neutron spectrum in the blanket region is ZrH. The depleted uranium pins in the radial blanket are replaced by ZrH pins in the volume fraction range from 0% to 30%. By increasing ZrH pins, the Pu production per unit mass of UO2 in blanket increased from 0.08kg-Pu/kg-UO2 to more than 0.1kg-Pu/kg-UO2. The FIR also slightly improved by replacing small fraction of UO2 by ZrH pins however it turned for the worse in the higher range more than 5% of ZrH. Loading ZrH into blanket fuel assembly drastically affects the Pu composition at

  18. New phenylpropanoid-substituted flavan-3-ols from Pu-er ripe tea.

    Science.gov (United States)

    Tao, Mu-Ke; Xu, Min; Zhu, Hong-Tao; Cheng, Rong-Rong; Wang, Dong; Yang, Chong-Ren; Zhang, Ying-Jun

    2014-08-01

    Pu-er ripe tea is a special microbial post-fermented tea made from Pu-er raw tea, a kind of green tea produced from the leaves of Camellia sinensis var. assamica. It is one of the most consumed teas in the past two decades in China, due to its special flavor, taste, and beneficial effects. This work aimed to obtain diverse catechin structures from Pu-er ripe tea, which led to the isolation of four new phenylpropanoid-substituted flavan-3-ols, puerins C-F (1-4), together with four known flavan-3-ols, (+)-catechin (5), (-)-epicatechin (6), (+/-)-gallocatechin (7), and (-)-epigallocatechin (8). Their structures were elucidated on the basis of detailed spectroscopic analysis, including 1D and 2D NMR, mass and CD spectra. Compounds 1-4, which could be formed in the post-fermentative process of Pu-er tea, were isolated for the first time from tea and Theaceae plant. PMID:25233599

  19. Constituent migration model for fast reactor U-Pu-Zr metallic fuel

    International Nuclear Information System (INIS)

    The metallic fuel behavior of U-Pu-Zr has been actively investigated at Argonne National Laboratory. The Central Research Institute of the Electric Power Industry has been developing a metallic fuel liquid-metal fast breeder reactor concept jointly with several Japanese organizations. One of the development activities resulted in the fuel performance code SESAME. Recently, joint efforts have included the development of more mechanistic models for metallic fuel behavior. One of the models is for the constituent migration behavior in U-Pu-Zr fuels. For a simulation of constituent migration in the Experimental Breeder Reactor 2 (EBR-2) test pins ND30 and ND35, a quasi-binary U-Zr-(11.5 at.% Pu) phase diagram is produced using the U-Pu-Zr ternary phase diagram of O'Boyle and Dwight

  20. Surprising Coordination Geometry Differences in Ce(IV)- and Pu(IV)-Maltol Complexes

    Energy Technology Data Exchange (ETDEWEB)

    Lawrence Berkeley National Laboratory; Raymond, Kenneth; Szigethy, Geza; Xu, Jide; Gorden, Anne E.V.; Teat, Simon J.; Shuh, David K.; Raymond, Kenneth N.

    2008-02-12

    As part of a study to characterize the detailed coordination behavior of Pu(IV), single crystal X-ray diffraction structures have been determined for Pu(IV) and Ce(IV) complexes with the naturally-occurring ligand maltol (3-hydroxy-2-methyl-pyran-4-one) and its derivative bromomaltol (5-bromo-3-hydroxy-2-methyl-pyran-4-one). Although Ce(IV) is generally accepted as a structural analog for Pu(IV), and the maltol complexes of these two metals are isostructural, the corresponding bromomaltol complexes are strikingly different with respect to ligand orientation about the metal ion: All complexes exhibit trigonal dodecahedral coordination geometry but the Ce(IV)-bromomaltol complex displays an uncommon ligand arrangement not mirrored in the Pu(IV) complex, although the two metal species are generally accepted to be structural analogs.

  1. Pu`ukohola Heiau National Historic Site Vegetation Mapping Project - Spatial Vegetation Data

    Data.gov (United States)

    National Park Service, Department of the Interior — This metadata is for the vegetation and land-use geo-spatial database for Pu'ukohola Heiau National Historic Site (PUHE) , Island of Hawai'i and surrounding areas....

  2. Stabilization of Pu and Np valences in Purex process: problems and outlook

    International Nuclear Information System (INIS)

    One of the trends for improving the Purex-process involves the development of new methods of Pu and Np valence regulation. The application of salt-free chemical reagents of the organic nature that simultaneously have the properties of reductants and stabilizers-anti-nitrites will allow the mutual U, Pu and Np separation processes to be implemented in a more flexible way, a reduction in the amount of non-vaporizable compounds in liquid waste and an improvement of the safety level of the SNF reprocessing process. The electrochemical method commercially used in the operation of the U and Pu separation at the RT-1 plant (Russia) is an actual alternative to the traditional chemical methods of Pu and Np reduction and oxidation in the Purex-process. (author)

  3. Thermophysical properties of α-Pu2O3: A new potential model

    Science.gov (United States)

    Günay, S. D.; Akgenç, B.; Akdere, Ü.; Taşseven, ć.

    2013-12-01

    α-Pu2O3 is an important material among plutonium based materials in nuclear industry. Pure plutonium surfaces quickly oxidizes into α-Pu2O3 and PuO2 which are in the form of layers one on another [1]. Here we have investigated thermal properties of α-Pu2O3 by molecular dynamics simulation by using a partially ionic semi-empirical rigid ion potential. Mechanical properties, thermal expansion, and heat capacity are calculated. Results were compared with available experimental data and quantum calculation [2]. Due to the experimental limitations such as toxicity and radiation effects, studying the physical properties of such materials from molecular dynamics simulations have vital importance.

  4. Toxicity of 239PuO2 inhaled by aged Beagle dogs. X

    International Nuclear Information System (INIS)

    The influence of age at exposure on the metabolism, dosimetry, and biological effects of inhaled 239PuO2 particles is being studied in aged Beagle dogs (8.0-10.5 yr of age at exposure). Forty-eight dogs inhaled 239PuO2 particles with an activity median aerodynamic diameter of 1.5 mm to achieve graded levels of initial pulmonary burdens (IPB) ranging from 0.02-0.66 μCi 239Pu/kg body weight (0.75-24 kBq/kg). Twelve other dogs were exposed to the aerosol diluent only. All forty-eight exposed dogs have died, including two in the past year. The twelve control dogs have also died, including one in the past year. Radiation pneumonitis and pulmonary fibrosis have been the primary causes of death in these aged dogs exposed to 239PuO2. (author)

  5. Malignancy of transplanted hamster lung lesions induced by inhaled 239PuO2

    International Nuclear Information System (INIS)

    Selected sites from the lungs of hamsters that had inhaled 239PuO2 aerosol were serially transplanted into the cheek pouches of recipient hamsters. Up to 13 mo postexposure, no evidence of malignancy has appeared

  6. DFT and two-dimensional correlation analysis methods for evaluating the Pu{sup 3+}–Pu{sup 4+} electronic transition of plutonium-doped zircon

    Energy Technology Data Exchange (ETDEWEB)

    Bian, Liang, E-mail: bianliang@ms.xjb.ac.cn [Key Laboratory of Functional Materials and Devices for Special Environments, Chinese Academy of Sciences, Urumqi 830011, Xinjiang (China); Laboratory for Extreme Conditions Matter Properties, South West University of Science and Technology, Mianyang 621010, Sichuan (China); Dong, Fa-qin; Song, Mian-xin [Laboratory for Extreme Conditions Matter Properties, South West University of Science and Technology, Mianyang 621010, Sichuan (China); Dong, Hai-liang [Department of Geology and Environmental Earth Science, Miami University, Oxford, OH 45056 (United States); Li, Wei-Min [Key Laboratory of Functional Materials and Devices for Special Environments, Chinese Academy of Sciences, Urumqi 830011, Xinjiang (China); Duan, Tao; Xu, Jin-bao [Laboratory for Extreme Conditions Matter Properties, South West University of Science and Technology, Mianyang 621010, Sichuan (China); Zhang, Xiao-yan [Key Laboratory of Functional Materials and Devices for Special Environments, Chinese Academy of Sciences, Urumqi 830011, Xinjiang (China); Laboratory for Extreme Conditions Matter Properties, South West University of Science and Technology, Mianyang 621010, Sichuan (China)

    2015-08-30

    Highlights: • Effect of Pu f-shell electron on the electronic property of zircon is calculated via DFT and 2D-CA techniques. • Reasons of Pu f-shell electron influencing on electronic properties are systematically discussed. • Phase transitions are found at two point 2.8 mol% and 7.5 mol%. - Abstract: Understanding how plutonium (Pu) doping affects the crystalline zircon structure is very important for risk management. However, so far, there have been only a very limited number of reports of the quantitative simulation of the effects of the Pu charge and concentration on the phase transition. In this study, we used density functional theory (DFT), virtual crystal approximation (VCA), and two-dimensional correlation analysis (2D-CA) techniques to calculate the origins of the structural and electronic transitions of Zr{sub 1−c}Pu{sub c}SiO{sub 4} over a wide range of Pu doping concentrations (c = 0–10 mol%). The calculations indicated that the low-angular-momentum Pu-f{sub xy}-shell electron excites an inner-shell O-2s{sup 2} orbital to create an oxygen defect (V{sub O-s}) below c = 2.8 mol%. This oxygen defect then captures a low-angular-momentum Zr-5p{sup 6}5s{sup 2} electron to form an sp hybrid orbital, which exhibits a stable phase structure. When c > 2.8 mol%, each accumulated V{sub O-p} defect captures a high-angular-momentum Zr-4d{sub z} electron and two Si-p{sub z} electrons to create delocalized Si{sup 4+} → Si{sup 2+} charge disproportionation. Therefore, we suggest that the optimal amount of Pu cannot exceed 7.5 mol% because of the formation of a mixture of ZrO{sub 8} polyhedral and SiO{sub 4} tetrahedral phases with the orientation (10-1). This study offers new perspective on the development of highly stable zircon-based solid solution materials.

  7. Role of PU.1 in MHC Class II Expression via CIITA Transcription in Plasmacytoid Dendritic Cells

    Science.gov (United States)

    Miura, Ryosuke; Kasakura, Kazumi; Nakano, Nobuhiro; Hara, Mutsuko; Maeda, Keiko; Okumura, Ko; Ogawa, Hideoki; Yashiro, Takuya; Nishiyama, Chiharu

    2016-01-01

    The cofactor CIITA is a master regulator of MHC class II expression and several transcription factors regulating the cell type-specific expression of CIITA have been identified. Although the MHC class II expression in plasmacytoid dendritic cells (pDCs) is also mediated by CIITA, the transcription factors involved in the CIITA expression in pDCs are largely unknown. In the present study, we analyzed the role of a hematopoietic lineage-specific transcription factor, PU.1, in CIITA transcription in pDCs. The introduction of PU.1 siRNA into mouse pDCs and a human pDC cell line, CAL-1, reduced the mRNA levels of MHC class II and CIITA. When the binding of PU.1 to the 3rd promoter of CIITA (pIII) in CAL-1 and mouse pDCs was analyzed by a chromatin immunoprecipitation assay, a significant amount of PU.1 binding to the pIII was detected, which was definitely decreased in PU.1 siRNA-transfected cells. Reporter assays showed that PU.1 knockdown reduced the pIII promoter activity and that three Ets-motifs in the human pIII promoter were candidates of cis-enhancing elements. By electrophoretic mobility shift assays, it was confirmed that two Ets-motifs, GGAA (-181/-178) and AGAA (-114/-111), among three candidates, were directly bound with PU.1. When mouse pDCs and CAL-1 cells were stimulated by GM-CSF, mRNA levels of PU.1, pIII-driven CIITA, total CIITA, MHC class II, and the amount of PU.1 binding to pIII were significantly increased. The GM-CSF-mediated up-regulation of these mRNAs was canceled in PU.1 siRNA-introduced cells. Taking these results together, we conclude that PU.1 transactivates the pIII through direct binding to Ets-motifs in the promoter in pDCs. PMID:27105023

  8. Distribution coefficients for the sorption of Th, U, Np, Pu, and Am on Opalinus Clay

    Energy Technology Data Exchange (ETDEWEB)

    Amayri, Samer; Froehlich, Daniel R.; Kaplan, Ugras; Trautmann, Norbert; Reich, Tobias [Mainz Univ. (Germany). Inst. of Nuclear Chemistry

    2016-04-01

    The distribution coefficients (K{sub d}) are determined for the sorption of Th(IV), U(VI), Np(V), Pu(III/IV/VI), and Am(III) in the system natural Opalinus Clay (OPA) from Mont Terri, Switzerland, and synthetic OPA pore water at pH 7.6 as a function of solid-to-liquid ratio and element concentration. A linear sorption behavior under the chosen experimental conditions was obtained. The K{sub d} values strongly depend on the oxidation state of the actinide. The K{sub d} values for the tri- and tetravalent actinides are in the range of 29-159 m{sup 3}/kg. U and Np in the oxidation states six and five, respectively, are weakly sorbed on OPA with K{sub d} values of 0.04-0.05 m{sup 3}/kg. The K{sub d} values for the redox-stable Am(III) and Th(IV) are in the same range as for Pu(III) and Pu(IV) which are redox sensitive. The K{sub d} value of Pu(VI) (13 ± 3 m{sup 3}/kg) is about one order of magnitude lower than the K{sub d} values of Pu(III) and Pu(IV), but still more than two orders of magnitude higher compared to the values obtained for U(VI) and Np(V). This discrepancy is attributed to the partial reduction of Pu(VI) to Pu(IV) during sorption.

  9. Determination of fissile fraction in MOX (mixed U + Pu oxides) fuels for different burnup values

    Energy Technology Data Exchange (ETDEWEB)

    Ozdemir, Levent, E-mail: levent.ozdemir@taek.gov.tr [Department of Nuclear Engineering, Hacettepe University, 06800 Beytepe, Ankara (Turkey); Acar, Banu Bulut; Zabunoglu, Okan H. [Department of Nuclear Engineering, Hacettepe University, 06800 Beytepe, Ankara (Turkey)

    2011-02-15

    When spent Light Water Reactor fuels are processed by the standard Purex method of reprocessing, plutonium (Pu) and uranium (U) in spent fuel are obtained as pure and separate streams. The recovered Pu has a fissile content (consisting of {sup 239}Pu and {sup 241}Pu) greater than 60% typically (although it mainly depends on discharge burnup of spent fuel). The recovered Pu can be recycled as mixed-oxide (MOX) fuel after being blended with a fertile U makeup in a MOX fabrication plant. The burnup that can be obtained from MOX fuel depends on: (1) isotopic composition of Pu, which is closely related to the discharge burnup of spent fuel from which Pu is recovered; (2) the type of fertile U makeup material used (depleted U, natural U, or recovered U); and (3) fraction of makeup material in the mix (blending ratio), which in turn determines the total fissile fraction of MOX. Using the Non-linear Reactivity Model and the code MONTEBURNS, a step-by-step procedure for computing the total fissile content of MOX is introduced. As was intended, the resulting expression is simple enough for quick/hand calculations of total fissile content of MOX required to reach a desired burnup for a given discharge burnup of spent fuel and for a specified fertile U makeup. In any case, due to non-fissile (parasitic) content of recovered Pu, a greater fissile fraction in MOX than that in fresh U is required to obtain the same burnup as can be obtained by the fresh U fuel.

  10. Ecological studies of small vertebrates in Pu-contaminated study areas of NTS and TTR

    International Nuclear Information System (INIS)

    Ecological studies of vertebrates in plutonium-contaminated areas of the Nevada Test Site (NTS) were initiated in March 1972, and have continued to date. In September 1973, standard census methods were also employed to derive a qualitative and quantitative inventory of vertebrate biota of four Nevada Applied Ecology Group (NAEG) study areas of the Tonopah Test Range (TTR). A checklist of vertebrates of NAEG study areas of NTS and TTR is presented. Data are presented on vertebrate composition, relative abundance, and seasonal status in the study areas. Concentrations of 239Pu and 241Am were determined in pelt or skin, GI tract, and carcass of 13 lizards and 16 mammals resident on Clean Slate 2, TTR, and Area 11, NTS. A total of 71 animals were collected for radioanalysis. However, the data were not available at the time this report was written. Pu tissue burdens were highest in lizards from Area 11 GZ. Maximum values obtained in nCi/g ash were 30.9, 42.2, and 0.43 for the pelt, GI tract, and carcass, respectively. Maximum 239Pu values in tissues of small rodents from Area 11 (not from GZ) were 11.4, 6.49, and 0.20 nCi/g ash for pelt, GI tract, and carcass, respectively. Pu/Am ratios were relatively consistent in tissue samples of lizards and small mammals from Area 11 (approximately 6:1, Pu/Am). Pu/Am ratios were not consistent in vertebrates of Clean Slate 2, TTR, and appeared to be lower in carcass (28:1, Pu/Am in mammals) than GI tract (9:1, Pu/Am in mammals). Although this trend was more conspicuous in mammals, it was also evident in reptiles. (auth)

  11. Fully automated system for Pu measurement by gamma spectrometry of alpha contaminated solid wastes

    International Nuclear Information System (INIS)

    A description is given of a fully automated system developed at Comb/Mepis Laboratories which is based on the detection of specific gamma signatures of Pu isotopes for monitoring Pu content in 15-25 l containers of low density (0.1 g/cm3) wastes. The methodological approach is discussed; based on experimental data, an evaluation of the achievable performances (detection limit, precision, accuracy, etc.) is also given

  12. Mass transport properties of Pu/DT mixtures from orbital free molecular dynamics simulations

    Energy Technology Data Exchange (ETDEWEB)

    Kress, Joel David [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Ticknor, Christopher [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Collins, Lee A. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2015-09-16

    Mass transport properties (shear viscosity and diffusion coefficients) for Pu/DT mixtures were calculated with Orbital Free Molecular Dynamics (OFMD). The results were fitted to simple functions of mass density (for ρ=10.4 to 62.4 g/cm3) and temperature (for T=100 up to 3,000 eV) for Pu/DT mixtures consisting of 100/0, 25/75, 50/50, and 75/25 by number.

  13. Transcriptional Factor PU.1 Regulates Decidual C1q Expression in Early Pregnancy in Human.

    Science.gov (United States)

    Madhukaran, Shanmuga Priyaa; Kishore, Uday; Jamil, Kaiser; Teo, Boon Heng Dennis; Choolani, Mahesh; Lu, Jinhua

    2015-01-01

    C1q is the first recognition subcomponent of the complement classical pathway, which in addition to being synthesized in the liver, is also expressed by macrophages and dendritic cells (DCs). Trophoblast invasion during early placentation results in accumulation of debris that triggers the complement system. Hence, both early and late components of the classical pathway are widely distributed in the placenta and decidua. In addition, C1q has recently been shown to significantly contribute to feto-maternal tolerance, trophoblast migration, and spiral artery remodeling, although the exact mechanism remains unknown. Pregnancy in mice, genetically deficient in C1q, mirrors symptoms similar to that of human preeclampsia. Thus, regulated complement activation has been proposed as an essential requirement for normal successful pregnancy. Little is known about the molecular pathways that regulate C1q expression in pregnancy. PU.1, an Ets-family transcription factor, is required for the development of hematopoietic myeloid lineage immune cells, and its expression is tissue-specific. Recently, PU.1 has been shown to regulate C1q gene expression in DCs and macrophages. Here, we have examined if PU.1 transcription factor regulates decidual C1q expression. We used immune-histochemical analysis, PCR, and immunostaining to localize and study the gene expression of PU.1 transcription factor in early human decidua. PU.1 was highly expressed at gene and protein level in early human decidual cells including trophoblast and stromal cells. Surprisingly, nuclear as well as cytoplasmic PU.1 expression was observed. Decidual cells with predominantly nuclear PU.1 expression had higher C1q expression. It is likely that nuclear and cytoplasmic PU.1 localization has a role to play in early pregnancy via regulating C1q expression in the decidua during implantation. PMID:25762996

  14. Kinetics of the oxidation of Pu(IV) by manganese dioxide

    International Nuclear Information System (INIS)

    The kinetics of the oxidation of plutonium(IV) by manganese dioxide were studied in 1.0 M NaCl over the pH range from 2.5 to 8.2 with variable concentrations of manganese dioxide from 0.01 m2/L to 4.97 m2/L at a constant temperature of 19±2 C. The concentration of plutonium in solution was 6.0(±1.0) x 10-10 M. Fractions of Pu(IV), (V) and (VI) as a function of time were determined by removal of plutonium from the solid phase followed by an ultrafiltration/solvent extraction procedure using TTA and HDEHP as extractants. Appropriate removal conditions were established for Pu(IV), Pu(V) and Pu(VI) using Th(IV), Np(V) and U(VI) as oxidation state analogs. In the pH range from 2.0 to 3.5, the oxidation of Pu(IV) by manganese dioxide was first order with respect to the concentration of manganese dioxide and -0.21 with respect to the hydrogen ion concentration. Consequently, assuming a first order dependence with respect to the concentration of Pu(IV), the oxidation reaction can be described by the following rate equation: -d[Pu(IV)]/dt = k . [Pu(IV)] . [MnO2(s)] . [H+]-0.21 with k = 3.72(±0.13) x 10-3 (m-2 L)(mol-1 L)-0.21(min)-1. Using the kinetic data determined in this study, the influence of manganese dioxide on the oxidation state distribution of plutonium under various environmental conditions as well as in waste solutions can be estimated. (orig.)

  15. Migration of 90Sr, 137Cs and Pu in soils. Verification of a computer model on the behaviour of these radiocontaminants in soils of Western Europe

    International Nuclear Information System (INIS)

    The main emphasis in 1979 was on the 239240Pu model for simulating translocations in soil. The verification was hampered because data for 239Pu were available from only two locations. A comparison between the observed and predicted Pu distribution however indicated the possibility of using the available simulation approach for 239240Pu. (Auth.)

  16. Electrode reaction of Pu3+/Pu couple in LiCl-KCl eutectic melts: comparison of the electrode reaction at the surface of liquid Bi with that at a solid Mo electrode

    International Nuclear Information System (INIS)

    The electrode reaction of Pu3+/Pu couple at the interface between LiCl-KCl eutectic melt containing PuCl3 and liquid Bi phase was investigated by cyclic voltammetry at 723, 773 and 823 K. For comparison, the system was also studied using a solid Mo electrode in place of the liquid Bi electrode. It was found that the electrode reaction of Pu3+/Pu couple at the Bi electrode was almost reversible. The redox potentials of Pu3+/Pu couple at the liquid Bi electrode in the LiCl-KCl eutectic melt containing 0.87 wt% PuCl3 (0.0014 mole fraction) at 723, 773 and 823 K were observed to be more positive by 0.575, 0.572 and 0.566 V, respectively, than those at the Mo electrode. These differences in potential were thermodynamically analyzed by assuming a lowering of the activity of Pu in Bi phase according to the alloy formation of PuBi2. (author)

  17. Many-body Expanded Analytical Potential Energy Function for Ground State PuOH Molecule

    Institute of Scientific and Technical Information of China (English)

    LI Yue-Xun; GAO Tao; ZHU Zheng-He

    2006-01-01

    Using the density functional method B3LYP with relativistic effective core potential (RECP) for Pu atom, the low-lying excited states (4∑+, 6∑+, 8∑+) for three structures of PuOH molecule were optimized. The results show that the ground state is X6∑+of the linear Pu-O-H (C∞v), its corresponding equilibrium geometry and dissociation energy are RPu-O=0.20595 nm, RO-H=0.09581 nm and -8.68 eV, respectively. At the same time, two other metastable structures [PuOH (Cs) and H-Pu-O (C∞v)] were found. The analytical potential energy function has also been derived for whole range using the many-body expansion method. This potential energy function represents the considerable topographical features of PuOH molecule in detail, which is adequately accurate in the whole potential surface and can be used for the molecular reaction dynamics research.

  18. Absolute measurement of the 242Pu neutron-capture cross section

    Science.gov (United States)

    Buckner, M. Q.; Wu, C. Y.; Henderson, R. A.; Bucher, B.; Chyzh, A.; Bredeweg, T. A.; Baramsai, B.; Couture, A.; Jandel, M.; Mosby, S.; O'Donnell, J. M.; Ullmann, J. L.; Dance Collaboration

    2016-04-01

    The absolute neutron-capture cross section of 242Pu was measured at the Los Alamos Neutron Science Center using the Detector for Advanced Neutron-Capture Experiments array along with a compact parallel-plate avalanche counter for fission-fragment detection. The first direct measurement of the 242Pu(n ,γ ) cross section was made over the incident neutron energy range from thermal to ≈6 keV, and the absolute scale of the (n ,γ ) cross section was set according to the known 239Pu(n ,f ) resonance at En ,R=7.83 eV. This was accomplished by adding a small quantity of 239Pu to the 242Pu sample. The relative scale of the cross section, with a range of four orders of magnitude, was determined for incident neutron energies from thermal to ≈40 keV. Our data, in general, are in agreement with previous measurements and those reported in ENDF/B-VII.1; the 242Pu(n ,γ ) cross section at the En ,R=2.68 eV resonance is within 2.4 % of the evaluated value. However, discrepancies exist at higher energies; our data are ≈30 % lower than the evaluated data at En≈1 keV and are approximately 2 σ away from the previous measurement at En≈20 keV.

  19. Polyurethane (PU) scaffolds prepared by solvent casting/particulate leaching (SCPL) combined with centrifugation

    International Nuclear Information System (INIS)

    This article reports an enhanced solvent casting/particulate (salt) leaching (SCPL) method developed for preparing three-dimensional porous polyurethane (PU) scaffolds for cardiac tissue engineering. The solvent for the preparation of the PU scaffolds was a mixture of dimethylformamide (DFM) and tetrahydrofuran (THF). The enhanced method involved the combination of a conventional SCPL method and a step of centrifugation, with the centrifugation being employed to improve the pore uniformity and the pore interconnectivity of scaffolds. Highly porous three-dimensional scaffolds with a well interconnected porous structure could be achieved at the polymer solution concentration of up to 20% by air or vacuum drying to remove the solvent. When the salt particle sizes of 212-295, 295-425, or 425-531 μm and a 15% w/v polymer solution concentration were used, the porosity of the scaffolds was between 83-92% and the compression moduli of the scaffolds were between 13 kPa and 28 kPa. Type I collagen acidic solution was introduced into the pores of a PU scaffold to coat the collagen onto the pore walls throughout the whole PU scaffold. The human aortic endothelial cells (HAECs) cultured in the collagen-coated PU scaffold for 2 weeks were observed by scanning electron microscopy (SEM). It was shown that the enhanced SCPL method and the collagen coating resulted in a spatially uniform distribution of cells throughout the collagen-coated PU scaffold.

  20. Characterization and testing of a 238Pu loaded ceramic waste form

    International Nuclear Information System (INIS)

    This paper will describe the preparation and progress of the effort at Argonne National Laboratory-West to produce ceramic waste forms loaded with 238Pu. The purpose of this study is to determine the extent of damage, if any, that alpha decay events will play over time to the ceramic waste form under development at Argonne. The ceramic waste form is glass-bonded sodalite. The sodalite is utilized to encapsulate the fission products and transuranics which are present in a chloride salt matrix which results from a spent fuel conditioning process. 238Pu possesses approximately 250 times the specific activity of 239Pu and thus allows for a much shorter time frame to address the issue. In preparation for production of 238Pu loaded waste forms 239Pu loaded samples were produced. Data is presented for samples produced with typical reactor grade plutonium. X-ray diffraction, scanning electron micrographs and durability test results will be presented. The ramifications for the production of the 238Pu loaded samples will be discussed

  1. Background distributions of 239+240Pu and 137Cs of upland soil in Rokkasho, Japan

    International Nuclear Information System (INIS)

    The background distributions of Pu and 137Cs in soil were investigated in Rokkasho, Aomori Prefecture, where the first commercial nuclear fuel reprocessing plant in Japan is now being constructed. Soil core samples to 1 m depth were collected at 13 upland fields in Rokkasho and control sites in Hachinohe and Hirosaki. Since fields under yam (Dioscorea babatus) cultivation, which is a common crop in Rokkasho, were dug to approximately 1 m depth at harvesting, depth profiles of fallout radionuclides are heavily disturbed for most fields in Rokkasho. The mean inventories of 239+240Pu and 137Cs in three fields with no yam cultivation history were 116 Bq m-2 and 3.4 kBq m-2, respectively and similar to values in Hachinohe. However, the inventories were approximately a half of those in Hirosaki. The mean ratio of 239Pu/240Pu for all studied fields was 0.18±0.04, and similar to that of global fallout. The Pu concentrations correlate very well with 137Cs (r=0.97) in spite of heavy disturbance of soil, and the ratio of 239+240Pu/137Cs was 0.037±0.007, which is a typical value for global fallout. (author)

  2. Contribution to the study of the (U,Pu)C,N system

    International Nuclear Information System (INIS)

    The reactions of UC, PuC, (U,Pu)C, UC2 and U(C1-xOx) with nitrogen at moderate temperatures (room temperature to 400 C) are described. The influence of the uptake of nitrogen by the powders necessary to sinter the carbides upon the nature of the final product has been investigated; it has been shown that the sintered carbides are hyper-stoichiometric. The reactions of carbon with UN, PuN and (U,Pu)N has also been studied. Under vacuum, carbon reacts on the nitrides at temperatures as low as 1100 C; nitrogen is replaced by carbon and the final product is a carbonitride. The reaction is: MN + x C → MN1-xCx + x/2N2. The reaction is limited and the carbonitrides have a fixed composition in presence of M2C3 or MC2; hence it is impossible to produce pure MC using the reaction. The ternary diagram U-C-N, Pu-C-N and (U,Pu)C-N have been drawn. They show clearly that it is possible to obtain single phase carbonitrides in a wide domain of compositions. (author)

  3. Structural characteristics and properties of PU-modified TDE-85/MeTHPA epoxy resin

    Institute of Scientific and Technical Information of China (English)

    2007-01-01

    Diglycidy1-4,5-epoxycyclohexane-1,2-dicarboxylate (TDE-85)/methyl tetrahydro-phthalic anhydride (MeTHPA) epoxy resin was modified by polyurethane(PU), and its structural characteristics and properties were studied by infrared spectrum analysis(IR), scanning electronic microscopy (SEM), mechanics testing and thermogravimetric analysis (TG). The results indicate that epoxy polymeric network Ⅰ and polyurethane polymeric network Ⅱ are formed in the PU-modified TDE-85/MeTHPA epoxy resin.Meanwhile the PU-modified TDE-85/MeTHPA resins have heterogeneous structure. The miscibility between epoxy (EP) and polyurethane (PU) as well as the phase size are dominantly determined by the mass fraction of polyurethane prepolymer (PUP) in the EP/PU blends. With the increase of PUP mass fraction, the tensile strength, impact strength and thermal stability of the PU-modified TDE-85/MeTHPA epoxy resin all firstly exhibit increasing tendency, and decrease after successively reaching their maxima. When the number-average molecular mass of PPG is 1 000 and the mass fraction of PUP is 15%, the tensile strength, impact strength and thermal stability of materials obtained, compared with TDE-85/MeTHPA epoxy resin, are improved obviously.

  4. A mass spectrometric investigation of the vaporisation behaviour in the (U + Pu + O) system

    International Nuclear Information System (INIS)

    Highlights: • Vapour pressure measurements performed at high temperatures on (U, Pu) oxide samples. • Experimental facility consisted of a Knudsen cell coupled with a mass spectrometer. • Partial pressures of gaseous species were assessed from ionisation efficiency curves. • Vapour pressure was calculated using a thermochemical model for the ternary system. -- Abstract: The vaporisation behaviour of (U, Pu)O2 mixed oxides (Pu/M = 0.25, 0.50 and 0.75, with M = U + Pu) was studied by means of mass spectrometry. Hyperstoichiometric samples were heated in a Knudsen cell up to T = 2300 K. The evolution of the uranium and plutonium bearing gaseous species was studied as a function of time in order to evaluate the congruent vapour composition. Ionisation efficiency measurements were performed and the partial pressures of the gaseous species involved in the vaporisation process were determined. The vapour pressure has also been calculated using a thermochemical model for the (U + Pu + O) system. A quasi congruent composition with respect to the O/M ratio has been assumed, in agreement with the experiments. Nevertheless, the evaluation of all the experimental and calculated results shows that a total congruent composition exists for a single composition of the mixed oxide (MOX) samples with a Pu/M content slightly lower than 0.50. A good agreement is obtained between the calculated and experimental vapour pressure data, as well as the quasi congruent vaporisation compositions

  5. Determination of Pu isotopic composition and 241Am by high resolution gamma spectrometry on solid samples

    International Nuclear Information System (INIS)

    The present report gives a detailed account of the development of non-destructive assay technique using high resolution gamma-ray spectrometry (HRGS) for determination of plutonium (Pu) isotopic composition and the 241Am content in solid Pu samples. Energy range 120-420 keV was used in this study. The methodology involves in situ relative efficiency calibration during the measurement process itself, to reduce the errors and increase the reliability of the method. Twenty solid Pu samples of power reactor and research reactor grade were analyzed by this method and the results were compared with those obtained by thermal ionization mass spectrometry. The accuracy of the final results depends strongly upon the accuracy of the available nuclear data (decay constant, gamma abundance etc.). MATLAB based programme was written to perform the analysis. A counting time of 4 hour was chosen for achieving good statistics on the results for samples having 100-200 mg of Pu. The attainable accuracy is found to be 0.5-1% for the fissile isotopes (239Pu + 241Pu) and 5-10% for 241Am content. (author)

  6. Distribution of the Pu and Am isotopes in the BOMARC missile site soil

    International Nuclear Information System (INIS)

    Full text: The activity concentrations as well as the activity and atomic ratios of the Pu and Am isotopes in different sizes of the soil sampled around BOMARC Missile Site were obtained by radiochemical analysis. The association pattern between the actinides and soil particles was investigated using a spherical model of a particle size with a variable radius. From the activity and atomic ratios of Pu and Am, the origin of the Pu and Am isotopes was identified in the BOMARC Missile Site soil. Plutonium is one of the transuranic elements which is primarily present in the environment as a result of human activity, namely as the fallout from nuclear weapon testings during the late 1940s through to the early 1960s, and accidental releases due to military mishaps. One particular mishap occurred in 1960 at McGuire Air Force Base in New Jersey, when a Boeing Michigan Aeronautical Research Center (BOMARC) missile caught fire and the warhead was partially melted by the fire. Although the missile did not explode, subsequent fire fighting activities contributed to the dispersion of weapons grade plutonium into the local environment. Soil samples around BOMARC site were taken to a depth of 2 inches by the U.S. Air Force Institute for Environment. The soil samples were blended and homogenized in a soil tumbler, and subdivided into approximately 20-gram samples. Grain size fractions were determined with sieves. Determination of 239,240Pu, 238Pu, 241Pu, 241Am and 239U was performed using a radiochemical method. After adding 242Pu, 243Am and 232U tracers, a total of a 2 g ashed soil sample was dissolved with concentrated HNO3 and HF and evaporated to dryness. Dissolution in HNO3/HF was repeated and again evaporated to dryness. The residue was dissolved in 9 M HCl. After filtration, the solution was passed over an anion exchange column (chloride form) to which the Pu was sorbed. The columns were washed with 9 M HCl followed by 8 M HNO3. This effluent was evaporated to dryness and

  7. Distribution of Pu and Am isotopes in BOMARC missile site soil

    International Nuclear Information System (INIS)

    Full text: The activity concentrations as well as the activity and atomic ratios of the Pu and Am isotopes in different sizes of the soil sampled around BOMARC Missile Site were obtained by radiochemical analysis. The association pattern between the actinides and soil particles was investigated using a spherical model of a particle size with a variable radius. From the activity and atomic ratios of Pu and Am, the origin of the Pu and Am isotopes was identified in the BOMARC Missile Site soil. Plutonium is one of the transuranic elements which is primarily present in the environment as a result of human activity, namely as the fallout from nuclear weapon testings during the late 1940s through to the early 1960s, and accidental releases due to military mishaps. One particular mishap occurred in 1960 at McGuire Air Force Base in New Jersey, when a Boeing Michigan Aeronautical Research Center (BOMARC) missile caught fire and the warhead was partially melted by the fire. Although the missile did not explode, subsequent fire fighting activities contributed to the dispersion of weapons grade plutonium into the local environment. Soil samples around BOMARC site were taken to a depth of 2 inches by the U.S. Air Force Institute for Environment. The soil samples were blended and homogenized in a soil tumbler, and subdivided into approximately 20-gram samples. Grain size fractions were determined with sieves. Determination of 239,240Pu, 238Pu, 241Pu, 241Am and 238U was performed using a radiochemical method. After adding 242Pu, 243Am and 232U tracers, a total of a 2 g ashed soil sample was dissolved with concentrated HNO3 and HF and evaporated to dryness. Dissolution in HNO3/HF was repeated and again evaporated to dryness. The residue was dissolved in 9 M HCl. After filtration, the solution was passed over an anion exchange column (chloride form) to which the Pu was sorbed. The columns were washed with 9 M HCl followed by 8 M HNO3. This effluent was evaporated to dryness and

  8. Application of a canine 238Pu biokinetics/dosimetry model to human bioassay data.

    Science.gov (United States)

    Hickman, A W; Griffith, W C; Roessler, G S; Guilmette, R A

    1995-03-01

    Associated with the use of 238Pu in thermoelectric power sources for space probes is the potential for human exposure, primarily by inhalation and most likely as 238PuO2. Several models have been developed for assessing the level of intake and predicting the resulting radiation dose following human exposure to 239Pu. However, there are indications that existing models do not adequately describe the disposition and dosimetry of 238Pu following human exposure. In this study, a canine model that accounts for these differences has been adapted for use with human excretion data. The model is based on existing knowledge about organ retention of plutonium. An analysis of the sensitivity of the model to changes in aerosol-associated properties indicated that predictions of urinary excretion are most sensitive to changes in particle solubility and diameter and in the ratio of fragment:particle surface area. Application of the model to urinary excretion data from seven workers exposed to a 238Pu ceramic aerosol gave estimated intakes of 390-8,200 Bq and associated initial pulmonary burdens of 80-1,700 Bq. The resulting 50-y dose commitments to critical organs per Bq of 238Pu intake were estimated to be 0.5 mSv for the thoracic region, 0.2 mSv for the liver, and 1 mSv for the bone surfaces. PMID:7860307

  9. Quantitative molecular plating of large-area 242Pu targets with improved layer properties

    International Nuclear Information System (INIS)

    For measurements of the neutron-induced fission cross section of 242Pu, large-area (42 cm2) 242Pu targets were prepared on Ti-coated Si wafers by means of constant current density molecular plating. Radiochemical separations were performed prior to the platings. Quantitative deposition yields (>95%) were determined for all targets by means of alpha-particle spectroscopy. Layer densities in the range of 100–150 μg/cm2 were obtained. The homogeneity of the targets was studied by radiographic imaging. A comparative study between the quality of the layers produced on the Ti-coated Si wafers and the quality of layers grown on normal Ti foils was carried out by applying scanning electron microscopy and energy dispersive X-ray spectroscopy. Ti-coated Si wafers resulted clearly superior to Ti foils in the production of homogeneous 242Pu layers with minimum defectivity. - Highlights: • Large area (i.e., 42 cm2) 242Pu targets were prepared on Ti-coated Si wafers. • Quantitative deposition yields (>95%) were obtained. • Homogeneous 242Pu layers with minimum defectivity were produced. • The targets were prepared for future 242Pu(n, f) cross section measurements

  10. Measurement of the ${240}$Pu(n,f) reaction cross-section

    CERN Multimedia

    Following proposal CERN-INTC-2010-042 / INTC-P-280 (“Measurement of the fission cross-section of $^{240}$Pu and $^{242}$Pu at CERN’s n_TOF Facility”), the parallel measurement of the $^{240}$Pu(n,f) and $^{242}$Pu(n,f) reaction cross-sections was carried out at n_TOF EAR-1. While the $^{242}$Pu measurement was successful, unexpected sample-induced damage to the detectors caused by the high α-activity of the 240Pu samples resulted in a deterioration of the detector performance over the data taking period of several months, which compromised the measurement. This obstacle can be eliminated by performing the measurement in EAR-2, where the higher neutron flux will allow collecting data in a much shorter time, thus preventing the degradation of the detectors. In addition to this obvious advantage, the measurement would also benefit from the stronger suppression of the sample-induced α-background, due to the shorter times-of-flight involved.

  11. Radiolysis and corrosion of 238Pu-doped UO2 pellets in chloride brine

    Indian Academy of Sciences (India)

    M Kelm; E Bohnert

    2002-12-01

    Deaerated 5 M NaCl solution is irradiated in the presence of UO2 pellets with a-radiation from 238Pu. Experiments are conducted with 238Pu doped pellets and others with 238Pu dissolved in the brine. The radiolysis products and yields of mobilized U and Pu from the oxidative dissolution of UO2 are determined. Results found for radiolysis products and for the oxidation/dissolution of pellets immersed in Pu containing brine are similar to results for Pu doped pellets, where the radiation chemical processes occur only in the liquid layer of some 10 m thickness adjacent to the pellet. The yield of radiolysis products is comparable to earlier results, that of mobilized U from the pellets is < 1% of the total amount of oxidized species. Thus, the radiation chemical yield (-value) for mobilized hexavalent U is < 0.01 ions/100 eV. In spite of the low radiation yield for the corrosion, the rate of UO2 dissolution is higher than expected for the concentrations of long-lived oxidizing radiolysis compounds found in the solutions.

  12. PU/SS Eutectic Assessment In 9975 Packagings In A Storage Facility During Extended Fire

    International Nuclear Information System (INIS)

    In a radioactive material (RAM) packaging, the formation of eutectic at the Pu/SS (plutonium/stainless steel) interface is a serious concern and must be avoided to prevent of leakage of fissile material to the environment. The eutectic temperature for the Pu/SS is rather low (410 C) and could seriously impact the structural integrity of the containment vessel under accident conditions involving fire. The 9975 packaging is used for long term storage of Pu bearing materials in the DOE complex where the Pu comes in contact with the stainless steel containment vessel. Due to the serious consequences of the containment breach at the eutectic site, the Pu/SS interface temperature is kept well below the eutectic formation temperature of 410 C. This paper discusses the thermal models and the results for the extended fire conditions (1500 F for 86 minutes) that exist in a long term storage facility and concludes that the 9975 packaging Pu/SS interface temperature is well below the eutectic temperature.

  13. Measurement of Neutron Induced and Spontaneous Fission in Pu-242 at DANCE

    Science.gov (United States)

    Chyzh, Andrii; Wu, C. Y.; Henderson, R.; Couture, A.; Lee, H. Y.; Ullmann, J.; O'Donnell, J. M.; Jandel, M.; Haight, R. C.; Bredeweg, T. A.; Dance Collaboration

    2013-10-01

    Neutron capture and fission reactions are important in nuclear engineering and physics. DANCE (Detector for Advanced Neutron Capture Measurement, LANL) combined with PPAC (avalanche technique based fission tagging detector, LLNL) were used to study neutron induced and spontaneous fission in 242Pu. 2 measurements were performed in 2013. The first experiment was done without the incident neutron beam with the fission tagging ability to study γ-rays emitted in the spontaneous fission of 242Pu. The second one - with the neutron beam to measure both the neutron capture and fission reactions. This is the first direct measurement of prompt fission γ-rays in 242Pu. The γ-ray multiplicity, γ-ray energy, and total energy of γ-rays per fission in 242Pu will be presented. These distributions of the 242Pu spontaneous fission will be compared to those in the 241Pu neutron induced fission. This work was performed under the auspices of the US Department of Energy by Los Alamos National Laboratory under Contract DE-AC52-06NA25396 and Lawrence Livermore National Laboratory under Contract DE-AC52-07NA27344.

  14. Could weapon-grade plutonium be an asset for managing Pu inventories?

    International Nuclear Information System (INIS)

    Due to the temporary shortage of MOX fuel fabrication facilities, the stockpile of separated civilian grade Pu (CPu) is predicted to increase up to the turn of the century. An additional quantity of weapon grade Pu (WPu) will be progressively isolated at the same period. Both CPu and WPu surpluses require disposition as soon as feasible. Although non-proliferation concerns, established national policies, public acceptance problems and other considerations largely complicate the aspect of the use of WPu, it is worth examining the advantages which could result from a synergetic management of: LWR grade Pu to which AGR grade Pu might be associated; WPu; GCR grade Pu which should be considered as a Pu variety situated between the two first ones as far as their physical and neutronic characteristics are concerned. Two scenarios of integrated managements of the CPu varieties and WPu are being considered. They indicate several technical and economical advantages but also important problems to be resolved, mainly from the non-proliferation point of view. In that respect, it is concluded that, although no reasonable perspective exists to resolve these problems easily (or at all), the advantages justify an effort of the international community to consider how it could be implemented. (author). 24 refs, 2 figs, 5 tabs

  15. Even–odd effects in prompt emission of spontaneously fissioning even–even Pu isotopes

    Energy Technology Data Exchange (ETDEWEB)

    Tudora, A., E-mail: anabellatudora@hotmail.com [University of Bucharest, Faculty of Physics, Bucharest Magurele, POB MG-11, R-76900 (Romania); Hambsch, F.-J. [EC-JRC Institute for Reference Materials and Measurements (IRMM), Retieseweg 111, B-2440, Geel (Belgium); Giubega, G.; Visan, I. [University of Bucharest, Faculty of Physics, Bucharest Magurele, POB MG-11, R-76900 (Romania)

    2015-01-15

    The available experimental Y(A,TKE) data for {sup 236,238,240,242,244}Pu(SF) together with the Zp model prescription with appropriate parameters allows the investigation of even–odd effects in fragment distributions. The size of the global even–odd effect in Y(Z) is decreasing from {sup 244}Pu(SF) to {sup 236}Pu(SF) confirming the general observation of a decrease of the even–odd effect with the fissility parameter. Charge polarizations (ΔZ) and root-mean squares (rms) as a function of A of {sup 236–244}Pu(SF) were obtained for the first time. In the asymmetric fission region both ΔZ(A) and rms(A) exhibit oscillations with a periodicity of about 5 mass units due to the even–odd effects. The total average charge deviations 〈ΔZ〉 (obtained by averaging ΔZ(A) over the experimental Y(A) distribution) are of about |0.5| for all studied Pu(SF) systems. The comparison of the calculated ΔZ(A) and rms(A) of {sup 240}Pu(SF) with those of {sup 239}Pu(n{sub th},f) reported by Wahl shows an in-phase oscillation with a higher amplitude in the case of {sup 240}Pu(SF), confirming the higher even–odd effect in the case of SF. As in the previously studied cases ({sup 233,235}U(n{sub th},f), {sup 239}Pu(n{sub th},f), {sup 252}Cf(SF)) the even–odd effects in the prompt emission of {sup 236–244}Pu(SF) are mainly due to the Z even–odd effects in fragment distributions and charge polarizations and the N even–odd effects in the average neutron separation energies from fragments 〈Sn〉. The size of the global N even–odd effect in 〈Sn〉 is decreasing with the fissility parameter, being higher for the Pu(SF) systems compared to the previously studied systems. The prompt neutron multiplicities as a function of Z, ν(Z), exhibit sawtooth shapes with a visible staggering for asymmetric fragmentations. The size of the global Z even–odd effect in ν(Z) exhibits a decreasing trend with increasing fissility. The average prompt neutron multiplicities as a

  16. Pu isotopes in the western North Pacific Ocean before the accident at Fukushima Dai-ichi Nuclear Power Station

    Science.gov (United States)

    Yamada, M.; Zheng, J.; Aono, T.

    2011-12-01

    Anthropogenic radionuclides such as Pu-239 (half-life: 24100 yr), Pu-240 (half-life: 6560 yr) and Pu-241 (half-life: 14.325 yr) mainly have been released into the environment as the result of atmospheric nuclear weapons testing. In the North Pacific Ocean, two distinct sources of Pu isotopes can be identified; i.e., the global stratospheric fallout and close-in tropospheric fallout from nuclear weapons testing at the Pacific Proving Grounds in the Marshall Islands. The atom ratio of Pu-240/Pu-239 is a powerful fingerprint to identify the sources of Pu in the ocean. The Pu-240/Pu-239 atom ratios in seawater and marine sediment samples collected in the western North Pacific before the accident at Fukushima Dai-ichi Nuclear Power Station will provide useful background data for understanding the process controlling Pu transport and for distinguishing future Pu sources. The atom ratios of Pu-240/Pu-239 in water columns from the Yamato and Tsushima Basins in the Japan Sea were significantly higher than the mean global fallout ratio of 0.18; however, there were no temporal variation of atom ratios during the period from 1984 to 1993 in the Japan Sea. The total Pu-239+240 inventories in the whole water columns were approximately doubled during the period from 1984 to 1993 in the two basins. The atom ratio of Pu-240/Pu-239 in surface water from Sagami Bay, western North Pacific Ocean, was 0.224 and showed no notable variation from the surface to the bottom with the mean atom ratio being 0.234. The atom ratios for the Pacific coast, near the Rokkasho nuclear fuel reprocessing plant, were approximately the same as the 0.224 ratio obtained from Sagami Bay, western North Pacific margin. The atom ratios in the surficial sediments from Sagami Bay ranged from 0.229 to 0.247. The mean atom ratio in the sediment columns in the East China Sea ranged from 0.248 for the Changjiang estuary to 0.268 for the shelf edge. The observed atom ratios were significantly higher than the mean

  17. Polymeric Species of Pu in Low Ionic Strength Media

    Energy Technology Data Exchange (ETDEWEB)

    Romanovski, V V; Palmer, C E; Shaw, H F; Bourcier, W L; Jardine, L J

    2000-01-27

    The US Government has declared that approximately 50 tons of plutonium is surplus to US needs and should be set aside for eventual disposition. The US is currently following a dual path for the disposition of this plutonium: immobilization and irradiation of mixed-oxide fuel. Some fraction of this plutonium material that is undesirable for use in mixed-oxide fuel will be immobilized in a titanate ceramic and disposed of in a geologic repository for high level waste. The reminder of Pu will be fabricated into mixed-oxide fuel and irradiated in domestic light-water reactors. The resulting spent fuel would also be disposed of in a geologic repository for high level waste. The proposed US repository would be at the Yucca Mountain site in Nevada. Plutonium present in the disposal forms, either ceramics or spent fuel, must remain isolated from the biosphere over the geologic repository regulatory performance period, which is currently 10,000 years. Contamination of the biosphere could result from slow dissolution of the disposal forms followed by transport of the dissolution products into the biosphere by flowing ground water. Measurable amounts of apparently soluble plutonium can be released if plutonium dioxide is exposed to water under some conditions. Furthermore, recent studies in Nevada near the Yucca Mountain Site revealed that plutonium, associated with the colloidal fraction of the groundwater, was detected over a kilometer from its source within 30 years after it was placed underground for a nuclear weapons testing. It was not clear whether plutonium was transported as an intrinsic plutonium colloid or as plutonium sorbed onto colloidal clay or zeolite particles.

  18. DETERMINATION OF 237NP AND PU ISOTOPES IN LARGE SOIL SAMPLES BY INDUCTIVELY COUPLED PLASMA MASS SPECTROMETRY

    Energy Technology Data Exchange (ETDEWEB)

    Maxwell, S.

    2010-07-26

    A new method for the determination of {sup 237}Np and Pu isotopes in large soil samples has been developed that provides enhanced uranium removal to facilitate assay by inductively coupled plasma mass spectrometry (ICP-MS). This method allows rapid preconcentration and separation of plutonium and neptunium in large soil samples for the measurement of {sup 237}Np and Pu isotopes by ICP-MS. {sup 238}U can interfere with {sup 239}Pu measurement by ICP-MS as {sup 238}UH{sup +} mass overlap and {sup 237}Np via {sup 238}U peak tailing. The method provides enhanced removal of uranium by separating Pu and Np initially on TEVA Resin, then transferring Pu to DGA resin for additional purification. The decontamination factor for removal of uranium from plutonium for this method is greater than 1 x 10{sup 6}. Alpha spectrometry can also be applied so that the shorter-lived {sup 238}Pu isotope can be measured successfully. {sup 239}Pu, {sup 242}Pu and {sup 237}Np were measured by ICP-MS, while {sup 236}Pu and {sup 238}Pu were measured by alpha spectrometry.

  19. Measurement of Nagasaki Pu global transport rates, comparing with SO2 from historic volcanic eruptions

    International Nuclear Information System (INIS)

    An artificial single dose contaminant was released at Nagasaki, Japan on August 9, 1945, detonating plutonium (10-15 kg) atomic bomb. A portion, 1,2 kg of 239Pu was fissioned releasing 21 kt TNT energy along with various fission products. The rest of the unexpended fissile material, 239+240Pu, 13.8 kg (3.49 x 1013 Bq), was dispersed into the atmosphere along with a fission product, 137Cs, 23.4 g (7.44 x 1013 Bq). The fate of 239+240Pu and 137Cs was investigated by analysing both local and global fallout. The highest concentration of 239+240Pu was 64.5 mBq/g (181 mBq/cm2) while it was 188 mBq/g (526 mBq/cm2) for 137Cs both at 2.8 km east from the hypocentre. The total amount of deposition in the local fallout region of 264 km2 was 37.5 g (9.48 x 1010Bq) for 239+240Pu and 3.14 mg (5.88 x 1010Bq) for 137Cs. The ratio of the local fallout against the total amount of the radionuclides released was 0.27 % for 239+240Pu and 0.134% for 137Cs. Recent advancements in analytical technology made it possible for artificial radionuclides released from the Nagasaki explosion to be detected in the Arctic ice core layer of 1945. The 239+240Pu and the 137Cs, were measured by collecting 10 ice cores on the Agassiz ice cap, Ellesmere Island, Canada. The deposition was 0.16 μBq/cm2 for 239+240Pu and 20 μBq/cm2 for 137Cs. During the atmospheric testing, the deposition of 239+240Pu and 137Cs varied more than 100 times with the highest peaks of over 50 μBq/cm2 for 239+240Pu and over 800 μBq/cm2 for 137Cs both occurred in 1962. Analyzing Arctic data, there are many new information for long global transport, the history of nuclear weapons development etc. (author)

  20. Chemically selective polymer substrate based direct isotope dilution alpha spectrometry of Pu

    Energy Technology Data Exchange (ETDEWEB)

    Paul, Sumana, E-mail: sumana@barc.gov.in [Fuel Chemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India); Pandey, Ashok K. [Radiochemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India); Shah, R.V. [Fuel Chemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India); Aggarwal, S.K., E-mail: skaggr2002@gmail.com [Fuel Chemistry Division, Bhabha Atomic Research Centre, Trombay, Mumbai 400 085 (India)

    2015-06-09

    Highlights: • Membrane based alpha spectrometry was developed for plutonium. • A thin bifunctional layer was grafted on a porous membrane. • UV method used for grafting is simple and highly reproducible. • This method does not require preconcentration and source preparation steps. • Isotope dilution was used to enhance analytical performance. - Abstract: Quantification of actinides in the complex environmental, biological, process and waste streams samples requires multiple steps like selective preconcentration and matrix elimination, solid source preparations generally by evaporation or electrodeposition, and finally alpha spectrometry. To minimize the sample manipulation steps, a membrane based isotope dilution alpha spectrometry method was developed for the determination of plutonium concentrations in the complex aqueous solutions. The advantages of this method are that it is Pu(IV) selective at 3 M HNO{sub 3}, high preconcentration factor can be achieved, and obviates the need of solid source preparation. For this, a thin phosphate–sulfate bifunctional polymer layer was anchored on the surface of microporous poly(ethersulfone) membrane by UV induced surface grafting. The thickness of the bifunctional layer on one surface of the poly(ethersulfone) membrane was optimized. The thickness, physical and chemical structures of the bifunctional layer were studied by secondary ionization mass spectrometry (SIMS), scanning electron microscopy (SEM) and SEM–EDS (energy-dispersive spectroscopy). The optimized membrane was used for preconcentration of Pu(IV) from aqueous solutions having 3–4 M HNO{sub 3}, followed by direct quantification of the preconcentrated Pu(IV) by isotope dilution alpha spectrometry using {sup 238}Pu spike. The chemical recovery efficiency of Pu(IV) was found to be 86 ± 3% below Pu(IV) loading capacity (1.08 μg in 2 × 1 cm{sup 2}) of the membrane sample. The experiments with single representative actinides indicated that Am

  1. Disagregation of (U, Pu)O2 fuels in molten sodium nitrate and oxides system

    International Nuclear Information System (INIS)

    An oxidation process based on the use of an alkali-nitrate melt has been considered as a possible head end step for the reprocessing of FBR spent fuels. The total alkali solubility in the nitrate melt was examined. It is influenced by the temperature. At 500 degC the alkali solubility in the sodium nitrate melt is about 17 mol %. Examining solidified mixture of sodium and nitrate or sodium oxides and nitrite by X-ray diffraction has revealed five unknown lattices. NaNO3.xNa2O2 is cubic (a=8.71A), NaNO2.xNa2O2 is tetragonal (a=5.939A, c=9.997A), NaNO2.xNa2O is cubic (a=10.586A). The structure of NaNO3.xNa2O and NaNO3.xNaO2 could not be determined. The solubility of barium and ruthenium was briefly investigated. The reaction (U,Pu)O2 with the alkaline sodium nitrate melt proceeds along the grain boundaries of the solid solution. Two steps have been recognized. First (U,Pu)O2 is oxidized to (U,Pu)Osub(2+x) and in a subsequent step (U,Pu)Osub(2+x) reacts with sodium peroxide to form (U,Pu)2O5.xNa2O2. Disaggregation efficiency is a function of temperature, alkali concentration and physical properties of the pellets. High temperature and low alkali concentration lead to high efficiency. The structure of the reaction products (U,Pu)O2 with alkaline NaNO3 melt was shown to depend mainly on the alkali concentration. As the alkali concentration is lower than 2 mole % (U,Pu)2O5. Na2O2 is the dominate phase. (U,Pu)2O5.3Na2O2 corresponds to 6 mole % and over 11 mole % alkali, (U,Pu)2O5.xNa2O2 becomes the main product. The solubility of the fuel (U,Pu) in the alkali sodium nitrate melt increases with the alkali concentration up to 6000-8000 ppm for uranium and 1200-1700 ppm for plutonium at 500 degC with only 5 mole % alkali. As a result of high losses of fissile material in the salt bath molten salt process must regarded as uneligible for a general head end step in fuel reprocessing. Nevertheless its application can still be considered for treatment of insoluble fraction of

  2. Chemically selective polymer substrate based direct isotope dilution alpha spectrometry of Pu

    International Nuclear Information System (INIS)

    Highlights: • Membrane based alpha spectrometry was developed for plutonium. • A thin bifunctional layer was grafted on a porous membrane. • UV method used for grafting is simple and highly reproducible. • This method does not require preconcentration and source preparation steps. • Isotope dilution was used to enhance analytical performance. - Abstract: Quantification of actinides in the complex environmental, biological, process and waste streams samples requires multiple steps like selective preconcentration and matrix elimination, solid source preparations generally by evaporation or electrodeposition, and finally alpha spectrometry. To minimize the sample manipulation steps, a membrane based isotope dilution alpha spectrometry method was developed for the determination of plutonium concentrations in the complex aqueous solutions. The advantages of this method are that it is Pu(IV) selective at 3 M HNO3, high preconcentration factor can be achieved, and obviates the need of solid source preparation. For this, a thin phosphate–sulfate bifunctional polymer layer was anchored on the surface of microporous poly(ethersulfone) membrane by UV induced surface grafting. The thickness of the bifunctional layer on one surface of the poly(ethersulfone) membrane was optimized. The thickness, physical and chemical structures of the bifunctional layer were studied by secondary ionization mass spectrometry (SIMS), scanning electron microscopy (SEM) and SEM–EDS (energy-dispersive spectroscopy). The optimized membrane was used for preconcentration of Pu(IV) from aqueous solutions having 3–4 M HNO3, followed by direct quantification of the preconcentrated Pu(IV) by isotope dilution alpha spectrometry using 238Pu spike. The chemical recovery efficiency of Pu(IV) was found to be 86 ± 3% below Pu(IV) loading capacity (1.08 μg in 2 × 1 cm2) of the membrane sample. The experiments with single representative actinides indicated that Am(III) did not sorb to

  3. Determination of Pu and total alpha activity in spent TBP/kerosene

    International Nuclear Information System (INIS)

    Determination of the activity of total Pu and total a in the spent TBP/kerosene is essential to the research on spent TBP/kerosene treatment and disposal of industrialization. Accordingly, a reliable procedure for determining of the activities of total Pu and alpha in spent TBP/kerosene was developed. It is well known that the large area grid ionization chamber alpha spectrometry is a suitable technique to determine the trace-level alpha emitters such as 238U, 237Np, 239+240Pu, 238Pu and 241Am present in samples. However, the spent TBP/kerosene sample cannot be prepared for the source because of the diffusion when it is heated. So the digestion of the spent TBP/ kerosene is needed in this work. Before the digestion, the kerosene in the sample was distilled out for pre-concentration because of the low-level alpha-emitters, which also conduce to the digestion of the sample. After the distillation, the residual TBP was digested with HNO3 and HClO4. For the determination of the total Pu, ion-exchange chromatography was used for chemical separation of Pu, and then the large area grid ionization chamber alpha spectrometry was used for the measurement. The RSD of the Pu measurement was less than 2%. Two recovery experiments were undergone for the test of effect of the ion-exchange separation, and the results of recovery rate was 97.9% and 102%. The spent TBP/kerosene sample was digested with HNO3. After the digestion, the source was prepared for the total alpha-activity measurement. The result of this measurement was not satisfied because the sample cannot be digested entirely with HNO3, some alpha particles were shielded for detection because of self-absorption. However the alpha particle spectrum taken indicated that the percentages of the activities of alpha-emitters were similar in every measurement because of the similar shielding. So the total activities of alpha-emitters were corrected by a factor, which was the ratio of the accurate 239+240Pu activity measured

  4. Recovery of 238PuO2 by Molten Salt Oxidation Processing of 238PuO2 Contaminated Combustibles (Part II)

    International Nuclear Information System (INIS)

    Pu-238 heat sources are used to fuel radioisotope thermoelectric generators (RTG) used in space missions. The demand for this fuel is increasing, yet there are currently no domestic sources of this material. Much of the fuel is material reprocessed from other sources. One rich source of Pu-238 residual material is that from contaminated combustible materials, such as cheesecloth, ion exchange resins and plastics. From both waste minimization and production efficiency standpoints, the best solution is to recover this material. One way to accomplish separation of the organic component from these residues is a flameless oxidation process using molten salt as the matrix for the breakdown of the organic to carbon dioxide and water. The plutonium is retained in the salt, and can be recovered by dissolution of the carbonate salt in an aqueous solution, leaving the insoluble oxide behind. Further aqueous scrap recovery processing is used to purify the plutonium oxide. Recovery of the plutonium from contaminated combustibles achieves two important goals. First, it increases the inventory of Pu-238 available for heat source fabrication. Second, it is a significant waste minimization process. Because of its thermal activity (0.567 W per gram), combustibles must be packaged for disposition with much lower amounts of Pu-238 per drum than other waste types. Specifically, cheesecloth residues in the form of pyrolyzed ash (for stabilization) are being stored for eventual recovery of the plutonium

  5. Recovery of 238PuO2 by Molten Salt Oxidation Processing of 238PuO2 Contaminated Combustibles (Part II)

    Science.gov (United States)

    Remerowski, Mary Lynn; Dozhier, C.; Krenek, K.; VanPelt, C. E.; Reimus, M. A.; Spengler, D.; Matonic, J.; Garcia, L.; Rios, E.; Sandoval, F.; Herman, D.; Hart, R.; Ewing, B.; Lovato, M.; Romero, J. P.

    2005-02-01

    Pu-238 heat sources are used to fuel radioisotope thermoelectric generators (RTG) used in space missions. The demand for this fuel is increasing, yet there are currently no domestic sources of this material. Much of the fuel is material reprocessed from other sources. One rich source of Pu-238 residual material is that from contaminated combustible materials, such as cheesecloth, ion exchange resins and plastics. From both waste minimization and production efficiency standpoints, the best solution is to recover this material. One way to accomplish separation of the organic component from these residues is a flameless oxidation process using molten salt as the matrix for the breakdown of the organic to carbon dioxide and water. The plutonium is retained in the salt, and can be recovered by dissolution of the carbonate salt in an aqueous solution, leaving the insoluble oxide behind. Further aqueous scrap recovery processing is used to purify the plutonium oxide. Recovery of the plutonium from contaminated combustibles achieves two important goals. First, it increases the inventory of Pu-238 available for heat source fabrication. Second, it is a significant waste minimization process. Because of its thermal activity (0.567 W per gram), combustibles must be packaged for disposition with much lower amounts of Pu-238 per drum than other waste types. Specifically, cheesecloth residues in the form of pyrolyzed ash (for stabilization) are being stored for eventual recovery of the plutonium.

  6. Oxygen potential of (Pu, U)O2. 1. Oxygen potential measurement of UO2+X and (Pu0.3U0.7)O2-X

    International Nuclear Information System (INIS)

    The ratio of oxygen to metal is one of important fuel specifications on UO2 and MOX fuels, because it effects on irradiation behavior. Oxygen potential of oxide fuels have been measured by various methods on the purpose of optimization of irradiation behavior and fabrication condition. In this report the oxygen potential of UO2+X and (Pu0.3U0.7)O2-X was measured by thermal gravimetry and differential thermal analysis (TG-DTA). Measurements of oxygen potential were carried out at 800degC, 1000degC and 1200degC in Ar/H2/H2O mixture gas flow. Ratio of O/M was obtained from the weight change of the sample according to the partial oxygen pressure that was controlled by H2/H2O ratio in atmosphere. The partial oxygen pressure in atmosphere was measured by stabilized zirconia oxygen sensor. The experimental results agree approximately to the other works. Thermodynamic data, ΔGo-bar2, ΔHo-bar2, ΔSo-bar2, were evaluated from the experimental data. The oxygen potential of UO2+X, (Pu, U)O2±X and PuO2-X was modeled by lattice defect theory using the data of the literature and this work. The resulting equation well reproduce the large amount of oxygen potential-temperature-composition data for the Pu-U oxide system. (author)

  7. Measurement of the 240Pu/239Pu mass ratio using a transition-edge-sensor microcalorimeter for total decay energy spectroscopy.

    Science.gov (United States)

    Hoover, Andrew S; Bond, Evelyn M; Croce, Mark P; Holesinger, Terry G; Kunde, Gerd J; Rabin, Michael W; Wolfsberg, Laura E; Bennett, Douglas A; Hays-Wehle, James P; Schmidt, Dan R; Swetz, Daniel; Ullom, Joel N

    2015-04-01

    We have developed a new category of sensor for measurement of the (240)Pu/(239)Pu mass ratio from aqueous solution samples with advantages over existing methods. Aqueous solution plutonium samples were evaporated and encapsulated inside of a gold foil absorber, and a superconducting transition-edge-sensor microcalorimeter detector was used to measure the total reaction energy (Q-value) of nuclear decays via heat generated when the energy is thermalized. Since all of the decay energy is contained in the absorber, we measure a single spectral peak for each isotope, resulting in a simple spectral analysis problem with minimal peak overlap. We found that mechanical kneading of the absorber dramatically improves spectral quality by reducing the size of radioactive inclusions within the absorber to scales below 50 nm such that decay products primarily interact with atoms of the host material. Due to the low noise performance of the microcalorimeter detector, energy resolution values of 1 keV fwhm (full width at half-maximum) at 5.5 MeV have been achieved, an order of magnitude improvement over α-spectroscopy with conventional silicon detectors. We measured the (240)Pu/(239)Pu mass ratio of two samples and confirmed the results by comparison to mass spectrometry values. These results have implications for future measurements of trace samples of nuclear material. PMID:25723106

  8. In situ high temperature X-Ray diffraction study of the phase equilibria in the UO2-PuO2-Pu2O3 system

    Science.gov (United States)

    Belin, Renaud C.; Strach, Michal; Truphémus, Thibaut; Guéneau, Christine; Richaud, Jean-Christophe; Rogez, Jacques

    2015-10-01

    The region of the U-Pu-O phase diagram delimited by the compounds UO2-PuO2-Pu2O3 is known to exhibit a miscibility gap at low temperature. Consequently, MOX fuels with a composition entering this region could decompose into two fluorite phases and thus exhibit chemical heterogeneities. The experimental data on this domain found in the literature are scarce and usually provided using DTA that is not suitable for the investigation of such decomposition phenomena. In the present work, new experimental data, i.e. crystallographic phases, lattice parameters, phase fractions and temperature of phase separation, were measured in the composition range 0.14 thermodynamic model of the U-Pu-O system based on the CALPHAD method. Also, the combined use of thermodynamic calculations and XRD results refinement proved helpful in the determination of the O/M ratio of the samples during cooling. The methodology used in the current work might be useful to investigate other oxides systems exhibiting a miscibility gap.

  9. DFT and two-dimensional correlation analysis methods for evaluating the Pu(3+)-Pu(4+) electronic transition of plutonium-doped zircon.

    Science.gov (United States)

    Bian, Liang; Dong, Fa-qin; Song, Mian-xin; Dong, Hai-liang; Li, Wei-Min; Duan, Tao; Xu, Jin-bao; Zhang, Xiao-yan

    2015-08-30

    Understanding how plutonium (Pu) doping affects the crystalline zircon structure is very important for risk management. However, so far, there have been only a very limited number of reports of the quantitative simulation of the effects of the Pu charge and concentration on the phase transition. In this study, we used density functional theory (DFT), virtual crystal approximation (VCA), and two-dimensional correlation analysis (2D-CA) techniques to calculate the origins of the structural and electronic transitions of Zr1-cPucSiO4 over a wide range of Pu doping concentrations (c=0-10mol%). The calculations indicated that the low-angular-momentum Pu-fxy-shell electron excites an inner-shell O-2s(2) orbital to create an oxygen defect (VO-s) below c=2.8mol%. This oxygen defect then captures a low-angular-momentum Zr-5p(6)5s(2) electron to form an sp hybrid orbital, which exhibits a stable phase structure. When c>2.8mol%, each accumulated VO-p defect captures a high-angular-momentum Zr-4dz electron and two Si-pz electrons to create delocalized Si(4+)→Si(2+) charge disproportionation. Therefore, we suggest that the optimal amount of Pu cannot exceed 7.5mol% because of the formation of a mixture of ZrO8 polyhedral and SiO4 tetrahedral phases with the orientation (10-1). This study offers new perspective on the development of highly stable zircon-based solid solution materials. PMID:25841086

  10. U3-U5-PU9-CRITICALS, Critical Dimensions of Systems containing U235, Pu239, and U233

    International Nuclear Information System (INIS)

    Description: Compilation of critical data obtained from experiments performed in a number of laboratories during the period of 1945 through 1985. It supplements the Nuclear Safety Guide [Report. TID-7016 (Rev. 2)(ref.2) in presenting critical data on which recommendations of the Guide are based. This report gives critical data without safety factors, and is no substitute for the Guide or for the related document, The American National Standard for Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors (ref.3). This standard is supported by publications of H. K. Clark that interpret criticality information for Pu, U-233 and U-235 systems (ref.4-6). Information for guiding the safety design of equipment for handling the three common fissile materials appears to a certain extent in the Nuclear Safety Guide, and with greater detail in several handbooks (ref.7). Other publications specify conditions for unique processes with particular fissionable material (ref.8). Experiments of several types which contribute results applicable to nuclear design and to safety problems have been described by Callihan (ref.9). Critical measurements with materials of interest in desired configurations yield information of greatest usefulness and accuracy. In some cases, calculated results are desirable to fill in experimental data or to extend them. Where they appear in the reports, they are identified as calculations because of the uncertainty associated with them. Calculated extensions of experimental data are included to show the nature of trends, not to substitute for results of experiments. They should be used with caution. A fundamental aim of this document is to illustrate relationships among critical data. The compilation and correlation of data for this purpose, from many measurements in a number of laboratories, require a certain amount of normalization or reduction to common terms. Frequently, for example, the effects of variations in geometry or

  11. Settling standards for body content of 238Pu in man based on animal experimentation

    International Nuclear Information System (INIS)

    The paper is devoted to an urgent problem of radiation medicine, that of setting standards for body content of 238Pu which is of great practical significance. The analysis is based on literature and experimental findings of the authors on the 238Pu metabolism and biological effect for a wide range of doses on 4 animal species: mice, rats, rabbits and monkey. The report consists of two parts. The first deals with experimental results on body distribution of 238Pu, its elimination kinetics, and microdistribution in organs and tissues following intratracheal administration. In the second, characteristics of the radionuclide's biological effect are considered. General regularities for different animal species, as well as some specific peculiarities are established. Some interest are data on 238Pu microdistribution, on mechanisms and consequences of damage relative to changes in the lung tumour spectrum as influenced by the activity administered. Data for the damaging effect of α-radiation on the thymus structure due to relatively low absorbed doses are presented. Late effects of the incorporated 238Pu are studied in detail blastomogenic effect being the most significant. The incidence, latent period, and tumour spectrum are shown to depend on the activity administered. The analysis of experimental evidence suggests that damage of bone marrow stem cells due to low doses of 238Pu results in haematopoietic and lymphoid tissues tumours at late times. The significance of regulatory system damage for tumour genesis is discussed. The data obtained by the authors and clinical observations of lung tumours in uranium miners served as a basis for comparison of lung and bone radiosensitivities, and conclusion that susceptibilities of the rat and human lung tissues to α-radiation are similar, thus permitting direct extrapolation to man of experimental findings on carcinogenic effect of the incorporated 238Pu. From the analysis made, the authors conclude that safety factors of the

  12. Development of prototype induced-fission-based Pu accountancy instrument for safeguards applications.

    Science.gov (United States)

    Seo, Hee; Lee, Seung Kyu; An, Su Jung; Park, Se-Hwan; Ku, Jeong-Hoe; Menlove, Howard O; Rael, Carlos D; LaFleur, Adrienne M; Browne, Michael C

    2016-09-01

    Prototype safeguards instrument for nuclear material accountancy (NMA) of uranium/transuranic (U/TRU) products that could be produced in a future advanced PWR fuel processing facility has been developed and characterized. This is a new, hybrid neutron measurement system based on fast neutron energy multiplication (FNEM) and passive neutron albedo reactivity (PNAR) methods. The FNEM method is sensitive to the induced fission rate by fast neutrons, while the PNAR method is sensitive to the induced fission rate by thermal neutrons in the sample to be measured. The induced fission rate is proportional to the total amount of fissile material, especially plutonium (Pu), in the U/TRU product; hence, the Pu amount can be calibrated as a function of the induced fission rate, which can be measured using either the FNEM or PNAR method. In the present study, the prototype system was built using six (3)He tubes, and its performance was evaluated for various detector parameters including high-voltage (HV) plateau, efficiency profiles, dead time, and stability. The system's capability to measure the difference in the average neutron energy for the FNEM signature also was evaluated, using AmLi, PuBe, (252)Cf, as well as four Pu-oxide sources each with a different impurity (Al, F, Mg, and B) and producing (α,n) neutrons with different average energies. Future work will measure the hybrid signature (i.e., FNEM×PNAR) for a Pu source with an external interrogating neutron source after enlarging the cavity size of the prototype system to accommodate a large-size Pu source (~600g Pu). PMID:27337652

  13. Low-level inhaled-239PuO2 life-span studies in rats

    International Nuclear Information System (INIS)

    This study determined the dose-response curve for lung tumor incidence in rats after inhalation of high-fired 239PuO2, which gave radiation doses to the lung of from ∼5 to >1000 rads. Exposed rats were given a single, nose-only, inhalation exposure to 169Yb-239PuO2 aerosol (AMAD, 1.6 +- 0.11 μm). The effective half-time for 169Yb in the lung was 14 days, whereas ∼76% of 239Pu was cleared with a half-time of 20 days and 24%, with a half-time of 180 days. Whole-body counting for 169Yb at 14 days after exposure was an accurate method for determining 239Pu IAD in individual rats, even at IAD's as low as 0.60 nCi of 239Pu. The 239Pu lung-clearance curve and an equation describing changes in lung weight with body weight and age were used to determine lung radiation doses. The IAD's of exposure groups were 0.60 +- 0.15 nCi of 239Pu (1000 rats), 0.98 +- 0.25 (531 rats), 2.4 +- 0.69 (209 rats), 5.7 +- 1.2 (98 rats), and 7.5 +- 2.0 to 150 +- 37 nCi (300 rats); corresponding radiation doses to the lung estimated at 3 years after exposure were 8.3, 14, 33, 79, and 100 to 2100 rads, respectively. 71 refs., 5 figs., 4 tabs

  14. Minimum pickup velocity (U{sub pu}) of nanoparticles in gas–solid pneumatic conveying

    Energy Technology Data Exchange (ETDEWEB)

    Anantharaman, Aditya [Nanyang Technological University, School of Chemical and Biomedical Engineering (Singapore); Ommen, J. Ruud van [Delft University of Technology, Department of Chemical Engineering (Netherlands); Chew, Jia Wei, E-mail: JChew@ntu.edu.sg [Nanyang Technological University, School of Chemical and Biomedical Engineering (Singapore)

    2015-12-15

    This paper is the first systematic study of the pneumatic conveying of nanoparticles. The minimum pickup velocity, U{sub pu}, of six nanoparticle species of different materials [i.e., silicon dioxide (SiO{sub 2}), aluminum oxide (Al{sub 2}O{sub 3}), and titanium dioxide (TiO{sub 2})] and surfaces (i.e., apolar and polar) was determined by the weight loss method. Results show that (1) due to relative lack of hydrogen bonding, apolar nanoparticles had higher mass loss values at the same velocities, mass loss curves with accentuated S-shaped profiles, and lower U{sub pu} values, (2) among the three species, SiO{sub 2}, which has the lowest Hamaker coefficient, exhibited the greatest discrepancy between apolar and polar surfaces with respect to both mass loss curves and U{sub pu} values, (3) U{sub mf,polar}/U{sub mf,apolar} was between 1 and 3.5 times that of U{sub pu,polar}/U{sub pu,apolar} due to greater extents of hydrogen bonding associated with U{sub mf}, (4) U{sub pu} values were at least an order-of-magnitude lower than that expected from the well-acknowledged U{sub pu} correlation (Kalman et al., Powder Technol 160:103–113, 2005) due to agglomeration, (5) although nanoparticles should be categorized as Zone III (Kalman et al. 2005) (or Geldart group C, Powder Technol 7:285–292, 1973), the nanoparticles, and primary and complex agglomerates agreed more with the Zone I (or Geldart group B) correlation.

  15. Dosimetry and response in rat pulmonary epithelium following inhalation of 239PuO2

    International Nuclear Information System (INIS)

    The distribution of inhaled 239PuO2 and pathologic changes have been studied in the lung of rats. The clearance of inhaled 237239PuO2 from the lung is a function of the amount of deposited Pu with a decrease in early alveolar clearance with increasing lung burden. With increasing time post-exposure there is a greater concentration of PuO2 and an increased aggregation of PuO2 particles in subpleural regions of the lung. Fibrotic and metaplastic lesions in the lung were usually focal, being found in subpleural regions associated with aggregates of PuO2. An average of 12 +- 6 percent of the lung volume was fibrotic at 530 days after an initial alveolar deposition of 180 nCi 239Pu. Lung tumors occupied 4 +- 6 percent and epithelial metaplasias less than 1 percent of the lung volume at this time. Cell proliferation as assayed by tritiated thymidine autoradiography was greater in fibrotic, metaplastic and neoplastic regions than in areas of normal alveolar-bronchiolar epithelium. Turnover times ranged from about 6 days for fibrotic lesions to 1 to 3 days for metaplastic and neoplastic lesions. The lung tumor doubling times were 57 to 116 days due to tumor cell necrosis and other factors that limit tumor cell survival. Cell proliferation rates for adenomatous metaplasia were similar to those for adenocarcinoma while those for squamous cell metaplasia were similar to those for squamous cell carcinoma. Squamous lesions exhibited a more rapid growth than did adenomatous lesions

  16. Exchange reactions of plutonium with silicides and estimation of the enthalpy of the formation of Pu5Si3

    International Nuclear Information System (INIS)

    An approximate ΔHof,298 value has been determined for Pu5Si3 through a study of exchange reactions of selected metal silicides with plutonium. The reactions were carried out by arc-melting. Results show that Pu5Si3 is intermediate in stability between V3Si and Mo3Si, and has a ΔHof,298 of -52±13 kJ/g-atom. Estimates of ΔHof,298 for the higher plutonium silicides are: Pu3Si2 -54, PuSi -60, Pu3Si5 -58, and PuSi2 -56 kJ/g-atom with uncertainties of ±18 kJ/g-atom. The plutonium silicides are found to be more stable than both the thorium and uranium silicides. (orig.)

  17. Hematological responses after inhaling {sup 238}PuO{sub 2}: An extrapolation from beagle dogs to humans

    Energy Technology Data Exchange (ETDEWEB)

    Scott, B.R.; Muggenburg, B.A.; Welsh, C.A.; Angerstein, D.A.

    1994-11-01

    The alpha emitter plutonium-238 ({sup 238}Pu), which is produced in uranium-fueled, light-water reactors, is used as a thermoelectric power source for space applications. Inhalation of a mixed oxide form of Pu is the most likely mode of exposure of workers and the general public. Occupational exposures to {sup 238}PuO{sub 2} have occurred in association with the fabrication of radioisotope thermoelectric generators. Organs and tissue at risk for deterministic and stochastic effects of {sup 238}Pu-alpha irradiation include the lung, liver, skeleton, and lymphatic tissue. Little has been reported about the effects of inhaled {sup 238}PuO{sub 2} on peripheral blood cell counts in humans. The purpose of this study was to investigate hematological responses after a single inhalation exposure of Beagle dogs to alpha-emitting {sup 238}PuO{sub 2} particles and to extrapolate results to humans.

  18. Stability constants important to the understanding of plutonium in environmental waters, hydroxy and carbonate complexation of PuO2+

    International Nuclear Information System (INIS)

    The formation constants for the reactions PuO2+ + H2O = PuO2(OH) + H+ and PuO2+ + CO32 = PuO2(CO3)- were determined in aqueous sodium perchlorate solutions by laser-induced photoacoustic spectroscopy. The molar absorptivity of the PuO2+ band at 569 nm decreased with increasing hydroxide concentration. Similarly, spectral changes occurred between 540 and 580 nm as the carbonate concentration was increased. The absorption data were analyzed by the non-linear least-squares program SQUAD to yield complexation constants. Using the specific ion interaction theory, both complexation constants were extrapolated to zero ionic strength. These thermodynamic complexation constants were combined with the oxidation-reduction potentials of Pu to obtain Eh versus pH diagrams. 120 refs., 35 figs., 12 tabs

  19. Detection and Quantification of Pu(III, IV, V, and VI) Using a1.0-meter Liquid Core Waveguide

    Energy Technology Data Exchange (ETDEWEB)

    Wilson, Richard E.; Hu, Yung-Jin; Nitsche, Heino

    2005-02-15

    Detection and quantification of the aquo ions of Pu in 1 MHClO4 was carried out using a 1-meter liquid core waveguide (LCW) coupledto a fiber optic UV-Vis spectrometer. Detection limits of 7 x 10-7 M forPu(VI), 1.6 x 10-5 M for Pu(V), 5 x 10-6 M for Pu(IV) and 8 x 10-6 M forPu(III) were achieved. The limits of detection represent increases of 18to 33 times those achievable using a conventional 1-cm path length.Because of the much lower detection limits of the LCW, routineidentification of the oxidation states in dilute Pu solutions can bemade.

  20. The plutonium-oxygen phase diagram in the 25-900 °C range: Non-existence of the PuO1.515 phase

    Science.gov (United States)

    Haschke, John M.; Dinh, Long N.; McLean, William

    2015-03-01

    Evaluation of data for phases formed in the Pu-O system at temperatures below 900 °C shows that the observed oxides are not at equilibrium. Results are consistent with coexistence of a hexagonal solid solution (hex-PuO1.5+z, 0 ⩽ z ⩽ 0.010) and a cubic phase (cub-PuO1.60) in equilibrium at 800 °C, but fail to confirm that the O/Pu ratio of the body-centered-cubic (bcc) oxide formed near the sesquioxide composition is 1.515 (1.52) or that bcc-PuO1.515 is formed by the peritectic reaction of hex-PuO1.510 with cub-PuO1.60. Stable Pu(IV)/Pu(III) ratios observed for products of the Pu-H2O reaction correspond to members of the PunO2n-2 homologous series, but a product is not formed at O/Pu = 1.515. Metastable bcc-PuO1.50 (n = 4) and stable hex-PuO1.5+z coexist below 285 °C, the point at which reversible eutectic decomposition of cubic PuO1.60 (n = 5) produces a non-equilibrium mixture of bcc-PuO1.50 and sub-stoichiometric dioxide (PuO2-y). Transformation of bcc-PuO1.50 to stable hex-PuO1.50 and reactions of the hexagonal oxide to form higher-composition cubic phases are kinetically hindered. An alternative diagram describing non-equilibrium chemical behavior of the Pu-O system is presented.

  1. Pu-breeding feasibility in irradiation channels of research reactors

    Energy Technology Data Exchange (ETDEWEB)

    Tomanin, A., E-mail: alice.tomanin@jrc.ec.europa.e [Institute for the Protection and the Security of the Citizen, Joint Research Centre Ispra, Via E. Fermi, 2749, I-21027 ISPRA, Varese (Italy); University Ghent, Engineering Faculty, B-9052 Gent-Zwijnaarde (Belgium); Peerani, P. [Institute for the Protection and the Security of the Citizen, Joint Research Centre Ispra, Via E. Fermi, 2749, I-21027 ISPRA, Varese (Italy); Janssens-Maenhout, G. [Institute for Environment and Sustainability, Joint Research Centre Ispra, Via E. Fermi, 2749, I-21027 ISPRA (Italy); University Ghent, Engineering Faculty, B-9052 Gent-Zwijnaarde (Belgium)

    2011-02-15

    Research highlights: Clandestine plutonium production in irradiation channels of research reactors is a safeguard concern. IAEA concentrates safeguard measures on research reactors with thermal power greater that 25 MWth. The breeding potential in irradiation channels scales with reactor power and available space for irradiation samples. From about 10 MWth and 0.05 m{sup 3} onwards the proliferation concern raises with more than 2 kg of yearly plutonium breeding capability. - Abstract: The breeding potential in the irradiation channels of research reactors is of safeguards concern, because of lacking continuous supervision on the type of experiments in all the irradiation channels. Moreover, the irradiation time can be optimized in order to breed high quality weapon grade plutonium. With regard to the safeguards measures currently adopted, IAEA concentrates its efforts on those reactors whose thermal power is greater than 25 MWth, because it was calculated that a 25 MWth LEU-fuelled reactor produces not more than one Significant Quantity of Pu (8 kg)/year in its spent fuel and a HEU-fuelled reactor of this power would require an annual reload of not more than one Significant Quantity of U{sub 235} (25 kg). In order to investigate whether it would be possible to determine an analogous power level threshold to estimate the clandestine plutonium production capability of different research reactors, the Monte Carlo method was used to determine the neutron flux in the irradiation channels and to calculate the plutonium breeding potential for three different reactor types: (1) a Triga Mark II with 250 kWth, representative for a small size research reactor; (2) a Material Test Reactor (MTR) with 5 MWth, representative for a medium size research reactor; (3) a High Flux Reactor (HFR) with 45 MWth, representative for a large size research reactor. It was observed that the most important factors for plutonium breeding are the neutron flux (to which reaction rates are

  2. Neutron-induced fission cross section of 240,242Pu up to En = 3 MeV

    OpenAIRE

    SALVADOR CASTINEIRA PAULA; BRYS TOMASZ; Hambsch, Franz-Josef; Oberstedt, Stephan; Pretel, C.; Vidali, Marzio

    2014-01-01

    The neutron-induced fission cross sections of 240,242Pu have been measured at JRC-IRMM with incident neutron energy from 0.2 MeV up to 3 MeV. A Twin-Frisch Grid Ionization Chamber (TFGIC) has been used in a back-to-back geometry. The measurements have been performed using the secondary standards 237Np and 238U as a reference. The purity of the plutonium samples was 99.89% for 240Pu and 99.97% for 242Pu. The results obtained follow the ENDF/B-VII.1 evaluation for 240Pu, but some discrepancies ...

  3. {\\alpha}-accompanied cold ternary fission of $^{238-244}$Pu isotopes in equatorial and collinear configuration

    CERN Document Server

    Santhosh, K P; Priyanka, B

    2015-01-01

    The cold ternary fission of $^{238}$Pu, $^{240}$Pu, $^{242}$Pu and $^{244}$Pu isotopes, with $^{4}$He as light charged particle, in equatorial and collinear configuration has been studied within the Unified ternary fission model (UTFM). The fragment combination $^{100}$Zr+$^{4}$He+$^{134}$Te possessing the near doubly magic nuclei $^{134}$Te (N=82, Z=52) gives the highest yield in the alpha accompanied ternary fission of $^{238}$Pu. For the alpha accompanied ternary fission of $^{240}$Pu, $^{242}$Pu and $^{244}$Pu isotopes, the highest yield was found for the fragment combination with doubly magic nuclei $^{132}$Sn (N=82, Z=50) as the heavier fragment. The deformation and orientation of fragments have also been taken into account for the alpha accompanied ternary fission of $^{238-244}$Pu isotopes, and it has been found that in addition to closed shell effect, ground state deformation also plays an important role in determining the isotopic yield in the ternary fission process. The emission probability and ki...

  4. Separation of uranium from solid (U, Pu, Ag) oxide analytical waste: effect of batch size and nitric acid molarity

    International Nuclear Information System (INIS)

    Quality control analyses of Pu based nuclear fuels for trace metallic content by the DC-Arc-AES technique, produce a large amount of solid analytical waste containing Pu, U and Ag. Through the present study, an attempt was made to separate uranium from the bulk of the analytical waste using HNO3 leaching. Systematic studies have been carried out to optimize various parameters, such as acid molarity, contact time, and batch size, required to remove uranium preferentially from the solid waste leaving behind Pu and other impurities. The concentrations of U, Pu, Ag and other impurities during this exercise were intermittantly determined using ICP-AES. (author)

  5. Distribution and source of (129)I, (239)(,240)Pu, (137)Cs in the environment of Lithuania.

    Science.gov (United States)

    Ežerinskis, Ž; Hou, X L; Druteikienė, R; Puzas, A; Šapolaitė, J; Gvozdaitė, R; Gudelis, A; Buivydas, Š; Remeikis, V

    2016-01-01

    Fifty five soil samples collected in the Lithuania teritory in 2011 and 2012 were analyzed for (129)I, (137)Cs and Pu isotopes in order to investigate the level and distribution of artificial radioactivity in Lithuania. The activity and atomic ratio of (238)Pu/((239,24)0)Pu, (129)I/(127)I and (131)I/(137)Cs were used to identify the origin of these radionuclides. The (238)Pu/(239+240)Pu and (240)Pu/(239)Pu ratios in the soil samples analyzed varied in the range of 0.02-0.18 and 0.18-0.24, respectively, suggesting the global fallout as the major source of Pu in Lithuania. The values of 10(-9) to 10(-6) for (129)I/(127)I atomic ratio revealed that the source of (129)I in Lithuania is global fallout in most cases though several sampling sites shows a possible impact of reprocessing releases. Estimated (129)I/(131)I ratio in soil samples from the southern part of Lithuania shows negligible input of the Chernobyl fallout. No correlation of the (137)Cs and Pu isotopes with (129)I was observed, indicating their different sources terms. Results demonstrate uneven distribution of these radionuclides in the Lithuanian territory and several sources of contamination i.e. Chernobyl accident, reprocessing releases and global fallout. PMID:26476410

  6. Thermal expansion measurement of (U,Pu)O2-x in oxygen partial pressure-controlled atmosphere

    Science.gov (United States)

    Kato, Masato; Ikusawa, Yoshihisa; Sunaoshi, Takeo; Nelson, Andrew T.; McClellan, Kenneth J.

    2016-02-01

    Thermal expansion of U0.7Pu0.3O2-x (x = 0, 0.01, 0.02, 0.03) and U0.52Pu0.48O2.00 was investigated by a unique dilatometry which measured in an oxygen partial pressure-controlled atmosphere. The oxygen partial pressure was controlled to hold a constant oxygen-to-metal ratio in the (U,Pu)O2-x during the measurement. Thermal expansion slightly increased with the decrease in oxygen-to-metal ratio. We proposed a relationship to describe thermal expansion as a function of temperature, O/M and Pu content.

  7. Reduction of Pu(VI) on Fe surfaces: soft x-ray absorption and resonant inelastic scattering study

    Energy Technology Data Exchange (ETDEWEB)

    Butorin, S.M.; Kvashnina, K.O.; Modin, A.; Nordgren, J. (Dept. of Physics and Materials Science, Uppsala Univ., Uppsala (Sweden)); Guo, J.H. (Advanced Light Source, Lawrence Berkeley National Laboratory, Berkeley, CA (United States)); Shuh, D.K. (Chemical Science Div., Lawrence Berkeley National Laboratory, Berkeley, CA (United States)); Werme, L. (Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden))

    2009-03-15

    Based on analysis of spectral shapes, their dependence on the energy of incident photons and comparison with model calculations and experimental data from the reference sample we can conclude that plutonium from the Pu(VI) solution sorbed on Fe surfaces is likely to be reduced and Pu species sorbed on the Fe foils are mainly in the form of Pu (IV). Current results correlate with what was observed for for Np (V) and U (VI) in our previous studies. Furthermore, combined analysis of present data with model atomic multiplet calculations of RIXS and XAS spectra suggests that significant presence of Pu(III) on the Fe foils is unlikely

  8. Plutonium 241Pu in tissues and organs of Cervidae from Northern Poland

    International Nuclear Information System (INIS)

    Livers, kidneys and muscles of large herbivorous animals: roe deer, red deer and fallow deer, collected in Northern Poland, were the subject of the investigation. The concentration of 241Pu ranged widely between 1.31 ± 0.28 and 214.5 ± 25.8 mBq kg-1 ww and decreased in the order kidney > liver > muscle. The average values of the activity concentrations of 241Pu were 11.5 ± 1.8 mBq kg-1 ww in muscles, 14.0 ± 2.25 mBq kg-1 ww in liver and 85.5 ± 9.7 mBq kg-1 ww in kidneys. As statistically checked the sampling location, sex, age and species of animals did not influence on plutonium concentrations of the analyzed samples. Only the organ type significantly influenced 241Pu content. The values of 241Pu/29+240Pu activity ratio in analyzed samples ranged from 7.12 ± 2.15 to 99.3 ± 16.4 and the results showed the main source of plutonium in analyzed organs could be the Chernobyl accident.

  9. Mechanism of the rapid dissolution of Pu02 under oxidizing conditions and applications

    International Nuclear Information System (INIS)

    Until the recent years, plutonium dioxide was known to be among the metallic oxides the most difficult to dissolve. From thermodynamic calculations it can be predicted that PuO2 will dissolve under oxidizing conditions. This can be achieved using Ag(II) species possibly regenerated by electrochemical means. The mechanism of such a process has been elucidated using carbon paste electrochemistry and 18O labelling. These studies demonstrate that the chemical reaction limiting the overall proces is located on the surface of the solid PuO2, and that the first step consists in the oxidation of the plutonium into Pu(V) species. Applications of the dissolution process of PuO2 by electrogenerated Ag(II) were growing in the recent years in FRANCE. These applications developed often in collaboration with SGN and COGEMA, concern the treatment of: out of specifications PuO2, incineration ashes, wastes produced during MOX fuel fabrication, and during the dismantling of old nuclear facilities. A general overview of these different applications is given

  10. Plutonium {sup 241}Pu in tissues and organs of Cervidae from Northern Poland

    Energy Technology Data Exchange (ETDEWEB)

    Struminska-Parulska, Dagmara I.; Skwarzec, Bogdan [Gdansk Univ. (Poland). Dept. of Environmental Chemistry and Radiochemistry

    2015-07-01

    Livers, kidneys and muscles of large herbivorous animals: roe deer, red deer and fallow deer, collected in Northern Poland, were the subject of the investigation. The concentration of {sup 241}Pu ranged widely between 1.31 ± 0.28 and 214.5 ± 25.8 mBq kg{sup -1} ww and decreased in the order kidney > liver > muscle. The average values of the activity concentrations of {sup 241}Pu were 11.5 ± 1.8 mBq kg{sup -1} ww in muscles, 14.0 ± 2.25 mBq kg{sup -1} ww in liver and 85.5 ± 9.7 mBq kg{sup -1} ww in kidneys. As statistically checked the sampling location, sex, age and species of animals did not influence on plutonium concentrations of the analyzed samples. Only the organ type significantly influenced {sup 241}Pu content. The values of {sup 241}Pu/{sup 29+240}Pu activity ratio in analyzed samples ranged from 7.12 ± 2.15 to 99.3 ± 16.4 and the results showed the main source of plutonium in analyzed organs could be the Chernobyl accident.

  11. DENSITY-FUNCTIONAL CALCULATIONS FOR Ce, Th, AND Pu METALS AND ALLOYS

    Directory of Open Access Journals (Sweden)

    A.Landa

    2004-01-01

    Full Text Available The phase diagrams of Ce, Th, and Pu metals have been studied by means of density-functional theory (DFT. In addition to these metals, the phase stability of Ce-Th and Pu-Am alloys has been also investigated from first-principles calculations. Equation-of-state (EOS for Ce, Th, and the Ce-Th alloys has been calculated up to 1 Mbar pressure in good comparison to experimental data. Present calculations show that the Ce-Th alloys adopt a body-centered-tetragonal (bct structure upon hydrostatic compression which is in excellent agreement with measurements. The ambient pressure phase diagram of Pu is shown to be very poorly described by traditional DFT but rather well modelled when including magnetic interactions. In particular, the anomalous δ phase of Pu is shown to be stabilized by magnetic disorder at elevated temperatures. The Pu-Am system has also been studied in a similar fashion and it is shown that this system, for about 25% Am content, becomes antiferromagnetic below about 400 K which corroborates the recent discovery of a Curie-Weiss behavior in this system.

  12. PuReMD-GPU: A reactive molecular dynamics simulation package for GPUs

    Energy Technology Data Exchange (ETDEWEB)

    Kylasa, S.B., E-mail: skylasa@purdue.edu [Department of Elec. and Comp. Eng., Purdue University, West Lafayette, IN 47907 (United States); Aktulga, H.M., E-mail: hmaktulga@lbl.gov [Lawrence Berkeley National Laboratory, 1 Cyclotron Rd, MS 50F-1650, Berkeley, CA 94720 (United States); Grama, A.Y., E-mail: ayg@cs.purdue.edu [Department of Computer Science, Purdue University, West Lafayette, IN 47907 (United States)

    2014-09-01

    We present an efficient and highly accurate GP-GPU implementation of our community code, PuReMD, for reactive molecular dynamics simulations using the ReaxFF force field. PuReMD and its incorporation into LAMMPS (Reax/C) is used by a large number of research groups worldwide for simulating diverse systems ranging from biomembranes to explosives (RDX) at atomistic level of detail. The sub-femtosecond time-steps associated with ReaxFF strongly motivate significant improvements to per-timestep simulation time through effective use of GPUs. This paper presents, in detail, the design and implementation of PuReMD-GPU, which enables ReaxFF simulations on GPUs, as well as various performance optimization techniques we developed to obtain high performance on state-of-the-art hardware. Comprehensive experiments on model systems (bulk water and amorphous silica) are presented to quantify the performance improvements achieved by PuReMD-GPU and to verify its accuracy. In particular, our experiments show up to 16× improvement in runtime compared to our highly optimized CPU-only single-core ReaxFF implementation. PuReMD-GPU is a unique production code, and is currently available on request from the authors.

  13. Identifying and localizing network problems using the PuNDIT project

    Science.gov (United States)

    Batista, Jorge; Dovrolis, Constantine; Lee, Danny; McKee, Shawn

    2015-12-01

    In today's world of distributed collaborations of scientists, there are many challenges to providing effective infrastructures to couple these groups of scientists with their shared computing and storage resources. The Pythia Network Diagnostic InfrasTructure (PuNDIT[1]) project is integrating and scaling research tools and creating robust code suitable for operational needs addressing the difficult challenge of automating the detection and location of network problems.PuNDIT is building upon the de-facto standard perfSONAR[2] network measurement infrastructure deployed in Open Science Grid(OSG)[3] and the Worldwide LHC Computing Grid(WLCG)[4]to gather and analyze complex real-world network topologies coupled with their corresponding network metrics to identify possible signatures of network problems from a set of symptoms. The PuNDIT Team is working closely with the perfSONAR developers from ESnet and Internet2 to integrate PuNDIT components as part of the perfSONAR Toolkit. A primary goal for PuNDIT is to convert complex network metrics into easily understood diagnoses in an automated way. We will report on the project progress to-date in working with the OSG and WLCG communities, describe the current implementation including some initial results and discuss future plans and the project timeline.

  14. Repeated inhalation exposure of rats to aerosols of 239PuO2. V

    International Nuclear Information System (INIS)

    The biological responses following protracted alpha irradiation of rat lungs are being studied. Groups of rats have been exposed once, or repeatedly, to aerosols of 239PuO2 to achieve, or to re-establish, lung burdens of 239Pu that will result in projected lifetime alpha-radiation doses to the lungs of 20, 60, 200, or 600 rad. There were dose related increases in the incidence of primary lung tumors In the rats exposed once or repeatedly to 239PuO2. Repeated inhalation exposure of rats to 239PuO2 did not increase the incidence of lung tumors, their time of occurrence nor the risk of death with a lung tumor per unit of absorbed alpha dose to the lung compared to doses received following single exposures. These findings are consistent with those in Beagle dogs repeatedly exposed to 239PuO2 in other studies, but are not consistent with previous observations In mice. The findings in mice indicated protraction of the alpha dose to the lung by repeated inhalation exposure was more carcinogenic than similar doses after a single inhalation exposure. (author)

  15. Migration of 239Pu in soluble and insoluble forms in soil

    International Nuclear Information System (INIS)

    A field experiment study was performed at the rural site of South-East Lithuania. The main tasks of the study included an evaluation of the peculiarities of partition of 239Pu in soluble (239Pu(NO3)4, 239PuCl3) and insoluble (239PuO2) forms in soddy and forest soil horizons. The results of durable experiments (418 and 326 days) have shown that from 44.1% to 92.2% of 239Pu of investigated chemical forms were accumulated in the top (0-5 cm) soil layer. Some share (5.7-39.2%) of plutonium from studied chemical forms was found in the 5-20 cm layers of studied soil samples (columns). Obtained distribution of plutonium in soil layers may be attributed to the consideration that the migration rate to the soil depth for plutonium is 0.1-1.0 cm x y-1 but for some part of plutonium 10 times higher migration rate is characteristic as well. Plutonium transfer factor (TF) to the grassland plants was calculated, the values ranged from 10-2 to 10-1. (author)

  16. Quality control of (Th,Pu)O2 fuel pellet obtained by coated agglomerate pelletization

    International Nuclear Information System (INIS)

    (Th,Pu)O2 fuel pellets were synthesised by coated agglomerate pelletization route and characterized for the chemical quality control. (Th,Pu)O2 pellets were characterized for trace metals by spectrometric methods and non metals by ion chromatographic, spectrophotometric, conductometric and manometric methods. H, F, B and Cd contents were found to be less than 1 ppm while that for V and Cl were found to be less than 10 ppm. The pellets were found to contain Cr, Cu, Mo, Na, Ni and Pb in the range of 10-50 ppm whereas Zn, Al, Ca and C in the range of 50-100 ppm. More than 100 ppm Si, Fe and Mg were found to be present in the (Th,Pu)O2 pellets. The O/M content of the pellets were found to be ∼2.00. A comparative study on (Infrared) I.R. and microwave (microwave) dissolution were also used to ascertain the Th and Pu content in the (Th,Pu)O2 pellets. (author)

  17. Review of DOE criteria for safe storage of Pu metals and oxides

    International Nuclear Information System (INIS)

    A technical review of the DOE criteria for storage of plutonium metals and oxides determined the maximum pressure that could be obtained from 50-year storage of 5.0-kg of PuO2 powder under the assumed worst-case conditions derived from the DOE standard [1,2]. Those conditions included a final temperature of 400 F and the reaction to yield H2 gas in accordance with the equation PuO2(c) + x H2O rarrow PuO2+x(c) + x H2(g) where the x moles of sorbed water represents 0.5 wt.% of the PuO2. The worst-case conditions also included the generation of He gas from the 50-year α-decay of the plutonium, that was considered to be power grade plutonium with the maximum limit of 3% for the short-lived isotope, Pu-238. The free volume for containment of the gases generated in the primary containment vessel, assuming failure of its inner boundary container, was assumed to be 2.5-L value given in the original standard

  18. Stabilization of Rocky Flats Pu-contaminated ash within chemically bonded phosphate ceramics

    International Nuclear Information System (INIS)

    A feasibility study was conducted on the use of chemically bonded phosphate ceramics for stabilization of combustion residue of high transuranic (TRU) wastes. Using a matrix of magnesium potassium phosphate formed by the room-temperature reaction of MgO and KH2PO4 solution, we made waste forms that contained 5 wt% Pu to satisfy the requirements of the waste isolation pilot plant. The waste forms were ceramics whose compression strength was twice that of conventional cement grout and whose connected porosity was ∝50% that of cement grout. Both surrogate and actual waste forms displayed high leaching resistance for both hazardous metals and Pu. Hydrogen generation resulting from the radiolytic decomposition of water and organic compounds present in the waste form did not appear to be a significant issue. Pu was present as PuO2 that was physically microencapsulated in the matrix. In the process, pyrophoricity was removed and leaching resistance was enhanced. The high leaching resistance was due to the very low solubility of PuO2 coupled with superior microencapsulation. As a result, the waste forms satisfied the current safeguard termination limit requirement for storage of TRU combustion residues. (orig.)

  19. Comparison of Pu isotopic composition between gamma and mass spectrometry: Experience from IAEA-SAL

    International Nuclear Information System (INIS)

    About 2000 Pu containing samples have been analysed during the last 8 years at SAL using gamma spectrometry (GS) in parallel with mass spectrometry (MS). Four different detectors have been used for the measurement of gamma-ray spectra and several versions of the MGA program have been used for spectra evaluation. The results of Pu isotopic composition obtained by both methods have neem systematically compared. Attempts to improve the agreement between GS and MS are described. This was done by adjustment of the emission probabilities for some gamma energies and the development of a new correlation equation for 242Pu. These improvements have been applied for evaluation of two sets containing 320 and 404 samples, respectively analysed in 1991 and in 1992-93. The mean differences and their standard deviations between MS and GS were calculated, showing mean relative differences for 238-241Pu isotopes in the range from 0.1 to 0.5% with standard deviations within ± 0.4 to ±1%. For 242Pu these values are about 0.5% and ± 5%, respectively. (author)

  20. PROPERTIES AND BEHAVIOR OF 238PU RELEVANT TO DECONTAMINATION OF BUILDING 235-F

    Energy Technology Data Exchange (ETDEWEB)

    Duncan, A.; Kane, M.

    2009-11-24

    This report was prepared to document the physical, chemical and radiological properties of plutonium oxide materials that were processed in the Plutonium Fuel Form Facility (PuFF) in building 235-F at the Savannah River Plant (now known as the Savannah River Site) in the late 1970s and early 1980s. An understanding of these properties is needed to support current project planning for the safe and effective decontamination and deactivation (D&D) of PuFF. The PuFF mission was production of heat sources to power Radioisotope Thermoelectric Generators (RTGs) used in space craft. The specification for the PuO{sub 2} used to fabricate the heat sources required that the isotopic content of the plutonium be 83 {+-} 1% Pu-238 due to its high decay heat of 0.57 W/g. The high specific activity of Pu-238 (17.1 Ci/g) due to alpha decay makes this material very difficult to manage. The production process produced micron-sized particles which proved difficult to contain during operations, creating personnel contamination concerns and resulting in the expenditure of significant resources to decontaminate spaces after loss of material containment. This report examines high {sup 238}Pu-content material properties relevant to the D&D of PuFF. These relevant properties are those that contribute to the mobility of the material. Physical properties which produce or maintain small particle size work to increase particle mobility. Early workers with {sup 238}PuO{sub 2} felt that, unlike most small particles, Pu-238 oxide particles would not naturally agglomerate to form larger, less mobile particles. It was thought that the heat generated by the particles would prevent water molecules from binding to the particle surface. Particles covered with bound water tend to agglomerate more easily. However, it is now understood that the self-heating effect is not sufficient to prevent adsorption of water on particle surfaces and thus would not prevent agglomeration of particles. Operational

  1. Phase equilibria in the UO2-PuO2 system under a temperature gradient

    International Nuclear Information System (INIS)

    The phase behaviour of U0.80Pu0.20O1.95 was investigated under a steady-state temperature gradient between the solidus and liquidus by a short-time power-to-melt irradiation experiment. The radial U, Pu, Am and O profiles in the fuel pin after redistribution were measured by X-ray microanalysis. During irradiation, an inner fuel melt forms which is separated from the outer solid only by one concentric liquid-solid-phase boundary. The UO2 concentration increases to 85% and the PuO2 concentration decreases to 15% on the solid side of the interface. Opposite gradients occur on the liquid side of the interface. The concentration discontinuity is a consequence of the necessary equality of the chemical potentials of UO2 and PuO2 on both sides of the phase boundary which corresponds to a 2750 deg. C isotherm. The radial oxygen profile results in an O/(U + Pu) ratio of 2.00 at the fuel surface and 1.92 at the central void of the fuel. The redistribution is caused by the thermal diffusion of oxygen vacancies in the lattice along the temperature gradient. This process is quantified by the heat of transport Q*v which ranges between -10 kJ/mol at the central void and about -230 kJ/mol near the fuel surface. (author)

  2. A first-principles study of PuN (0 0 1) surface properties

    International Nuclear Information System (INIS)

    The properties of PuN (0 0 1) surface have been investigated using all-electron full-potential linearized augmented plane wave plus local orbitals basis (FP-LAPW+lo) method at both scalar- and fully- relativistic levels, with and without spin-polarization. The ground state of PuN (0 0 1) surface is found to be ferromagnetic with spin–orbit coupling (FM + SO). At the ground state, the semi-infinite surface energy and average work function for PuN (0 0 1) surface are predicted to be 1.12 J/m2 and 2.62 eV, respectively. At three layers of formula units and beyond, the PuN (0 0 1) surface properties including total energies per N-formula unit, surface energy, work function and magnetic moment converge, indicating that a 3-layer slab can be used to model PuN (0 0 1) surface to a good approximation. The localization of the 5f electron states is pronounced at the top surface layer while bulk-like behavior is exhibited at the second and deeper layers

  3. Determination of the half-life and specific thermal power of 241Pu by nuclear calorimetry

    International Nuclear Information System (INIS)

    241Pu has the shortest half-life of the abundant plutonium isotopes present in reprocessed irradiated nuclear fuel with a value of approximately 14.3 years. It is important to know the half-life of 241Pu with a higher fractional accuracy than that of the other plutonium isotopes because the half-life of 241Pu and its associated uncertainty affects the estimation by decay calculation of both the total amount of separated plutonium in storage and the determination of the total plutonium mass by non-destructive assay. This paper addresses the determination of the 241Pu half-life using nuclear calorimetry by the measurement of the thermal power as 241Pu evolves in time from a sealed plutonium source, ideally initially rich in 241Pu and chemically stripped of 241Am. The absolute accuracy of nuclear calorimeters can be ensured over long periods of time (many years) using long-lived nuclear reference materials and/or traceable electrical heat standards. One can, therefore, expect nuclear calorimetry to offer an accurate way to determine the half-life of 241Pu, which is comparable in quality and independent, yet complementary, to other approaches. Temporal analysis of the power-versus-time data also yields an estimate of the specific power of 241Pu, which other methods do not. After describing the principle of the method and developing the pertinent mathematical expressions, we outline the approach by drawing on some unpublished notes of Kenneth C. Jordan who carried out such experiments at the Mound Laboratory over 40 years ago. Today, Jordan’s work remains possibly the most significant experiment of its type to the 241Pu nuclear data evaluator. However, objectively assigning confidence to his results is problematic because the details of the experiments and data reduction have never been adequately reported. This work goes some way to that end but, without the raw data and first-hand knowledge, cannot provide a complete record. We conclude that a new high

  4. Designing of Multiphase Fly Ash/MWCNT/PU Composite Sheet Against Electromagnetic Environmental Pollution

    Science.gov (United States)

    Gujral, Parth; Varshney, Swati; Dhawan, S. K.

    2016-06-01

    Fly ash and multiwalled carbon nanotubes (MWCNT) reinforced multiphase polyurethane (PU) composite sheets have been fabricated by using a solution casting technique. Utilization of fly ash was the prime objective in order to reduce environmental pollution and to enhance the shielding properties of PU polymer. Our study proves that fly ash particles with MWCNTs in a PU matrix leads to novel hybrid high performance electromagnetic shielding interference material. Scanning electron microscopy confirms the existence of fly ash particles along with MWCNTs in a PU matrix. This multiphase composite shows total shielding effectiveness of 35.8 dB (>99.99% attenuation) in the Ku-band (12.4-18 GHz) frequency range. This is attributed to high dielectric losses of reinforcement present in the polymers matrix. The Nicolson-Ross-Weir algorithm has been applied to calculate the electromagnetic attributes and dielectric parameters of the PU samples by using scattering parameters ( S 11, S 22, S 12, S 21). The synthesized multiphase composites were further characterized by using x-ray diffraction, Fourier transform infrared spectroscopy, and thermo gravimetric analysis.

  5. Comparison and modification of Pu-239 kinetics in young and adult rats

    International Nuclear Information System (INIS)

    It is obvious that the biokinetics of bone-seeking radionuclides are influenced by skeletal growth and remodelling, the rate of which in general decreases with increasing age. For plutonium, Mahlum and Sikov (1974) observed that rats injected with Pu-239 as weanlings retained a lower percentage in the liver and more in the bones than the animals injected as adults. However, skeletal Pu-239 was diluted more rapidly in the young rats because of intensive new bone formation and this led to a more pronounced reduction in the accumulation of radiation dose than was the case in adult animals. The aim of the present experiments was to study: a) The age effect on Pu-239 biokinetics in adult rates as influenced by the sex of the animals. b) Early retention and distribution of Pu-239 in the bones of young and adult rats injected with an optimal osteosarcomogenic dose. c) The effectiveness of a delayed prolonged administration of Zn-DTPA in drinking water for the mobilization of injected Pu-239 in rats of various age. 3 refs.; 5 figs.; 1 table

  6. Reactivity of the uranium (U(IV)/U(VI)) and the plutonium (Pu(III)/Pu(IV)) in nitric aqueous solution under ultrasound

    International Nuclear Information System (INIS)

    To minimize the volumes of solid waste and industrial effluents generated at the end of cycle, particularly in the spent nuclear fuel reprocessing industry, research is currently under way on so-called innovative processes, designed to induce chemical reactions without adding reagent to the media. Among these processes, the use of ultrasound can prove advantageous, and the purpose of this study is to assess accurately the potential for its application. In the present context, this work shows that the transmission of an ultrasonic wave in aqueous nitric acid solution leads to: the accumulation of nitrous acid in solution, until a steady-sate concentration is reached; the removal of nitrogen monoxide and nitrogen dioxide in the gas stream. The initial kinetics of the formation of HNO2 in solution was quantified as a function of the nitric acid concentration and the ultrasound intensity. It was also shown than an excess of nitrous acid in nitric solution decomposes under the effect of ultrasound. It is also possible to accumulate hydrogen peroxide in solution during the ultrasonic irradiation of aqueous nitric acid solutions in the presence of a chemical species N2H5+, NH2SO3H...) which reacts rapidly with HNO2, preventing the reduction of H2O2 by HNO2. The mechanisms of HNO2 formation and decomposition, and the mechanism of H2O2 formation during the ultrasonic irradiation of aqueous nitric acid solutions, are presented. Control of H2O2 or HNO2 in a nitric acid medium under the effect of an ultrasonic wave can be exploited to control redox reactions of uranium and plutonium ions, particularly with respect to the oxidation of U and Pu (U(IV)→ U(IV) or Pu(III) → Pu(IV)) and the reduction of Pu (Pu(IV)→ Pu(III). The redox behavior of uranium and plutonium ions in aqueous nitric solution subject to an ultrasonic flux is interpreted in term of effects induced on the reaction medium, and reveals the potential for using ultrasound to cause chemical reactions in

  7. Simultaneous determination of radiocesium ((135)Cs, (137)Cs) and plutonium ((239)Pu, (240)Pu) isotopes in river suspended particles by ICP-MS/MS and SF-ICP-MS.

    Science.gov (United States)

    Cao, Liguo; Zheng, Jian; Tsukada, Hirofumi; Pan, Shaoming; Wang, Zhongtang; Tagami, Keiko; Uchida, Shigeo

    2016-10-01

    Due to radioisotope releases in the Fukushima Dai-ichi Nuclear Power Plant (FDNPP) accident, long-term monitoring of radiocesium ((135)Cs and (137)Cs) and Pu isotopes ((239)Pu and (240)Pu) in river suspended particles is necessary to study the transport and fate of these long-lived radioisotopes in the land-ocean system. However, it is expensive and technically difficult to collect samples of suspended particles from river and ocean. Thus, simultaneous determination of multi-radionuclides remains as a challenging topic. In this study, for the first time, we report an analytical method for simultaneous determination of radiocesium and Pu isotopes in suspended particles with small sample size (1-2g). Radiocesium and Pu were sequentially pre-concentrated using ammonium molybdophosphate and ferric hydroxide co-precipitation, respectively. After the two-stage ion-exchange chromatography separation from the matrix elements, radiocesium and Pu isotopes were finally determined by ICP-MS/MS and SF-ICP-MS, respectively. The interfering elements of U ((238)U(1)H(+) and (238)U(2)H(+) for (239)Pu and (240)Pu, respectively) and Ba ((135)Ba(+) and (137)Ba(+) for (135)Cs and (137)Cs, respectively) were sufficiently removed with the decontamination factors of 1-8×10(6) and 1×10(4), respectively, with the developed method. Soil reference materials were utilized for method validation, and the obtained (135)Cs/(137)Cs and (240)Pu/(239)Pu atom ratios, and (239+240)Pu activities showed a good agreement with the certified/information values. In addition, the developed method was applied to analyze radiocesium and Pu in the suspended particles of land water samples collected from Fukushima Prefecture after the FDNPP accident. The (135)Cs/(137)Cs atom ratios (0.329-0.391) and (137)Cs activities (23.4-152Bq/g) suggested radiocesium contamination of the suspended particles mainly originated from the accident-released radioactive contaminates, while similar Pu contamination of suspended

  8. Cancellation of spin and orbital magnetic moments in δ-Pu: Theory

    International Nuclear Information System (INIS)

    Density functional theory (DFT), in conjunction with the fixed-spin-moment (FSM) method, spin-orbit coupling (SO), and orbital polarization (OP), is shown to retain key features of the conventional DFT treatment of δ-Pu while at the same time not producing the substantial net magnetic moments commonly predicted by this theory. It is shown that when a small adjustment of the spin moment (less than 20%) is allowed, a complete spin- and orbital-moment cancellation occurs which results in a zero net magnetic moment in δ-Pu. This minor modification, accomplished by the FSM method, is shown to have a very small effect on the calculated total energy as well as the electron density-of-states (DOS). The photoemission spectra (PES), obtained from the DOS of the present model, compares equal or better to measured spectra, than that of two other recent non-magnetic models for δ-Pu

  9. Molecular Structure and Bonding in Plutonium Carbides: A Theoretical Study of PuC3.

    Science.gov (United States)

    Molpeceres, Germán; Rayón, Víctor M; Barrientos, Carmen; Largo, Antonio

    2016-04-14

    The most relevant species of plutonium tricarbide were characterized using theoretical methods. The global minimum is predicted to be a fan structure where the plutonium atom is bonded to a quasi-linear C3 unit. A rhombic isomer, shown to be a bicyclic species with transannular C-C bonding, lies about 39 kJ/mol above the fan isomer. A linear PuCCC isomer and a three-membered ring CPuC2 isomer were found to be higher in energy (150 and 195 kJ/mol, respectively, above the predicted global minimum). The possible processes for the formation of these species are discussed, and the IR spectra were predicted to help in possible experimental detection. The nature of the Pu-C interaction has been analyzed in terms of a topological analysis of the electronic density, showing that Pu-C bonding is essentially ionic with a certain degree of covalent character. PMID:27010701

  10. Sensitivities of five alpha continuous air monitors for detection of airborne {sup 239}Pu

    Energy Technology Data Exchange (ETDEWEB)

    McIsaac, C.V.; Amaro, C.R.

    1992-07-01

    Results of measurements of the sensitivities of five alpha continuous air monitors (CAMs) for detection of airborne {sup 239}Pu are presented. Four commercially available alpha CAMs (Kurz model 8311, Merlin Gerin Edgar, RADeCO model 452, and Victoreen model 758) and a prototype alpha CAM currently in use at Argonne National Laboratory- West (ANL-W) were tested sampling natural ambient air and laboratory-generated atmospheres laden with either blank dust or dust containing nCi/g concentrations of {sup 239}Pu. Cumulative alpha spectra were stored at 30 or 60 minute intervals during each sampling and were subsequently analyzed using three different commonly used alpha spectrum analysis algorithms. The effect of airborne dust concentration and sample filter porosity on detector resolution and sensitivity for airborne {sup 239}Pu are described.

  11. Sensitivities of five alpha continuous air monitors for detection of airborne sup 239 Pu

    Energy Technology Data Exchange (ETDEWEB)

    McIsaac, C.V.; Amaro, C.R.

    1992-07-01

    Results of measurements of the sensitivities of five alpha continuous air monitors (CAMs) for detection of airborne {sup 239}Pu are presented. Four commercially available alpha CAMs (Kurz model 8311, Merlin Gerin Edgar, RADeCO model 452, and Victoreen model 758) and a prototype alpha CAM currently in use at Argonne National Laboratory- West (ANL-W) were tested sampling natural ambient air and laboratory-generated atmospheres laden with either blank dust or dust containing nCi/g concentrations of {sup 239}Pu. Cumulative alpha spectra were stored at 30 or 60 minute intervals during each sampling and were subsequently analyzed using three different commonly used alpha spectrum analysis algorithms. The effect of airborne dust concentration and sample filter porosity on detector resolution and sensitivity for airborne {sup 239}Pu are described.

  12. Sensitivities of five alpha continuous air monitors for detection of airborne 239Pu

    International Nuclear Information System (INIS)

    Results of measurements of the sensitivities of five alpha continuous air monitors (CAMs) for detection of airborne 239Pu are presented. Four commercially available alpha CAMs (Kurz model 8311, Merlin Gerin Edgar, RADeCO model 452, and Victoreen model 758) and a prototype alpha CAM currently in use at Argonne National Laboratory- West (ANL-W) were tested sampling natural ambient air and laboratory-generated atmospheres laden with either blank dust or dust containing nCi/g concentrations of 239Pu. Cumulative alpha spectra were stored at 30 or 60 minute intervals during each sampling and were subsequently analyzed using three different commonly used alpha spectrum analysis algorithms. The effect of airborne dust concentration and sample filter porosity on detector resolution and sensitivity for airborne 239Pu are described

  13. Kzp Regulates the Transcription of gata2 and pu.1 during Primitive Hematopoiesis in Zebrafish Embryos

    Institute of Scientific and Technical Information of China (English)

    Fang Liu; Shaohua Yao; Ting Zhang; Chun Xiao; Yanna Shang; Jin Liu; Xianming Mo

    2012-01-01

    Kaiso zinc finger-containing protein (Kzp),a maternally-derived transcription factor,controls dorsoventral patterning during zebrafish gastrulation.Here,we uncovered a new function for Kzp in zebrafish embryonic primitive hematopoiesis.The depletion of kzp led to defects in primitive hematopoiesis including the development of the erythroid and myeloid lineages.On the other hand,overexpression of kzp caused the ectopic expression of gatal,gata2,and pu.1.Chromosome immunoprecipitation assays revealed that Kzp protein directly binds to gatal,gata2,and pu.1 promoters.Interestingly,the ectopic expression of gata2 was able to rescue the erythroid,but not the myeloid lineage in kzp-depleted zebrafish embryos.gatal expression controlled by Kzp was dependent on gata2 during primitive erythropoiesis.Our results indicate that Kzp is a critical transcriptional factor for the expression of gata2 and pu.1 to modulate primitive hematopoiesis.

  14. Status of irradiation testing and PIE of MOX (Pu-containing) fuel

    International Nuclear Information System (INIS)

    This paper describes AECL's mixed oxide (MOX) fuel-irradiation and post-irradiation examination (PIE) program. Post-irradiation examination results of two major irradiation experiments involving several (U, Pu)O2 fuel bundles are highlighted. One experiment involved bundles irradiated to burnups ranging fro 400 to 1200 MWh/kgHe in the Nuclear Power Demonstration (NPD) reactor. The other experiment consisted of several (U, Pu)O2 bundles irradiated to burnups of up to 500 Mwh/kgHe in the National Research Universal (NRU) reactor. Results of these experiments demonstrate the excellent performance of CANDU MOX fuel. This paper also outlines the status of current MOX fuel irradiation tests, including the irradiation of various (U, Pu)O2 bundles. The strategic importance of MOX fuel to CANDU fuel-cycle flexibility is discussed. (author)

  15. Evolving Magnetism from self damage in α and δ-Pu

    Science.gov (United States)

    McCall, Scott; Fluss, Micheal; Chung, Brandon; McElfresh, Micheal; Jackson, Damon

    2006-03-01

    As a consequence of the unusual nature of plutonium's electronic structure, point- and extended-defects are expected to, and do exhibit extraordinary properties. Low temperature magnetic susceptibility measurements on Pu and fcc-Pu(Ga) show that the magnetic susceptibility increases as a function of time, yet upon annealing the specimen returns to its initial magnetic susceptibility. This excess magnetic susceptibility (EMS) arises from the α-decay and U recoil damage cascades which produce vacancy and interstitials as point and extended defects. The time dependence of the EMS leads to an estimate of the number of atoms influenced by each α-decay, as well as a temperature dependence well described by a Curie-Weiss law. These results will be described in context of recent time dependent studies of the elastic modulus in delta Pu. Work performed under the auspices of the U.S. Department of Energy by Lawrence Livermore National Laboratory under Contract W-7405-Eng-48.

  16. Measurement of the 240Am production cross section via proton irradiation of 242Pu

    International Nuclear Information System (INIS)

    A new nuclear reaction for the production of 240Am was experimentally investigated. Targets of 150-500 μg/cm2242Pu on 2 μm Ti were produced through molecular deposition. Five irradiations, in which 242Pu, natTi, and natNi targets were jointly activated with protons from the Lawrence Berkeley National Laboratory 88-Inch Cyclotron produced 240Am, 48V, and 57Ni, respectively. The radioactive decay of these nuclides was monitored using high-purity Ge gamma ray detectors in the weeks following irradiation. A maximum 242Pu(p, 3n)240Am nuclear reaction cross section was measured to be 45 ± 13 mb with 23 MeV protons. While this value is lower than theoretical predictions, it is high enough to be the most viable nuclear reaction for the large-scale production of 240Am. (orig.)

  17. Quantitative scanning electron microscopic autoradiography of inhaled 239PuO2

    International Nuclear Information System (INIS)

    We have applied the scanning electron microscope (SEM) to obtain autoradiographs of particles of 239PuO2 deposited in rat lung. The technique was used to obtain quantitative information on the clearance rates of particles from the alveoli, bronchioles and trachea up to 240 d after exposure. At all times, the concentration of particles on the surface of the bronchioles was an order of magnitude greater than on the tracheal surface. The clearance of Pu from both regions followed a biphasic pattern, similar to that obtained by radiometric analysis of the whole lung. Most of the radiation dose to the bronchiolar epithelium originated from Pu particles in peribronchiolar alveoli in which they were preferentially retained, compared to other alveolar regions. The prolonged retention of particles in the peribronchiolar alveoli may be a significant factor in the induction of lung carcinomas

  18. Modeling and production of 240Am by deuteron-induced activation of a 240Pu target

    Energy Technology Data Exchange (ETDEWEB)

    Finn, Erin C.; McNamara, Bruce K.; Greenwood, Lawrence R.; Wittman, Richard S.; Soderquist, Chuck Z.; Woods, Vincent T.; VanDevender, Brent A.; Metz, Lori A.; Friese, Judah I.

    2015-02-01

    A novel reaction pathway for production of 240Am is reported. Models of reaction cross-sections in EMPIRE II suggests that deuteron-induced activation of a 240Pu target produces maximum yields of 240Am from 11.5 MeV incident deuterons. This activation had not been previously reported in the literature. A 240Pu target was activated under the modeled optimum conditions to produce 240Am. The modeled cross-section for the 240Pu(d, 2n)240Am reaction is on the order of 20-30 mbarn, but the experimentally estimated value is 5.3 ± 0.2 mbarn. We discuss reasons for the discrepancy as well as production of other Am isotopes that contaminate the final product.

  19. Modeling and production of 240Am by deuteron-induced activation of a 240Pu target

    International Nuclear Information System (INIS)

    A novel reaction pathway for production of 240Am is reported. Models of reaction cross-sections in EMPIRE II suggest that deuteron-induced activation of a 240Pu target produces maximum yields of 240Am from 11.5 MeV incident deuterons. This activation had not been previously reported in the literature. A 240Pu target was activated under the modeled optimum conditions to produce 240Am. The modeled cross-section for the 240Pu(d, 2n)240Am reaction is on the order of 20–30 mbarn, but the experimentally estimated value is 5.6 ± 0.2 mbarn. We discuss reasons for the discrepancy as well as production of other Am isotopes that contaminate the final product

  20. La-oxides as tracers for PuO2 to simulate contaminated aerosol behavior

    International Nuclear Information System (INIS)

    An analytical and experimental study was performed on the use of lanthanide oxides (La-oxides) as surrogates for plutonium oxides (PuO2) during simulated buried waste retrieval. This study determined how well the La-oxides move compared to PuO2 in aerosolized soils during retrieval scenarios. As part of the analytical study, physical properties of La-oxides and PuO2, such as molecular diameter, diffusivity, density, and molecular weight are compared. In addition, an experimental study was performed in which Idaho National Engineering Laboratory (INEL) soil, INEL soil with lanthanides, and INEL soil with plutonium were aerosolized and collected in filters. Comparison of particle size distribution parameters from this experimental study show similarity between INEL soil, INEL soil with lanthanides, and INEL soil with plutonium

  1. Biochemical effects of inhaled 239PuO2 on lung lipids

    International Nuclear Information System (INIS)

    Results of experiments carried out to assess the effect of 239Pu α irradiation on lung lipid biosynthesis and to determine the lungs ability to incorporate palmitate into lavage lecithin and its turnover are reported. The experiments were carried out on rats which had inhaled 239PuO2 particles. The study of palmitate incorporation into lipids shows conclusively that for medium (23 to 42 nCi) or high (more than 100 nCi) lung depositions the incorporation by isolated mitochondria is significantly (P 239PuO2 were positive, with respect to controls in 8 of 10 instances, when measured following the label of palmitate in lung lavage lecithin. The interpretation of the significant result (P < 0.05) is that: (1) initial and/or final lecithin pool sizes were different, (2) transfer rates were affected between blood and lung, or (3) rates of degradation of lung lavage lecithin were affected. (U.K.)

  2. Electronic and Magnetic Properties of Cd-Doped PuRhIn5

    Science.gov (United States)

    Zhu, Jian-Xin

    Since their discovery nearly a decade ago, plutonium-based superconductors have attracted considerable interest, which is now heightened by the latest discovery of superconductivity in other Pu-115 compounds. Within the generalized gradient approximation (GGA) of density functional theory and its combination with the dynamical mean-field theory, we present a study of electronic structure in the paramagnetic state of Cd-doped PuRhIn5. A doping-induced delocalization-localization transition is identified. In addition, the spin-polarized GGA-based total energy calculations are performed to determine the magnetic exchange interactions in the pristine PuRhIn5. The implication to the nature of quantum criticality is discussed. This work was carried out under the auspices of the National Nuclear Security Administration of the U.S. Department of Energy at LANL under Contract No. DE-AC52-06NA25396, and was supported by the LANL ASC Program.

  3. Covariances for 239Pu induced cross section in the resonance range using the CONRAD code

    International Nuclear Information System (INIS)

    This paper will present the evaluation of neutron induced cross sections covariances for the 239Pu in the resonance range. The methodology used is based on marginalization and retroactive technique to allow the treatment of experimental systematic uncertainties such as normalization. In addition, as sensitivity studies performed on iso-thermal temperature moderator analysis have demonstrated the need for improving the description of the 239Pu neutron cross sections in the sub-thermal energy range and knowing the poor accuracy of the EXFOR data below the thermal energy range, integral trends have to be taken into account in this evaluation work. The focus of the presentation is to show results obtained on the 239Pu capture and fission neutron cross sections in the resonance range with an exhaustive integral validation. (authors)

  4. 238PuO2 Fuel and Dosimetry

    Energy Technology Data Exchange (ETDEWEB)

    Mayo, Douglas R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Rawool-Sullivan, Mohini [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Garner, Scott Edward [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Wenz, Tracy R. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Karpius, Peter Joseph [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

    2016-06-01

    238Pu is an ideal material for use as a heat source with its half-life of 87.7 years and copious particle emissions. 238Pu radioisotope thermoelectric generators (RTGs) have found use for pacemakers, Apollo Space missions, Mars rovers, and Voyager spacecraft. In evaluating the dose to personnel and components near a 238Pu-based RTG, a number of additional nuclides and their daughter products must be considered to get an accurate estimate for γ-dose, and the amount of 17O and 18O for the neutron-dose must be considered. This paper looks at the contributing nuclides and their daughter products that add the most to the dose rates.

  5. Efficient PU Mode Decision and Motion Estimation for H.264/AVC to HEVC Transcoder

    Directory of Open Access Journals (Sweden)

    Zong-Yi Chen

    2014-04-01

    Full Text Available H.264/AVC has been widely applied to various applications. However, a new video compression standard, High Efficient Video Coding (HEVC, had been finalized in 2013. In this work, a fast transcoder from H.264/AVC to HEVC is proposed. The proposed algorithm includes the fast prediction unit (PU decision and the fast motion estimation. With the strong relation between H.264/AVC and HEVC, the modes, residuals, and variance of motion vectors (MVs extracted from H.264/AVC can be reused to predict the current encoding PU of HEVC. Furthermore, the MVs from H.264/AVC are used to decide the search range of PU during motion estimation. Simulation results show that the proposed algorithm can save up to 53% of the encoding time and maintains the rate-distortion (R-D performance for HEVC.

  6. A Fast PU Mode Decision Algorithm for H.264/AVC to HEVC Transcoding

    Directory of Open Access Journals (Sweden)

    Jiunn-Tsair Fang

    2014-02-01

    Full Text Available H.264/AVC has been widely applied to various applic ations. However, a new video compression standard, High Efficient Video Coding (HEVC, had b een finalized recently. In this work, a fast transcoder from H.264/AVC to HEVC is proposed. The proposed algorithm includes the fast prediction unit (PU decision and the fast motion e stimation. With the strong relation between H.264/AVC and HEVC, the motion vectors (MVs, resid uals, and modes from each coding block of H.264/AVC can be reused to predict the current e ncoding PU of HEVC. Furthermore, the MV variance from H.264/AVC is calculated to decide the search range of PU and also to reduce the prediction mode. Simulation results show that t he proposed method can save up to 53% of the encoding time and maintains the rate-distortion (R-D performance for HEVC.

  7. Sm-Nd-Pu timepieces in the Angra dos Reis meteorite

    International Nuclear Information System (INIS)

    Sm-Nd systematics in pyroxene and phosphate mineral separates of Angra dos Reis have been studied. A pyroxene-phosphate internal isochron age of T2=4.55+-0.04 AE is obtained, in excellent agreement with reported Pb-Pb ages. 142Nd/144Nd ratios in pyroxene samples are systematically larger than those in phosphates by 6 parts in 105. This variation is tentatively assigned to a radiogenic contribution from extinct 146Sm. Fission xenon components in pyroxene and phosphate separates are characterized by discrete ratios of fission/spallation and evidence is presented for a third ratio in celsian. It is shown that this characteristic is due to a close association of 244Pu with the light REE. Computed ratios 244Pu/Nd are the same in pyroxene and phosphate separates, but 244Pu/238U and 244Pu/232Th ratios are not. Taking the fission xenon retention age to be 4.55 AE, an abundance ratio 244Pu/Nd=1.5x10-4 (or an atomic ratio 244Pu/150Nd=1.6x10-3) is obtained at this time and in the region of the solar system where the Angra dos Reis parent body formed. The exposure age of Angra dos Reis, as obtained by the 81Kr-83Kr method is 55.5+-1.2 m.y. Neutron capture during the 55.5-m.y. exposure to cosmic rays increased the ratio 150Sm/149Sm in Angra dos Reis by 6 parts in 104. (Auth.)

  8. Post-irradiation examination of CANDU fuel bundles fuelled with (Th, Pu)O2

    International Nuclear Information System (INIS)

    AECL has extensive experience with thoria-based fuel irradiations as part of an ongoing R&D program on thorium within the Advanced Fuel Cycles Program. The BDL-422 experiment was one component of the thorium program that involved the fabrication and irradiation testing of six Bruce-type bundles fuelled with (Th, Pu)O2 pellets. The fuel was manufactured in the Recycle Fuel Fabrication Laboratories (RFFL) at Chalk River allowing AECL to gain valuable experience in fabrication and handling of thoria fuel. The fuel pellets contained 86.05 wt. % Th and 1.53 wt. % Pu in (Th, Pu)O2. The objectives of the BDL-422 experiment were to demonstrate the ability of 37-element geometry (Th, Pu)O2 fuel bundles to operate to high burnups up to 1000 MWh/kgHE (42 MWd/kgHE), and to examine the (Th, Pu)O2 fuel performance. This paper describes the post-irradiation examination (PIE) results of BDL-422 fuel bundles irradiated to burnups up to 856 MWh/kgHE (36 MWd/kgHE), with power ratings ranging from 52 to 67 kW/m. PIE results for the high burnup bundles (>1000 MWh/kgHE) are being analyzed and will be reported at a later date. The (Th, Pu)O2 fuel performance characteristics were superior to UO2 fuel irradiated under similar conditions. Minimal grain growth was observed and was accompanied by benign fission gas release and sheath strain. Other fuel performance parameters, such as sheath oxidation and hydrogen distribution, are also discussed. (author)

  9. Safety analysis report for the 238PuO2 fuel form facility

    International Nuclear Information System (INIS)

    The Plutonium Fuel Form (PuFF) Facility has been constructed at the Savannah River Plant to manufacture 30 to 60 kg/yr of 238Pu fuel forms for space power applications. This facility is located in the existing Building 235-F near the geographical center of the Savannah River Plant (SRP) site. Pilot production is scheduled to begin in July 1977, with full-scale production in April 1978. The process line of the facility consists of nine separate, interconnected shielded cells; five shielded wing cabinets or glove boxes; three hoods; and contained auxiliary equipment. These process enclosures will be, for the most part, under an atmosphere of recirculating inert gas. The products of the facility will be dense fuel forms manufactured from PuO2 powder with a nominal isotopic composition of 80% 238Pu-20% 239Pu. This powder, made from calcined oxalate, has been produced safely at a rate of about 20 kg 238Pu/yr in the H-Area B-Line in Building 221-H for approximately ten years. This report describes design objectives, nature of operations, potential hazards and limiting factors, facility response to postulated accidents and failures, and environmental effects. The results of the analyses described in this report indicate that the facility has the capacity to prevent or sufficiently reduce accidents that represent potential risks to health and safety. The safety analysis in conjunction with process requirements provides the bases for Technical Standards for operation. The analysis also documents the degree of conformance of the facility design with the General Design Criteria - Plutonium Facilities and the Environmental Statement

  10. Medical Care for Accidental Deposition of Plutonium (239Pu) Within the Body

    International Nuclear Information System (INIS)

    With expanding uses of plutonium chances for accidental deposition within the body are increasing. Metabolism of plutonium within the body is variable, depending on chemical composition, particle size and shape, monomeric or polymeric physical state, route of entry (inhalation,or through wounds) and many other factors. A notable exception is the negligible absorption from the gastrointestinal tract. It is difficult to determine lung deposition of poorly soluble plutonium by either bioassay or in vivo counting. The intravenous administration of the chelating agent tri-sodium calcium salt of diethylenetriamine- pentaacetic acid (DTPA), soon after an accident, is quite effective in removing soluble plutonium which has been inhaled or deposited in wounds. Conditions requiring prolonged therapy are described. Effectiveness of treatment of 239Pu body depositions is greatly influenced by the solubility of the plutonium at the site of deposition. Size, frequency and duration of dose of DTPA is recommended. Mice developed fibrosarcomas following subcutaneous injections of 0.064 μCi of 239Pu, while an employee apparently developed a pre-cancerous condition after subcutaneous deposition of only 0.005 μCi. It is our policy to recommend excision of any measurable quantity of 239Pu in a superficial wound when this may be accomplished with little hazard. The maximum permissible deposition in skin or subcutaneous tissue may be much lower than that for depositions in bone liver, lung or tracheo-bronchial lymph nodes. No limiting value has been set for depositions in wounds by any official body; The surgeon must balance the benefits to be secured against the risk of the operation. A wound bearing 239Pu should be immediately washed with DTPA, normal saline, or water, in that order of preference. Methods of removal of 239Pu from the intact skin are briefly discussed. A U.S. Plutonium Registry will assist in evaluating depositions of 239Pu and effectiveness of therapy by reconciling

  11. Variability in PuO2 Intake by Inhalation: Implications for Worker Protection at the US Department of Energy

    International Nuclear Information System (INIS)

    This paper describes the stochastic exposure (SE) paradigm where, at most, small numbers of airborne toxic particles are presented for inhalation. The focus is on alpha-emitting plutonium dioxide (PuO2) particles that may be inhaled by Department of Energy (DOE) workers. Consideration of the SE paradigm is important because intake of only a few highly radioactive PuO2 particles such as 238PuO2, could greatly exceed the annual limit on intake (ALI) used to control worker exposure. For the SE paradigm, credible intake distributions evaluated over the population at risk are needed, rather than unreliable point estimates of intake. Credible distributions of radiation doses and health risks are also needed. Because there are limited data on humans who inhaled PuO2, these distributions must be calculated. Calculated distributions are presented that relate to the intake of radioactivity via inhaling polydisperse PuO2 particles. The results indicate that a large variability in radioactivity intake is expected when relatively small numbers of PuO2 particles are inhaled. For the SE paradigm, one cannot know how many PuO2 particles were inhaled by an individual involved in a given inhalation exposure scenario. Thus, rather than addressing questions such as 'Did the calculated worker's intake of 238PuO2 exceed the ALI?', it is better to address questions such as 'What is the probability that 238PuO2 intake by a given worker occurred and exceeded the ALI?' Mathematical tools for addressing the latter question are presented, and examples of their applications are provided, with emphasis on possible DOE worker exposures at the Rocky Flats facility near Denver, Colorado. The alpha-emitting isotopes 238Pu, 239Pu, 240Pu and 242Pu are found at Rocky Flats. Although 238Pu is thought to be present in relatively small amounts there, intake via inhalation of only a few 238PuO2 particles could greatly exceed the ALI. (author)

  12. Results of 90Sr and 239+240Pu, 238Pu, 241Am measurements in some samples of mushrooms and forest soil from Poland

    International Nuclear Information System (INIS)

    Strontium-90, plutonium and americium activity concentrations in a few samples of forest soils, some species of mushrooms and fern leaves were determined. These results are compared with caesium activity concentrations in the same materials obtained in a previous work. Radiochemical procedures are described. The origin of the contamination (Chernobyl accident or nuclear test explosion release) is discussed. The 90Sr activity concentration ranges from 0.6 Bq/kg (mushroom samples) to 48.4 Bq/kg (fern leaves). For 239+240Pu, it ranges from not detected above background (mushrooms, fern) to 10.8 Bq/kg (humus layer of forest soil). The maximum concentration of 241Am is found to be 2.4 Bq/kg (humus sample) and for 238Pu it is 0.85 Bq/kg (also in the humus sample). (author). 12 refs, 9 figs, 7 tabs

  13. 90Sr and 239+240Pu 238Pu 241Am in some samples of mushrooms and forest soil from Poland

    International Nuclear Information System (INIS)

    Strontium-90, plutonium and americium activity concentrations in a few samples of forest soils, some species of mushrooms and fern leaves have been determined. These results are compared with cesium activity concentrations in the same materials obtained in a previous work. Radiochemical procedures are described. The origin of the contamination (Chernobyl accident or nuclear test explosion release) is discussed. The 90Sr activity concentration ranges from 0.6 Bq/kg (mushroom samples) to 48.4 Bq/kg (fern leaves). For 239+240Pu, it ranges from not detected above background (mushrooms, fern) to 10.8 Bq/kg (humus layer of forest soil). The maximum concentration of 241Am is found to be 2.4 Bq/kg (humus sample) and for 238Pu it is 0.85 Bq/kg (also in the humus sample). (author) 16 refs.; 7 figs.; 3 tabs

  14. Transmutation of 129I, 237Np, 238Pu, 239Pu, and 241Am using neutrons produced in target-blanket system `Energy plus Transmutation' by relativistic protons

    Indian Academy of Sciences (India)

    J Adam; K Katovsky; A Balabekyan; V G Kalinnikov; M I Krivopustov; H Kumawat; A A Solnyshkin; V I Stegailov; S G Stetsenko; V M Tsoupko-Sitnikov; W Westmeier

    2007-02-01

    Target-blanket facility `Energy + Transmutation' was irradiated by proton beam extracted from the Nuclotron Accelerator in Laboratory of High Energies of Joint Institute for Nuclear Research in Dubna, Russia. Neutrons generated by the spallation reactions of 0.7, 1.0, 1.5 and 2 GeV protons and lead target interact with subcritical uranium blanket. In the neutron field outside the blanket, radioactive iodine, neptunium, plutonium and americium samples were irradiated and transmutation reaction yields (residual nuclei production yields) have been determined using -spectroscopy. Neutron field's energy distribution has also been studied using a set of threshold detectors. Results of transmutation studies of 129I, 237Np, 238Pu, 239Pu and 241Am are presented.

  15. 242Pu as tracer for simultaneous determination of 237Np and 239,240Pu in environmental samples

    DEFF Research Database (Denmark)

    Chen, Q.J.; Dahlgaard, H.; Nielsen, S.P.;

    2002-01-01

    describes a suitable chemical procedure for Np and Pu including a quantitative pre-concentration of neptunium and plutonium, preparation of Np4+ and Pu4+, NP(NO3)(6)(2-) and Pu(NO3)(6)(2-), The ratio of Np-237/Pu-242 (or Np-237/Pu-239) before and after the procedure has been determined using 10 g soil (free...

  16. Preparation of a 238Pu standard source . II. Source preparation and standardization

    Science.gov (United States)

    Nobuo, Shinohara; Nobuaki, Kohno

    1988-07-01

    A standard source of 238Pu was prepared for calibrating the counting efficiency of alpha-ray detector. The plutonium was electrodeposited on a platinum or tantalum disk using isopropyl alcohol-hydrochloric acid solution as an electrolyte. The absolute activity was certified by isotope dilution alpha-ray spectrometry. Several types of the source, whose areas 238Pu-deposited are from 2.0 to 25.0 mm in diameter, were also prepared by the method. The overall uncertainties of the certified values for the standard sources prepared are estimated to be within 0.15 to 0.25% (1σ).

  17. Pulmonary immune response of dogs after exposure to 239PuO2

    International Nuclear Information System (INIS)

    This study evaluated the cell-mediated (CMI) and humoral immune responses in four Beagle dogs five to six years after single inhalation exposures to different monodisperse 239PuO2 aerosols (0.72-1.4μm activity median aerodynamic diameter). These exposures resulted in initial lung burdens ranging from 19 to 35kBq. The immune responses induced by lung immunization of dogs that had inhaled 239PuO2 were not suppressed by large doses of chronic alpha irradiation of the lungs and tracheobronchial lymph nodes, indicating that local pulmonary immune responses are preserved despite severe radiation-induced alteration of these tissues. (author)

  18. Microwave absorption, reflection and EMI shielding of PU-PANI composite

    Energy Technology Data Exchange (ETDEWEB)

    Lakshmi, K. [Department of Polymer Science and Rubber Technology, Cochin University of Science and Technology, Cochin 22, Kerala (India); John, Honey [Faculty of Applied Sciences, Indian Institute of Space Science and Technology, Thiruvananthapuram 22, Kerala (India); Mathew, K.T. [Department of Electronics, Cochin University of Science and Technology, Cochin University P.O., Cochin, Kerala 682022 (India)], E-mail: ktm@cusat.ac.in; Joseph, Rani; George, K.E. [Department of Polymer Science and Rubber Technology, Cochin University of Science and Technology, Cochin 22, Kerala (India)

    2009-01-15

    In order to allow electronic components to coexist without harmful electromagnetic interference (EMI) it is necessary to develop new shielding and absorbing materials with high performance and a large operating frequency band. Conducting polymer composites have been found to be suitable for EMI shielding and for the dissipation of electrostatic charge. In the present study polyaniline-polyurethane (PANI-PU) composite was considered for these applications. The microwave absorption, microwave reflection and EMI shielding properties of PANI-PU composite is evaluated both at S-band and X-band frequencies. The material is found to have good microwave absorption and is a potential candidate for EMI shielding applications.

  19. Djelovanje pušenja duhana na tvrda i meka tkiva usne šupljine

    OpenAIRE

    Brkić, Hrvoje; Keros, Jadranka; Mravak-Stipetić, Marinka; Žiger, Tihomir

    1994-01-01

    Literatura i svakodnevna kazuistika upozoravaju na štetno termičko, kemijsko i mehaničko djelovanje pušenja duhana na zdravlje. Promjene uzrokovane duhanom zahvaćaju svekoliku sluznicu dišnog, a djelomice i probavnog sustava. Svrha je našeg rada bila istražiti promjene na tvrdim i mekim tkivima usne šupljine. Istraživanjem smo obuhvatili 50 dugogodišnjih pušača cigareta obaju spolova, te 100 nepušača u usporedbenoj skupini, podjednake životne dobi. Pritom smo istraživali devet parametara rele...

  20. Transport and scavenging of Pu in surface waters of the Southern Hemisphere Oceans

    DEFF Research Database (Denmark)

    Gastaud, J.; Povinec, P.P.; Aoyama, M.;

    2011-01-01

    The distribution of 239Pu in Atlantic and Indian Ocean waters about four decades after their main injection from atmospheric nuclear weapons tests is discussed. Recent data obtained in the framework of the SHOTS (Southern Hemisphere Ocean Tracer Studies) projects are evaluated and compared with...... previous investigations. Seawater samples were collected during the round the globe BEAGLE2003 (Blue Ocean Global Expedition) along the 30°S transect in the Atlantic and the 20°S transect in the Indian Ocean. The results indicate transport of surface waters labelled with 239Pu from the western North...

  1. COMPLIANCE ANALYSIS, OPTIMISATION AND COMPARISON OF A NEW 3PUS-PU MECHANISM

    Directory of Open Access Journals (Sweden)

    B. Wei

    2013-06-01

    Full Text Available This paper investigates the compliance of a new 3PUS-PU hybrid mechanism with three degrees of freedom, including translation along the Z axis and rotations about the X and Y axes. Firstly, the kinematic analysis of the mechanism is analysed and the compliance model of the mechanism derived. Secondly, the effects the geometric parameters and position and orientation parameters on the compliance of the mechanism in each direction are investigated, and the genetic algorithm is used to optimise the global compliance by simultaneously adjusting design variables. Finally, the compliance of two similar kinds of 3PUS-PU mechanism in each direction is reviewed.

  2. Development plan of Pu NDA system using ZnS ceramic scintillator

    International Nuclear Information System (INIS)

    Alternative techniques to neutron detection by He-3 for nuclear security and safeguards systems are necessary to be developed since He-3 shortage is serious. With support of Japanese government (the Ministry of Education, Culture, Sports, and Technology), we have started an R and D project of Pu NDA system using ZnS ceramic scintillator. Here we present development plan, production of a new type of ZnS ceramic scintillator experimentally and basic design of a PCAS alternative Pu NDA system. We are planning the demonstration tests using the alternative NDA system comparing with the current PCAS in which the He-3 counters are installed. (author)

  3. Ideal Strengths and Bonding Properties of PuO2 under Tension

    Institute of Scientific and Technical Information of China (English)

    WANG Bao-Tian; MANG Ping

    2011-01-01

    We perform a first-principles computational tensile test on PuO2 based on density-functional theory within a local density approximation ( LDA )+U formalism to investigate its structural, mechanical, magnetic and intrinsic bonding properties in four representative directions: [001], [100], [110]and [111].The stress-strain relations show that the ideal tensile strengths in the four directions are 81.2, 80.5, 28.3 and 16.8GPa at strains of 0.36, 0.36,0.22 and 0.18, respectively.The [001]and [100]directions are prominently stronger than the other two directions since more Pu-O bonds participate in the pulling process.By charge and density of state analysis along the [001]direction, we find that the strong mixed ionic/covalent character of the Pu-O bond is weakened by tensile strain and PuO2 will exhibit an insulator-to-metal transition after tensile stresses exceeding about 79 GPa.%@@ We perform a first-principles computational tensile test on Pu02 based on density-functional theory within a local density approximation(LDA)+U formalism to investigate its structural, mechanical, magnetic and intrinsic bonding properties in four representative directions:[001], [100], [110] and [111].The stress-strain relations show that the ideal tensile strengths in the four directions are 81.2, 80.5, 28.3 and 16.8 GPa at strains of 0.36, 0.36,0.22 and 0.18, respectively.The [001]and [100]directions are prominently stronger than the other two directions since more Pu-0 bonds participate in the pulling process.By charge and density of state analysis along the[001]direction,we find that the strong mixed ioni%ovalent character of the Pu-0 bond is weakened by tensile strain and PuO2 will exhibit an insulator-to-metal transition after tensile stresses exceeding about 79 GPa.

  4. Validation and configuration management plan for the KE basins KE-PU spreadsheet code

    International Nuclear Information System (INIS)

    This report provides documentation of the spreadsheet KE-PU software that is used to verify compliance with the Operational Safety Requirement and Process Standard limit on the amount of plutonium in the KE-Basin sandfilter backwash pit. Included are: A summary of the verification of the method and technique used in KE-PU that were documented elsewhere, the requirements, plans, and results of validation tests that confirm the proper functioning of the software, the procedures and approvals required to make changes to the software, and the method used to maintain configuration control over the software

  5. First-principles elastic constants and phonons of delta-Pu

    DEFF Research Database (Denmark)

    Söderlind, P.; Landa, A.; Sadigh, B.;

    2004-01-01

    Elastic constants and zone-boundary phonons of delta-plutonium have been calculated within the density-functional theory. The paramagnetic state of delta-Pu is modeled by disordered magnetism utilizing either the disordered local moment or the special quasirandom structure techniques. The anomalo......Elastic constants and zone-boundary phonons of delta-plutonium have been calculated within the density-functional theory. The paramagnetic state of delta-Pu is modeled by disordered magnetism utilizing either the disordered local moment or the special quasirandom structure techniques...

  6. Effects of inhalation of 239PuO2 on immune responses following lung immunization

    International Nuclear Information System (INIS)

    Results of this study indicated that the number of antibody-forming cells in lung-associated lymph nodes after intratracheal immunization was significantly lower in animals exposed to 239PuO2. Only a few antibody-forming cells were found in spleen and cervical lymph nodes. Thus, 239PuO2 exposure suppressed immune responses in lung-associated lymph nodes, although their filtering capacity was unaffected and antigen did not translocate to the spleen. Changes in immunologic responses were observed as the animals aged and the number of antibody-forming cells gradually decreased in the lung-associated lymph nodes and increased in the spleen

  7. An isotopic analysis system for plutonium samples enriched in 238Pu

    International Nuclear Information System (INIS)

    We have designed and built a gamma-ray spectrometer system that measures the relative plutonium isotopic abundances of plutonium oxide enriched in 238Pu. The first system installed at Westinghouse Savannah River Company was tested and evaluated on plutonium oxide in stainless steel EP60/61 containers. 238Pu enrichments ranged from 20% to 85%. Results show that 200 grams of plutonium oxide in an EP60.61 container can be measured with ±0.3% precision and better than ±1.0% accuracy in the specific power using a counting time of 50 minutes. 3 refs., 2 figs

  8. Highly accurate measurements of the spontaneous fission half-life of 240,242Pu

    OpenAIRE

    SALVADOR CASTINEIRA PAULA; BRYS TOMASZ; EYKENS ROGER; Hambsch, Franz-Josef; MOENS Andre; Oberstedt, Stephan; SIBBENS Goedele; VANLEEUW DAVID; Vidali, Marzio; Pretel, C.

    2013-01-01

    Fast spectrum neutron-induced fission cross-section data for transuranic isotopes are of special demand from the nuclear data community. In particular highly accurate data are needed for the new generation IV nuclear applications. The aim is to obtain precise neutron-induced fission cross sections for 240Pu and 242Pu. To do so, accurate data on spontaneous fission half-lives must be available. Also, minimizing uncertainties in the detector efficiency is a key point. We studied both isotopes b...

  9. Effects of 239Pu administered at 9 days of gestation on hematologic development of the rat

    International Nuclear Information System (INIS)

    Injection of pregnant rats with monomeric 239Pu after 9 days of gestation decreased their leukocyte and reticulocyte counts at 5 and 10 days postexposure. Most of the fetal hematologic enumerative values were unaffected by injection of monomeric 239Pu. There was, however, a major change in the maturation of the cells of the erythroid series, as indicated by a difference in the distribution between cell types. The weight of the yolk sac and fetal liver, and the cellularity of the fetal spleen were decreased

  10. Monitoring intakes of Pu/Am by external counting. Current status in India

    International Nuclear Information System (INIS)

    This paper describes the current status of the direct methods of monitoring intakes of actinides, Pu/Am, by external counting techniques in India. It begins with the brief descriptions of the in vivo monitoring facilities established and a variety of optimised radiation detectors being operated inside the graded lined steel room chamber. Two types of phoswich detectors (200 mm dia) differing in the thicknesses of their primary detectors, are operated with pulse shape discrimination electronics based on pulse shape analyser (ORTEC model 458). The other detection systems are : 51 mm dia coaxial HPGe low energy photon spectrometer, a miniature CdTe and a twin thin NaI(Tl). Over the past several years, these facilities have been rationally utilized for conducting various types of internal monitoring programmes for workers handing Pu/Am. Due emphasis has been given to the Quality Assurance (QA) programmes and thus the accuracy of internal exposure evaluations has been ensured by participating in the international intercomparison studies. These included: a) In vivo calibration experiments based on inhalation of mock Pu i.e. polystyrene particles labelled with 103Pd - 51Cr, by human volunteers; b) Calibration measurements on Lawrence Livermore National Laboratory's (LLNL) realistic thorax phantom representing a Caucasian man, under an IAEA-CRP and c) By participating in yet another IAEA-CRP on the calibration of in vivo counting systems for actinides (Pu, Am, U, Th) using a Reference Asian phantom whose physique represented an Asian man of Japanese origin. As both, ICRP and BSS of IAEA recommend the use of latest dose coefficients, the current methodology of evaluating internal exposures to actinides (Pu/Am) is based on the new (ICRP-66) model of the human respiratory tract. For this purpose, the software package LUDEP 2.05 (Lung Dose Evaluation Program) has been standardised for routine use. The use of LUDEP 2.05 for calculating intakes and committed effective doses is

  11. Determination of U(VI) and Pu(IV) in nitric acid solutions with derivative spectroscopy

    International Nuclear Information System (INIS)

    The authors study the absorption spectra and fourth derivative spectra (FDS) of U(VI) and Pu(IV) in nitric acid solutions and the effect of impurities on FDS. The concentrations of U(VI) and Pu(IV) with peak-zero method at 415 nm and peak-area method between 472.5-479.5 nm are determined, respectively. When CHNO3 or CNO3- is in 1.5-3.0 mol/l, U(VI) can be directly determined by FDS, with the analysis deviation -4 mol/l

  12. Independent Verification of Element 114 Production in the 48Ca+242Pu Reaction

    International Nuclear Information System (INIS)

    Independent verification of the production of element 114 in the reaction of 244-MeV 48Ca with 242Pu is presented. Two chains of time- and position-correlated decays have been assigned to 286114 and 287114. The observed decay modes, half-lives, and decay energies agree with published results. The measured cross sections at a center-of-target energy of 244 MeV for the 242Pu(48Ca,3-4n)287,286114 reactions were 1.4-1.2+3.2 pb each, which are lower than the reported values.

  13. Inhalation exposure of ponies to aerosols of 169Yb-labeled 238PuO2

    International Nuclear Information System (INIS)

    Techniques and apparatus were developed for the exposure, maintenance, and profile scanning of Shetland-type ponies. Two ponies were exposed to monodisperse aerosols of 169Yb-labeled 238PuO2. One pony was maintained for 36 days after exposure, but had an abnormal lung which made projections about early distribution and translocation of 238Pu difficult. The ability to achieve substantial lung burdens of inhaled particulates and to perform meaningful linear profile scans in the pony was demonstrated. (U.S.)

  14. Effect of inhaled 239PuO2 on alveolar Type II cells

    International Nuclear Information System (INIS)

    Morphological changes of rat alveolar type II (AT-II) cells were studied at 8 and 10 months following inhalation of 239PuO2 to elucidate the biological role of AT-II cells in the induction of lung tumours. TEM micrographs of random sections of lung were analysed qualitatively and quantitatively using an automatic image analyser. Eighteen morphometric parameters were obtained according to stereological principles. The results showed that, following the inhalation of 239PuO2, AT-II cells became less differentiated and the metabolism of the pulmonary surfactant in AT-II cells was disturbed. (author)

  15. Effect of inhaled 239PuO2 on alveolar type II cells

    International Nuclear Information System (INIS)

    Morphological changes of rat alveolar type II (AT-II) cells were studied at 8 and 10 months following inhalation of 239PuO2 to elucidate the biological role of At-II cells in the induction of lung tumours. TEM micrographs of random sections of lung were analysed qualitatively and quantitatively using an automatic image analyser. Eighteen morphometric parameters were obtained according to stereo logical principles. The results showed that, following the inhalation of 239PuO2, AT-II cells became less differentiated and the metabolism of the pulmonary surfactant in AT-II cells was disturbed

  16. Narrativas sobre a experiência de ser puérpera de alto risco

    OpenAIRE

    Ariane Thaise Frello Roque; Telma Elisa Carraro

    2015-01-01

    Objetivo: Quando o puerpério ocorre concomitantemente à hospitalização do recém-nascido, leva a puérpera a tornar-se acompanhante na Unidade Neonatal, o que pode influenciar seu poder vital conceituando-se o Puerpério de Alto Risco. O objetivo deste estudo foi conhecer a experiência de ser puérpera de alto risco. Métodos: Narrativo com abordagem qualitativa, sustentado em Florence Nightingale. Realizado em uma instituição pública do sul do Brasil, de janeiro a março de 2010, foram sujeitos da...

  17. Immobilization of Pu-containing wastes into glass and ceramics: Results of US-Russia collaboration

    Science.gov (United States)

    Anderson, E. B.; Aloy, A. S.; Burakov, B. E.; Jardine, L. J.

    2000-07-01

    This continuing collaboration between the V.G. Khlopin Radium Institute (KRI) in St. Petersberg, Russia, and Lawrence Livermore National Laboratory (LLNL) in the United States was initiated in 1997. The collaboration is focused on plutonium immobilization to support the disposition of excess weapons plutonium in the US and Russia. Our work consists primarily of laboratory-scale experiments and studies of borosilicate and phosphate Pu-doped glasses and zircon/zirconia, mono-zirconia, and pyrochlore ceramics. The results were used to compare and evaluate the use of these various materials in Pu immobilization.

  18. Diffusivity of Sr, I and Pu in Granite With Through-Diffusion Experiment

    DEFF Research Database (Denmark)

    Dang, Hai-Jun; Hou, Xiaolin; Liu, Wen-yuan;

    2014-01-01

    The diffusion behavior of Sr, I and Pu in granite was investigated by through-diffusion experiment. the effective diffusion coefficients of Sr, I and Pu in granite at 26 °C were determined to be (1.24±0.03)×10-13 m2/s, (2.88±0.02)×10-13 m2/s and (1.33±0.52)×10-13 m2/s, respectively. It is also ob...

  19. Sequential determination of Pu and Am radioisotopes in environmental samples; a comparison of two separation procedures

    International Nuclear Information System (INIS)

    Two separation methods for the sequential determination of Am and Pu radionuclides are presented and the results obtained are compared. Analysis involves leaching the sample with concentrated nitric acid (HNO3), followed by radiochemical separation using extraction chromatographic resins (UTEVA, TRU) and anion exchange. Sources for alpha spectrometry were prepared by micro-precipitation on neodymium fluoride (NdF3). The chemical recoveries were determined using 242Pu and 243Am tracers. The methods were tested on reference materials and on two sediments. All the results were in good agreement with the reference values. The evaluation of uncertainty is also included

  20. Pu(V)O2+ adsorption and reduction by synthetic hematite and goethite.

    Science.gov (United States)

    Powell, Brian A; Fjeld, Robert A; Kaplan, Daniel I; Coates, John T; Serkiz, Steven M

    2005-04-01

    Changes in aqueous- and solid-phase plutonium oxidation state were monitored over time in hematite (alpha-Fe2O3) and goethite (alpha-FeOOH) suspensions containing 239Pu(V)-amended 0.01 M NaCl. Solid-phase oxidation state distribution was quantified by leaching plutonium into the aqueous phase and applying an ultrafiltration/solvent extraction technique. The technique was verified using oxidation state analogues of plutonium and sediment-free controls of known Pu oxidation state. Batch kinetic experiments were conducted at hematite and goethite concentrations between 10 and 500 m2 L(-1) in the pH range of 3-8. Surface-mediated reduction of Pu(V) was observed for both minerals at pH values of 4.5 and greater. At pH 3 no adsorption of Pu(V) was observed on either goethite or hematite; consequently, no reduction was observed. For hematite, adsorption of Pu(V) was the rate-limiting step in the adsorption/reduction process. In the pH range of 5-8, the overall removal of Pu(V) from the system (solid and aqueous phases) was found to be approximately second order with respect to hematite concentration and of order -0.39 with respect to the hydrogen ion concentration. The overall reaction rate constant (k(rxn)), including both adsorption and reduction of Pu(V), was 1.75+/-2.05 x 10(-10) (m(-2) L)(-2.08) (mol(-1) L)(-0.39) (s(-1)). In contrast to hematite, Pu(V) adsorption to goethite occurred rapidly relative to reduction. At a given pH,the reduction rate was approximately independent of the goethite concentration, although the hydrogen ion concentration (pH) had only a slight effect on the overall reaction rate. For goethite, the overall reaction rates at pH 5 and pH 8 were 6.0 x 10(-5) and 1.5 x 10(-4) s(-1), respectively. For hematite, the reaction rate increased by 3 orders of magnitude across the same pH range. PMID:15871244