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Sample records for 243am 209bi natw

  1. Preparation of tracer 239Np from 243Am

    The aim of this work is the preparation of tracer 239Np from 243Am by extraction chromatography as a separation method that can be used as a tracer to determine the radiochemical yield of 237Np in the analysis of environmental samples. (authors)

  2. Radiationless transition probabilities in muonic 209Bi

    The probability for non-radiative (n.r.) excitations in muonic 209Bi was determined from a (μ-, γγ)-measurement by comparing the intensities of muonic X-ray transitions in single and coincidence spectra. The values of Pn.r.(3p→1s)=(17.9±2.0)% and Pn.r.(3d→1s)=(3.0±2.2)% were measured for the first time. The strength of the n.r. decay of the 2p-level was found to be (4.2±2.2)%. The n.r. transition probabilities of two subcomplexes of the (2p→1s)-transition leading to different mean excitation energies are (3.2±1.8)% and (5.0±2.0)%, respectively. (orig.)

  3. Fission dynamics study in 243Am and 254Fm

    Banerjee, K.; Ghosh, T. K.; Roy, P.; Bhattacharya, S.; Chaudhuri, A.; Bhattacharya, C.; Pandey, R.; Kundu, S.; Mukherjee, G.; Rana, T. K.; Meena, J. K.; Mohanto, G.; Dubey, R.; Saneesh, N.; Sugathan, P.; Guin, R.; Das, S.; Bhattacharya, P.

    2016-06-01

    Fission fragment mass distributions in the reactions 11B + 232Th and 11B + 243Am were measured in an energy range around the barrier. No sudden change in the width of the mass distribution as a function of center-of-mass energy was observed at near-barrier energies, indicating no quasifission transition in the near-barrier energies. Interestingly, the previous measurements of fission fragment angular anisotropies for the same systems showed significant departure from the statistical saddle-point model predictions at near-barrier energies, indicating the presence of nonequilibrium fission processes.

  4. Multinucleon photonuclear reactions on {sup 209}Bi: Experiment and evaluation

    Belyshev, S.S.; Kurilik, A.S. [Lomonosov Moscow State University, Department of Physics, Moscow (Russian Federation); Filipescu, D.M.; Tesileanu, O. [Extreme Light Infrastructure - Nuclear Physics/Horia Hulubei National Institute for R and D in Physics and Nuclear Engineering, Bucharest-Magurele (Romania); Gheoghe, I. [Extreme Light Infrastructure - Nuclear Physics/Horia Hulubei National Institute for R and D in Physics and Nuclear Engineering, Bucharest-Magurele (Romania); University of Bucharest, Faculty of Physics, Bucharest-Magurele (Romania); Ishkhanov, B.S. [Lomonosov Moscow State University, Department of Physics, Moscow (Russian Federation); Skobeltsyn Institute of Nuclear Physics, Lomonosov Moscow State University, Moscow (Russian Federation); Khankin, V.V.; Kuznetsov, A.A.; Orlin, V.N.; Peskov, N.N.; Stopani, K.A.; Varlamov, V.V. [Skobeltsyn Institute of Nuclear Physics, Lomonosov Moscow State University, Moscow (Russian Federation)

    2015-06-15

    Photon activation technique using bremsstrahlug with end-point energy 55.6 MeV is used to induce photonuclear reactions in a {sup 209}Bi target. Absolute yields and integrated cross sections of multiparticle reactions (γ, 2n-6n), (γ, 4n1p), and (γ, 5n1p) are obtained. The results are compared to predictions of statistical models using systematical and microscopic description of photoabsorption and to the result of evaluation of the partial photoneutron reaction cross sections. Based on a comparison with existing experimental photoneutron cross sections and model calculations, we make a conclusion that neutron multiplicity assignment in available photoneutron cross sections on {sup 209}Bi can be corrected and evaluated cross sections of (γ, 1n) and (γ, 2n) are obtained that are in an agreement with the obtained experimental results. (orig.)

  5. Preparation and high intensity heavy ion irradiation tests of intermetallic 243Am/Pd targets

    Previously reported preparation method for Pd-based intermetallic targets (Usoltsev, et al., 2012) [1] has been successfully applied for producing two stationary 243Am/Pd targets. Both targets have been irradiated at the U-400 cyclotron at Flerov Laboratory of Nuclear Reactions Dubna (Russian Federation) using high intensity beams (up to 0.83 μApart) of 48Ca18+. Alpha-particle spectroscopy and light microscopy allowed for a comprehensive characterization of the intermetallic targets before and after irradiation. A natNd/Pd intermetallic target and a solely electroplated 243Am/Ti target were similarly investigated for comparison

  6. Evaluation and calculation of photonuclear reaction data for 209Bi below 30 MeV

    Based on available experimental data of neutron and photonuclear reaction, both neutron optical potential parameter and giant resonance parameters of gamma for 209Bi were obtained. The photonuclear reaction data for 209Bi were calculated, compared with experimental data and recommended below 30 MeV

  7. Measurements of neutron cross section of the {sup 243}Am(n,{gamma}){sup 244}Am reaction

    Hatsukawa, Yuichi; Shinohara, Nobuo; Hata, Kentaro [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1998-03-01

    The effective thermal neutron cross section of {sup 243}Am(n,{gamma}){sup 244}Am reaction was measured by the activation method. Highly-purified {sup 243}Am target was irradiated in an aluminum capsule by using a research reactor JRR-3M. The tentative effective thermal neutron cross sections are 3.92 b, and 84.44 b for the production of {sup 244g}Am and {sup 244m}Am, respectively. (author)

  8. Pion-Induced Fission of 209Bi and 119Sn:. Measurements, Calculations, Analyses and Comparison

    Rana, Mukhtar Ahmed; Sher, Gul; Manzoor, Shahid; Shehzad, M. I.

    Cross-sections for the π--induced fission of 209Bi and 119Sn have been measured using the most sensitive CR-39 solid-state nuclear track detector. In experiments, target-detector stacks were exposed to negative pions of energy 500, 672, 1068, and 1665 MeV at the Brookhaven National Laboratory, USA. An important aspect of the present paper is the comparison of pion-induced fission fragment spectra of above mentioned nuclei with the spontaneous fission fragment spectra of 252Cf. This comparison is made in terms of fission fragment track lengths in the CR-39 detectors. Measurement results are compared with calculations of Monte Carlo and statistical weight functions methods using the computer code CEM95. Agreement between measurements and calculations is fairly good for 209Bi target nuclei whereas it is indigent for the case of 119Sn. The possibilities of the trustworthy calculations, using the computer code CEM95, comparable with measurements of pion-induced fission in intermediate and heavy nuclei are explored by employing various systematics available in the code. Energy dependence of pion-induced fission in 119Sn and 209Bi is analyzed employing a newly defined parameter geometric-size-normalized fission cross-section (χfg). It is found that the collective nuclear excitations, which may lead to fission, become more probable for both 209Bi and 119Sn nuclei with increasing energy of negative pions from 500 to 1665 MeV.

  9. Measurement and analysis of the $^{243}$Am neutron capture cross section at the n_TOF facility at CERN

    Mendoza, E; Guerrero, C; Berthoumieux, E; Abbondanno, U; Aerts, G; Alvarez-Velarde, F; Andriamonje, S; Andrzejewski, J; Assimakopoulos, P; Audouin, L; Badurek, G; Balibrea, J; Baumann, P; Becvar, F; Belloni, F; Calvino, F; Calviani, M; Capote, R; Carrapico, C; Carrillo de Albornoz, A; Cennini, P; Chepel, V; Chiaveri, E; Colonna, N; Cortes, G; Couture, A; Cox, J; Dahlfors, M; David, S; Dillmann, I; Dolfini, R; Domingo-Pardo, C; Dridi, W; Duran, I; Eleftheriadis, C; Ferrant†, L; Ferrari, A; Ferreira-Marques, R; Fitzpatrick, L; Frais-Koelbl, H; Fujii, K; Furman, W; Goncalves, I; Gonz alez-Romero, E; Goverdovski, A; Gramegna, F; Griesmayer, E; Gunsing, F; Haas, B; Haight, R; Heil, M; Herrera-Martinez, A; Igashira, M; Isaev, S; Jericha, E; Kappeler, F; Kadi, Y; Karadimos, D; Karamanis, D; Ketlerov, V; Kerveno, M; Koehler, P; Konovalov, V; Kossionides, E; Krticka, M; Lampoudis, C; Leeb, H; Lindote, A; Lopes, I; Lossito, R; Lozano, M; Lukic, S; Marganiec, J; Marques, L; Marrone, S; Martınez, T; Massimi, C; Mastinu, P; Mengoni, A; Milazzo, P M; Moreau, C; Mosconi, M; Neves, F; Oberhummer, H; O’Brien, S; Oshima, M; Pancin, J; Papachristodoulou, C; Papadopoulos, C; Paradela, C; Patronis, N; Pavlik, A; Pavlopoulos, P; Perrot, L; Pigni, M T; Plag, R; Plompen, A; Plukis, A; Poch, A; Praena, J; Pretel, C; Quesada, J; Rauscher, T; Reifarth, R; Rosetti, M; Rubbia, C; Rudolf, G; Rullhusen, P; Salgado, J; Santos, C; Sarchiapone, L; Savvidis, I; Stephan, C; Tagliente, G; Tain, J L; Tassan-Got, L; Tavora, L; Terlizzi, R; Vannini, G; Vaz, P; Ventura, A; Villamarin, D; Vicente, M C; Vlachoudis, V; Vlastou, R; Voss, F; Walter, S; Wendler, H; Wiescher, M; Wisshak, K

    2014-01-01

    Background:The design of new nuclear reactors and transmutation devices requires to reduce the present neutron cross section uncertainties of minor actinides. Purpose: Reduce the $^{243}$Am(n,$\\gamma$) cross section uncertainty. Method: The $^{243}$Am(n,$\\gamma$) cross section has been measured at the n_TOF facility at CERN with a BaF$_{2}$ Total Absorption Calorimeter, in the energy range between 0.7 eV and 2.5 keV. Results: The $^{243}$Am(n,$\\gamma$) cross section has been successfully measured in the mentioned energy range. The resolved resonance region has been extended from 250 eV up to 400 eV. In the unresolved resonance region our results are compatible with one of the two incompatible capture data sets available below 2.5 keV. The data available in EXFOR and in the literature has been used to perform a simple analysis above 2.5 keV. Conclusions: The results of this measurement contribute to reduce the $^{243}$Am(n,$\\gamma$) cross section uncertainty and suggest that this cross section is underestimate...

  10. High-energy neutron transport file for the 209Bi isotope

    The simulation of the nuclear processes, occurring in media irradiated with high-energy particles, promote the elaboration of high-energy transport files. These files being used in versatile computer codes, such as MCNP, allow to simulate with high accuracy particle transport. High-energy transport files are very important for the investigation of accelerator-driven systems. The detailed description of the methods and codes used for the elaboration of the file for 209Bi is presented in this paper. (orig.)

  11. Competence of alpha spectrometry analysis algorithms used to resolve the 241Am and 243Am alpha peak overlap

    Five alpha spectrometry analysis algorithms were evaluated for their ability to resolve the 241Am and 243Am peak overlap present under typical low-level counting conditions. The major factors affecting the performance of the algorithms were identified using design-of-experiment combined with statistical analysis of the results. The study showed that the accuracy of the 241Am/243Am ratios calculated by the algorithms depends greatly on the degree of peak deformation and tailing. Despite the improved data quality obtained using an algorithm that may include peak addition and tail estimation, the accurate determination of 241Am by alpha spectrometry relies primarily on reduction of peak overlap rather than on algorithm selection

  12. Re-evaluation of neutron nuclear data for 242mAm, 243Am, 99Tc and140Ce

    The evaluated nuclear data given in JENDL-3.2 were compared with other evaluated data sets and available experimental data, for important minor actinides of 242mAm and 243Am, and fission product nuclides of 99Tc and 140Ce. Since problems were found as a result of the comparison, the data of JENDL-3.2 were improved for these nuclides. It was found that the evaluated data of Maslov et al. were superior to the others. They were adopted for 242mAm and 243Am after further improvements. For 99Tc and 140Ce, resonance parameters and optical model parameters were improved. The cross sections of these two nuclides in the smooth part were re-calculated. The present results were given in the neutron energy range from 10-5 eV to 20 MeV in the ENDF-6 format, and adopted to JENDL-3.3. (author)

  13. The influence of impurities for cross section measurement of {sup 241,243}Am(n,f) reactions

    Kai, Tetsuya; Kobayashi, Katsuhei; Yamamoto, Shuji; Fujita, Yoshiaki; Kimura, Itsuro; Miyoshi, Mitsuharu; Yamamoto, Hideki [Kyoto Univ. (Japan); Shinohara, Nobuo

    1997-03-01

    The influence of the impurities on the fission cross section measurements for {sup 241}Am and {sup 243}Am has been investigated with the practical results. Following cases have been considered as the influence of impurities; (a) experiments with the {sup 241}Am sample that contains impurities originally, and (b) experiments with the {sup 243}Am sample that contains impurities produced by {alpha}, {beta} decays after the chemical purification. The present study has demonstrated the usefulness of pure samples by the comparison of the experiments using the sample on the market with those using the pure sample processed by the authors. Particularly on the case (b), the correction of the impurity through the periodical measurements was experimentally performed (about 18% around 0.3 eV in 4 weeks after the chemical purification). (author)

  14. Neutron density distributions from antiprotonic 208Pb and 209Bi atoms

    Klos, B.; Trzcinska, A.; Jastrzebski, J.; Czosnyka, T.; Kisielinski, M.; Lubinski, P.; Napiorkowski, P.; Pienkowski, L.; Hartmann, F. J.; Ketzer, B.; Ring, P.; Schmidt, R.; von Egidy, T.; Smolanczuk, R.; S. Wycech

    2007-01-01

    The X-ray cascade from antiprotonic atoms was studied for 208Pb and 209Bi. Widths and shifts of the levels due to the strong interaction were determined. Using modern antiproton-nucleus optical potentials the neutron densities in the nuclear periphery were deduced. Assuming two parameter Fermi distributions (2pF) describing the proton and neutron densities the neutron rms radii were deduced for both nuclei. The difference of neutron and proton rms radii /\\r_np equal to 0.16 +-(0.02)_{stat} +-...

  15. Lightest Isotope of Bh Produced via the 209Bi(52Cr,n)260Bh Reaction

    The lightest isotope of Bh was produced in the new 209Bi(52Cr,n)260Bh reaction at the Lawrence Berkeley National Laboratory's 88-Inch Cyclotron. Positive identification was made by observation of eight correlated alpha particle decay chains in the focal plane detector of the Berkeley Gas-Filled Separator. 260Bh decays with a 35-9+19 ms half-life by alpha particle emission mainly by a group at 10.16 MeV. The measured cross section of 59-20+29 pb is compared to model predictions. The influence of the N=152 and Z=108 shells on alpha decay properties is discussed

  16. Precision laser spectroscopy of the ground state hyperfine splitting of hydrogenlike ^209 Bi^82+

    Klaft, Ingo; Borneis, Stefan; Engel, Thomas; Fricke, Burkhard; Grieser, Ralf; HUBER, GERHARD; Kühl, Thomas; Marx, Dieter; Neumann, Reinhard; Schröder, Sönke; Seelig, Peter; Völker, Lothar

    1994-01-01

    The first direct observation of a hyperfine splitting in the optical regime is reported. The wavelength of the M1 transition between the F = 4 and F = 5 hyperfine levels of the ground state of hydrogenlike ^209 Bi^82+ was measured to be \\lamda_0 = 243.87(4) nm by detection of laser induced fluorescence at the heavy-ion storage ring ESR at GSI. In addition, the lifetime of the laser excited F = 5 sublevel was determined to be \\tau_0 = 0.351(16) ms. The method can be applied to a number of othe...

  17. Measurements of high-energy neutron-induced fission ofnatPb and 209Bi

    Couture A.

    2010-10-01

    Full Text Available The CERN Neutron Time-Of-Flight (n_TOF facility is well suited to measure low cross sections as those of neutron-induced fission in subactinides. The cross section ratios of natPb and 209Bi relative to 235U and 238U were measured using PPAC detectors and a fragment coincidence method that allows us to identify the fission events. The present experiment provides first results for neutron-induced fission up to 1 GeV. Good agreement is found with previous experimental data below 200 MeV. The comparison with proton-induced fission indicates that the limiting regime where neutron-induced and proton-induced fission reach equal cross sections is close to 1 GeV.

  18. New data from the 243Am + 48Ca reaction give cross-bombardment verification of elements 113, 115 and 117

    The reaction 243Am + 48Ca has been reinvestigated to provide new evidence for the discovery of elements 113, 115. Twenty eight new 288115 decay chains were detected in this reaction to increase from three to 31 the number of 288115 atoms observed. In addition, four new decay chains were observed for the first time and assigned to the decay of 289115. These new 289115 events have the same properties for their decay chains as those observed for 289115 populated in the alpha decay of 293117 produced in the 249Bk + 48Ca reaction to provide cross-bombardment evidence. These new high statistics data sets and the cross-bombardment agreement provide definitive evidence for the discoveries of the new elements with Z = 113, 115, 117.

  19. Simultaneous description of CF, ICF and TF data of 6,7Li + 209Bi reaction using new ICF mode

    The systematic behavior of the fusion suppression factors and ICF probability as a function of target mass is not well understood, despite the CF experimental data being available for a number of projectile-target systems. In our recent paper, a new method was proposed to calculate the ICF probability which is based on absorption cross sections obtained from the CDCC calculations. In continuation of this work, we have also carried out similar calculations for 6,7Li + 209Bi where the experimental data of CF and ICF is available. In the recent paper by Marta et al., the semi-classical model calculations were attempted to understand CF and ICF data for 6,7Li + 209Bi, which was not explaining the data quite well. Here, we have demonstrated the use of quantum mechanical treatment for simultaneous explanation of CF, ICF and TF over a large energy range

  20. Analysis of 209 Bi and 238 U photofission cross section in the quasi-deuteron region of photonuclear absorption

    An analysis of the photofission reactions in the quasi-deuteron energy range of photonuclear absorption (∼ 30-140 MeV) has been performed for 209 Bi and 238 U nuclei. Experimental cross section data available in the literature have been compared with calculated values obtained from a model in which the incoming photon is assumed to be absorbed by a neutron-proton pair (Levinger's quasi-deuteron photoabsorption), followed by a mechanism of evaporation-fission competition for the excited residual nuclei. The model has been shown to reproduce the main experimental features of 209 Bi and 238 U photofission cross section, although unexplained differences still remain in the case of 238 U-fission by 30-50 MeV incident photons. (author). 49 refs, 10 figs, 2 tabs

  1. Fission fragment angular distributions in proton-induced fission of 209 Bi(p,t) and 197 Au(p,f)

    De, S S; N H; M. L.

    2001-01-01

      The fission fragment angular distributions have been measured for proton-induced fission of 209Bi and 197Au nuclei using surface barrier detectors at several energies between 25 MeV and 30 MeV. The experimental anisotropies are found to be in agreement with the predictions of the Standard Saddle-Point Statistical Model (SSPSM). The fission cross sections of 209Bi 197Au nuclei were also measured and compared with the previous works.

  2. Fission fragment angular distributions in proton-induced fission of 209 Bi(p,t and 197 Au(p,f

    S. S.

    2001-12-01

    Full Text Available   The fission fragment angular distributions have been measured for proton-induced fission of 209Bi and 197Au nuclei using surface barrier detectors at several energies between 25 MeV and 30 MeV. The experimental anisotropies are found to be in agreement with the predictions of the Standard Saddle-Point Statistical Model (SSPSM. The fission cross sections of 209Bi 197Au nuclei were also measured and compared with the previous works.

  3. Life time of the HFS transition in Li-like {sup 209}Bi{sup 80+}

    Geppert, C.; Noertershaeuser, W. [Institut fuer Kernchemie, Uni Mainz (Germany); GSI, Darmstadt (Germany); Hannen, V.; Joehren, R.; Ortjohann, H.W.; Vollbrecht, J.; Weinheimer, C. [Institut fuer Kernphysik, Uni Muenster (Germany); Kuehl, T. [Institut fuer Kernchemie, Uni Mainz (Germany); GSI, Darmstadt (Germany); Helmholtz Institut Jena (Germany); S' anchez, R.; Winters, D. [GSI, Darmstadt (Germany); Stoehlker, T. [Institut fuer Kernchemie, Uni Mainz (Germany); GSI, Darmstadt (Germany); Helmholtz Institut Jena (Germany); Uni Jena (Germany)

    2014-07-01

    Measuring the hyperfine splitting of heavy, highly charged ions enables tests of QED in strong fields. HFS calculations have a relative uncertainty of more than 10{sup -3} due to the distribution of the magnetic moment (Bohr-Weisskopf-Effekt). With an appropriate comparison of H- and Li-like ions this nuclear structure contribution can be suppressed. Bismuth is a suitable element for these studies, as the HFS splitting for both configurations are in a wavelength range suitable for laser spectroscopy. For this purpose the two ion species were stored in the Experimental Storage Ring at GSI at a velocity of β = 0.71. To efficiently collect the forward emitted photons a specially developed movable detector system was used. Thereby the HFS of Li-like {sup 209}Bi{sup 80+} was successfully measured for the first time. Besides the determination of the transition energy it was possible to extract the lifetime of the transition out of the collected data. The corresponding analysis and the results are presented on this poster.

  4. Life time of the HFS transition in Li-like 209Bi80+

    Measuring the hyperfine splitting of heavy, highly charged ions enables tests of QED in strong fields. HFS calculations have a relative uncertainty of more than 10-3 due to the distribution of the magnetic moment (Bohr-Weisskopf-Effekt). With an appropriate comparison of H- and Li-like ions this nuclear structure contribution can be suppressed. Bismuth is a suitable element for these studies, as the HFS splitting for both configurations are in a wavelength range suitable for laser spectroscopy. For this purpose the two ion species were stored in the Experimental Storage Ring at GSI at a velocity of β = 0.71. To efficiently collect the forward emitted photons a specially developed movable detector system was used. Thereby the HFS of Li-like 209Bi80+ was successfully measured for the first time. Besides the determination of the transition energy it was possible to extract the lifetime of the transition out of the collected data. The corresponding analysis and the results are presented on this poster.

  5. Neutron capture cross section measurements of $^{238}$U, $^{241}$Am and $^{243}$Am at n_TOF

    Koehler, P E; Plag, R

    The increase of the world energy demand and the need of low carbon energy sources have triggered the renaissance and/or enhancement of nuclear energy in many countries. Fundamental nuclear physics can contribute in a practical way to the sustainability and safety of the nuclear energy production and the management of the nuclear waste. There exists a series of recent studies which address the most relevant isotopes, decay data, nuclear reaction channels and energy ranges which have to be investigated in more detail for improving the design of different advanced nuclear systems [1] and nuclear fuel cycles [2]. In this proposal, we aim at the measurement of the neutron capture cross sections of $^{238}$U, $^{241}$Am and $^{243}$Am. All three isotopes are listed in the NEA High Priority Request List [37], are recommended for measurements [1] and play an important role in the nuclear energy production and fuel cycle scenarios. The measurements will provide as well valuable nuclear structure data necessary for the...

  6. Synthesis of element 113 in the reaction 209Bi(70Zn, n)278113

    The convincing candidate event of the isotope of the 113th element, were observed, for the first time, in the 209Bi+70Zn reaction at a beam energy of 349.0 MeV with a total dose of 1.7 x 1019. Alpha decay energies and decay times of the candidates, 278113, 274111, and 270Mt, were (11.68±0.04 MeV, 0.344 ms), (11.15±0.07 MeV, 9.26 ms), and (10.03±0.07 MeV, 7.16 ms), respectively. The production cross section of the isotope was deduced to be 55-45+150 fb(10-39 cm2). The experiment was performed at RIIKEN (The Institute of Physical and Chemical Research) Linear Accelerator (RILAC) Facility. The evaporation residues produced by the reaction with a 70Zn beam provided by the RILAC and the bismuth targets, were separated by a gas-filled recoil separator (GARIS) from the beam particles and the target recoils, and collected at the focus of GARIS. We observed an event of implantation of an evaporation residue in the position-sensitive semiconductor detector followed by four consecutive alpha decays terminated by a spontaneous fission decay. Assignment of the event was based on genetic correlation of sequential alpha decays to the already known nuclides 266Bh and 262Db. The fourth alpha decay and the following spontaneous fission decay were assigned to be the decays of 266Bh and 262Db, respectively because of agreements of decay energies and decay times with the reported values. As a consequence, the preceding three alpha decays were assigned to be ones of 278113, 274111, and 270Mt.

  7. Experimental Cross Sections for Reactions of Heavy Ions and 208Pb, 209Bi, 238U, and 248Cm Targets

    The study of the reactions between heavy ions and 208Pb, 209Bi, 238U, and 248 Cm targets was performed to look at the differences between the cross sections of hot and cold fusion reactions. Experimental cross sections were compared with predictions from statistical computer codes to evaluate the effectiveness of the computer code in predicting production cross sections. Hot fusion reactions were studied with the MG system, catcher foil techniques and the Berkeley Gas-filled Separator (BGS). 3n- and 4n-exit channel production cross sections were obtained for the 238U(18O,xn)256-xFm, 238U(22Ne,xn)260-xNo, and 248Cm(15N,xn)263-xLr reactions and are similar to previous experimental results. The experimental cross sections were accurately modeled by the predictions of the HIVAP code using the Reisdorf and Schaedel parameters and are consistent with the existing systematics of 4n exit channel reaction products. Cold fusion reactions were examined using the BGS. The 208Pb(48Ca,xn)256-xNo, 208Pb(50Ti,xn)258-xRf, 208Pb(51V,xn)259-xDb, 209Bi(50Ti,xn)259-xDb, and 209Bi(51V,xn)260-xSg reactions were studied. The experimental production cross sections are in agreement with the results observed in previous experiments. It was necessary to slightly alter the Reisdorf and Schaedel parameters for use in the HIVAP code in order to more accurately model the experimental data. The cold fusion experimental results are in agreement with current 1n- and 2n-exit channel systematics

  8. Experimental Cross Sections for Reactions of Heavy Ions and 208Pb, 209Bi, 238U, and 248Cm Targets

    Patin, Joshua B.

    2002-05-24

    The study of the reactions between heavy ions and {sup 208}Pb, {sup 209}Bi, {sup 238}U, and {sup 248} Cm targets was performed to look at the differences between the cross sections of hot and cold fusion reactions. Experimental cross sections were compared with predictions from statistical computer codes to evaluate the effectiveness of the computer code in predicting production cross sections. Hot fusion reactions were studied with the MG system, catcher foil techniques and the Berkeley Gas-filled Separator (BGS). 3n- and 4n-exit channel production cross sections were obtained for the {sup 238}U({sup 18}O,xn){sup 256-x}Fm, {sup 238}U({sup 22}Ne,xn){sup 260-x}No, and {sup 248}Cm({sup 15}N,xn){sup 263-x}Lr reactions and are similar to previous experimental results. The experimental cross sections were accurately modeled by the predictions of the HIVAP code using the Reisdorf and Schaedel parameters and are consistent with the existing systematics of 4n exit channel reaction products. Cold fusion reactions were examined using the BGS. The {sup 208}Pb({sup 48}Ca,xn){sup 256-x}No, {sup 208}Pb({sup 50}Ti,xn){sup 258-x}Rf, {sup 208}Pb({sup 51}V,xn){sup 259-x}Db, {sup 209}Bi({sup 50}Ti,xn){sup 259-x}Db, and {sup 209}Bi({sup 51}V,xn){sup 260-x}Sg reactions were studied. The experimental production cross sections are in agreement with the results observed in previous experiments. It was necessary to slightly alter the Reisdorf and Schaedel parameters for use in the HIVAP code in order to more accurately model the experimental data. The cold fusion experimental results are in agreement with current 1n- and 2n-exit channel systematics.

  9. Determination of the {sup 209}Bi(n,{gamma}){sup 210}Bi and {sup 209}Bi(n,{gamma}){sup 210m,g}Bi reaction cross sections in a cold neutron beam

    Borella, A. [European Commission, Joint Research Centre, Institute for Reference Materials and Measurements, B-2440 Geel (Belgium); SCK-CEN, Boeretang 200, B-2400 Mol (Belgium); Belgya, T. [Institute of Isotope, Hungarian Academy of Sciences, POB 77, H-1525 Budapest (Hungary); Kopecky, S. [European Commission, Joint Research Centre, Institute for Reference Materials and Measurements, B-2440 Geel (Belgium); Gunsing, F. [CEA/Saclay, DSM/Irfu, F-91191 Gif-sur-Yvette (France); Moxon, M. [Hyde Copse 3, Marcham (United Kingdom); Rejmund, M. [GANIL, F-14076 Caen (France); Schillebeeckx, P., E-mail: peter.schillebeeckx@ec.europa.e [European Commission, Joint Research Centre, Institute for Reference Materials and Measurements, B-2440 Geel (Belgium); Szentmiklosi, L. [Institute of Isotope, Hungarian Academy of Sciences, POB 77, H-1525 Budapest (Hungary)

    2011-01-15

    Gamma-ray transitions following neutron capture in {sup 209}Bi have been studied at the cold neutron beam facility of the Budapest Neutron Centre. Measurements have been performed using a coaxial HPGe detector with Compton suppression. Partial capture cross sections at a velocity of 2200 m/s (or a neutron energy of 25.3 meV) have been deduced relatively to the one for the 4055 keV transition after thermal neutron capture in {sup 209}Bi. This partial cross section of (8.07 {+-} 0.14) mb has in turn been obtained from measurements with a bismuth nitrate target relatively to the cross section for the 1884 keV transition after thermal neutron capture in {sup 14}N. Shell model calculations have been performed to deduce the half-life of the 3rd excited state at 320 keV and to assign the M1 multipolarity of the 320 keV transition to the ground state. Lower limits of (21.4 {+-} 0.8) mb and (18.2 {+-} 0.7) mb for the cross sections to the ground state and to the isomeric state, respectively, have been deduced from the data for the gamma rays feeding these states. The results obtained in this work are in good agreement with experimental data reported in the literature. The thermal total capture cross section has been compared with the contribution due to observed s-wave resonances.

  10. Measurement of cross sections of the 210Po production reaction by keV-neutron capture of 209Bi

    The cross sections of the 209Bi(n, γ)210gBi reaction were measured in the keV-neutron region, using an activation method with the detection of α rays from 210Po. Pulsed keV neutrons were generated from the 7Li(p, n)7Be reaction by a 1.5-ns bunched proton beam from the 3-MV Pelletron accelerator of the Research Laboratory for Nuclear Reactors at the Tokyo Institute of Technology. The 209Bi samples were metallic bismuth evaporated on a gold backing. After sample irradiation, the 412-keV γrays from the gold backing were measured with on HPGe detector, and then the α rays from 210Po nuclei in the bismuth sample were measured with a Si surface barrier detector. The derived cross sections were 1.9±0.4 mb and 0.62±0.14 mb at the average neutron energies of 30 keV and 534 keV, respectively. The present value at 30 keV is in agreement with the previous measurement at 24 keV of Booth et al., but about a quarter of the evaluation of JENDL Activation cross section File. The present result at 534 keV is the first experimental one around 500 keV, and is about a half of the evaluation of JENDL Activation cross section File. (author)

  11. Measurement of the neutron-induced fission cross-section of 243Am relative to 235U from 0.5 to 20 MeV

    The ratio of the neutron-induced fission cross-sections of 243Am and 235U was measured in the energy range from 0.5 to 20 MeV with uncertainties of ∼ 4%. The experiment was performed at the CERN nTOF facility using a fast ionization chamber. With the good counting statistics that could be achieved thanks to the high instantaneous flux and the low backgrounds, the present results are useful for resolving discrepancies in previous data sets and are important for future reactors with improved fuel burn-up. (orig.)

  12. Measurement of the neutron-induced fission cross-section of {sup 243}Am relative to {sup 235}U from 0.5 to 20 MeV

    Belloni, F.; Milazzo, P.M.; Abbondanno, U.; Fujii, K.; Moreau, C. [Istituto Nazionale di Fisica Nucleare, Trieste (Italy); Calviani, M. [Laboratori Nazionali di Legnaro, Istituto Nazionale di Fisica Nucleare, Legnaro (Italy); CERN, Geneva (Switzerland); Colonna, N.; Barbagallo, M.; Marrone, S.; Meaze, M.H.; Tagliente, G.; Terlizzi, R. [Istituto Nazionale di Fisica Nucleare, Bari (Italy); Mastinu, P.; Gramegna, F. [Lab. Nazionali di Legnaro, Istituto Nazionale di Fisica Nucleare, Legnaro (Italy); Aerts, G.; Andriamonje, S.; Berthoumieux, E.; Dridi, W.; Gunsing, F.; Pancin, J.; Perrot, L.; Plukis, A. [Irfu, CEA, Gif-sur-Yvette (France); Alvarez, H.; Cano-Ott, D.; Duran, I.; Embid-Segura, M.; Gonzalez-Romero, E.; Paradela, C.; Tarrio, D. [Univ. de Santiago de Compostela, Galicia (Spain); Alvarez-Velarde, F.; Guerrero, C.; Martinez, T.; Villamarin, D.; Vincente, M.C. [Centro de Investigaciones Energeticas Medioambientales y Technologicas, Madrid (Spain); Andrzejewski, J.; Marganiec, J. [Univ. of Lodz (Poland); Audouin, L.; Dillmann, I.; Heil, M.; Kaeppeler, F.; Mosconi, M.; Plag, R.; Voss, F.; Walter, S.; Wisshak, K. [Karlsruhe Inst. of Technology, Eggenstein-Leopoldshafen (Germany). Inst. fuer Kernphysik; Badurek, G.; Jericha, E.; Leeb, H.; Oberhummer, H. [Technische Univ. Wien, Atominstitut der Oesterreichischen Universitaeten, Wien (Austria); Baumann, P.; David, S.; Kerveno, M.; Lukic, S.; Rudolf, G. [IReS, Centre National de la Recherche Scientifique/IN2P3, Strasbourg (France); Becvar, F.; Krticka, M. [Charles Univ., Faculty of Mathematics and Physics, Prague (Czech Republic); Calvino, F.; Cortes, G.; Poch, A.; Pretel, C. [Univ. Politecnica de Catalunya, Barcelona (Spain); Capote, R. [NAPC/Nuclear Data Section, International Atomic Energy Agency, Vienna (Austria); Univ. de Sevilla (Spain); Carrapico, C.; Goncalves, I.; Salgado, J.; Santos, C.; Tavora, L.; Vaz, P. [Inst. Tecnologico e Nuclear, Lisbon (Portugal)] [and others

    2011-12-15

    The ratio of the neutron-induced fission cross-sections of {sup 243}Am and {sup 235}U was measured in the energy range from 0.5 to 20 MeV with uncertainties of {approx} 4%. The experiment was performed at the CERN n{sub T}OF facility using a fast ionization chamber. With the good counting statistics that could be achieved thanks to the high instantaneous flux and the low backgrounds, the present results are useful for resolving discrepancies in previous data sets and are important for future reactors with improved fuel burn-up. (orig.)

  13. Neutron-induced fission cross sections of 233U and 243Am in the energy range 0.5 Mev En 20 MeV @ n_TOF

    Belloni, F; Milazzo, P M; Calviani, M; Colonna, N; Mastinu, P; Abbondanno, U; Aerts, G; Álvarez, H; Álvarez-Velarde, F; Andriamonje, S; Andrzejewski, J; Assimakopoulos, P; Audouin, L; Badurek, G; Baumann, P; Becvár, F; Berthoumieux, E; Calviño, F; Cano-Ott, D; Capote, R; Carrapiço, C; Cennini, P; Chepel, V; Chiaveri, E; Cortes, G; Couture, A; Cox, J; Dahlfors, M; David, S; Dillmann, I; Domingo-Pardo, C; Dridi, W; Duran, I; Eleftheriadis, C; Embid-Segura, M; Ferrant, L; Ferrari, A; Ferreira-Marques, R; Fujii, K; Furman, W; Goncalves, I; González-Romero, E; Gramegna, F; Guerrero, C; Gunsing, F; Haas, B; Haight, R; Heil, M; Herrera-Martinez, A; Igashira, M; Jericha, E; Käppeler, F; Kadi, Y; Karadimos, D; Karamanis, D; Kerveno, M; Koehler, P; Kossionides, E; Krticka, M; Lampoudis, C; Leeb, H; Lindote, A; Lopes, I; Lozano, M; Lukic, S; Marganiec, J; Marrone, S; Martínez, T; Massimi, C; Mengoni, A; Moreau, C; Mosconi, M; Neves, F; Oberhummer, H; O'Brien, S; Pancin, J; Papachristodoulou, C; Papadopoulos, C; Paradela, C; Patronis, N; Pavlik, A; Pavlopoulos, P; Perrot, L; Pigni, M T; Plag, R; Plompen, A; Plukis, A; Poch, A; Praena, J; Pretel, C; Quesada, J; Rauscher, T; Reifarth, R; Rubbia, C; Rudolf, G; Rullhusen, P; Salgado, J; Santos, C; Sarchiapone, L; Savvidis, I; Stephan, C; Tagliente, G; Tain, J L; Tassan-Got, L; Tavora, L; Terlizzi, R; Vannini, G; Vazl, P; Ventura, A; Villamarin, D; Vincente, M C; Vlachoudis, V; Vlastou, R; Voss, F; Walter, S; Wiescher, M; Wisshak, K

    2011-01-01

    Neutron-induced fission cross-sections of actinides have been recently measured at the neutron time of flight facility n_TOF at CERN in the frame of a research project involving isotopes relevant for nuclear astrophysics and nuclear technologies. Fission fragments are detected by a gas counter with good discrimination between nuclear fission products and background events. Neutron-induced fission cross-sections of 233U and 243Am were determined relative to 235U. The present paper reports the results obtained at neutron energies between 0.5 and 20 MeV.

  14. The use of isotopic correlation technique for determination of sup(241)Am and sup(243)Am concentration in nuclear irradiated fuels

    In the last years the isotopic correlation technique is emerging as a powerful tool for the determination of concentration and isotopic composition of heavy nuclides in the nuclear fuel cycle. Accordingly, this technique has gained significant importance for the safeguard of the nuclear materials as well as for the accounting and build up of actinides elements in the irradiated nuclear fuels. In this work 42 isotopic correlations between the nuclides sup(241)Am and sup(243)Am and post irradiation isotopic data of 7 samples from fuel element BE-124 and 1 sample from fuel element BE-120 from the Obrigheim pressurized water nuclear power reactor, Federal Republic of Germany, were proposed. These isotopic correlations allowed to estimate the isotopic concentrations of sup(241)Am and sup(243)Am with an average deviation, relative to the experimental data obtained from isotopic dilution mass spectrometry technique, of 10%. These results are more precise than those found using the computer code ORIGEN 2 demonstrating the great potential of this technique for the determination of isotopic concentration and build up of those nuclides in irradiated nuclear fuels. The analytical and other experimental aspects of the post irradiation isotopic analysis of nuclear fuels are also discussed. (author)

  15. Thermal neutron capture cross-section measurements of 243Am and 242Pu using the new mini-INCA α- and γ-spectroscopy station

    In the framework of the Mini-INCA project, dedicated to the study of Minor Actinide transmutation process in high neutron fluxes, an α- and γ-spectroscopy station has been developed and installed at the High Flux Reactor of the Laue-Langevin Institut. This set-up allows short irradiations as well as long irradiations in a high quasi-thermal neutron flux and post-irradiation spectroscopy analysis. It is well suited to measure precisely, in reference to 59Co cross-section, neutron capture cross-sections, for all the actinides, in the thermal energy region. The first measurements using this set-up were done on 243Am and 242Pu isotopes. Cross-section values, at En=0.025eV, were found to be (81.8+/-3.6)b for 243Am and (22.5+/-1.1)b for 242Pu. These values differ from evaluated data libraries by a factor of 9% and 17%, respectively, but are compatible with the most recent measurements, validating by the way the experimental apparatus

  16. Comparative study of fusion barrier distribution in 16O and 18O induced reactions on 232Th and 209Bi targets

    In order to investigate the influence of projectile excitations and transfer channels, quasi-elastic excitation function measurements with 16,18O projectile on two targets, one heavy (232Th) and the other a lighter target (209Bi) at energies around their Coulomb barrier are investigated. The results are compared with a new CC code CCFULL

  17. Fission Cross Sections of {209}Bi, {232}Th, {235}U, {238}U and {237}Np for Intermediate Energy Protons and Deuterons

    Yurevich, V I; Yakovlev, R M; Sosnin, A N

    2001-01-01

    Fission cross sections of {209}Bi, {232}Th, {235}U, {238}U and {237}Np have been measured with 1.0-3.7 GeV protons and 1.0 GeV deuterons. The results are compared with other experimental data, available evaluations and predictions of the theoretical model.

  18. Lightest Isotope of Bh Produced Via the 209Bi(52Cr,n)260BhReaction

    Nelson, Sarah L.; Gregorich, Kenneth E.; Dragojevic, Irena; Garcia, Mitch A.; Gates, Jacklyn M.; Sudowe, Ralf; Nitsche, Heino

    2007-05-07

    The lightest isotope of Bh known was produced in the new {sup 209}Bi({sup 52}Cr,n){sup 260}Bh reaction at the Lawrence Berkeley National Laboratory's 88-Inch Cyclotron. Positive identification was made by observation of eight correlated alpha particle decay chains in the focal plane detector of the Berkeley Gas-Filled Separator. {sup 260}Bh decays with a 35{sub -9}{sup +19} ms half-life by alpha particle emission mainly by a group at 10.16 MeV. The measured cross section of 59{sub -20}{sup +29} pb is approximately a factor of four larger than compared to recent model predictions. The influences of the N = 152 and Z = 108 shells on alpha decay properties are discussed.

  19. Complete and incomplete fusion cross sections for 6Li+209Bi reaction in multi-body classical molecular dynamical model

    Using the multi-body Classical Molecular Dynamics simulation of 6Li+209Bi reaction it is shown that: (i) the breakup of a projectile fragment near the barrier leads to substantial increase in the ICF probabilities; (ii) the expected increase in σCF on relaxation of the rigid-body (RB) constraint on the projectile is compensated by reduction in the flux leading to CF, due to ICF events; (iii) the breakup probability increases with ECM and, for given ECM it also increases as b increases and peaks around some b>0, while cross sections σCF and σTF were calculated for b=0 only Therefore, we present the results of σCF (Complete Fusion) and σTF (Total Fusion) calculations which are obtained at critical impact parameter, bcr, where many ICF channels open up and compare with the calculations performed at b=0 only, where only few ICF channels open up

  20. Study of viscosity on the fission dynamics of the excited nuclei 228U produced in 19F + 209Bi reactions

    A two-dimensional (2D) dynamical model based on Langevin equations was applied to study the fission dynamics of the compound nuclei 228U produced in 19F + 209Bi reactions at intermediate excitation energies. The distance between the centers of masses of the future fission fragments was used as the first dimension and the projection of the total spin of the compound nucleus onto the symmetry axis, K, was considered as the second dimension in Langevin dynamical calculations. The magnitude of post-saddle friction strength was inferred by fitting measured data on the average pre-scission neutron multiplicity for 228U. It was shown that the results of calculations are in good agreement with the experimental data by using values of the post-saddle friction equal to 6–8 × 1021s-1. (author)

  1. Extended optical model analyses for the 11B+209Bi system at near-Coulomb-barrier energies

    In the framework of an extended optical model approach in which the polarization potential is decomposed into direct-reaction (DR) and fusion parts, simultaneous χ2 analyses of elastic scattering and fusion cross-section data for the 11B+209Bi system at near-Coulomb-barrier energies are performed. We show that the DR and fusion potentials extracted from χ2 analyses separately satisfy the dispersion relation and that the threshold anomaly exhibits in both DR and fusion parts. We find that the analyses using only elastic scattering and fusion data can produce reliable predictions of cross-sections even though the direct reaction cross-section data are not complete. By using the extracted DR potential, we investigate the effects of the projectile breakup on fusion cross-sections. (orig.)

  2. Fission Cross-section Measurements of (233)U, (245)Cm and (241,243)Am at CERN n_TOF Facility

    Calviani, M; Andriamonje, S; Chiaveri, E; Vlachoudis, V; Colonna, N; Meaze, M H; Marrone, S; Tagliente, G; Terlizzi, R; Belloni, F; Abbondanno, U; Fujii, K; Milazzo, P M; Moreau, C; Aerts, G; Berthoumieux, E; Dridi, W; Gunsing, F; Pancin, J; Perrot, L; Plukis, A; Alvarez, H; Duran, I; Paradela, C; Alvarez-Velarde, F; Cano-Ott, D; Gonzalez-Romero, E; Guerrero, C; Martinez, T; Villamarin, D; Vicente, M C; Andrzejewski, J; Marganiec, J; Assimakopoulos, P; Karadimos, D; Karamanis, D; Papachristodoulou, C; Patronis, N; Audouin, L; David, S; Ferrant, L; Isaev, S; Stephan, C; Tassan-Got, L; Badurek, G; Jericha, E; Leeb, H; Oberhummer, H; Pigni, M T; Baumann, P; Kerveno, M; Lukic, S; Rudolf, G; Becvar, F; Krticka, M; Calvino, F; Capote, R; Carrillo De Albornoz, A; Marques, L; Salgado, J; Tavora, L; Vaz, P; Cennini, P; Dahlfors, M; Ferrari, A; Gramegna, F; Herrera-Martinez, A; Kadi, Y; Mastinu, P; Praena, J; Sarchiapone, L; Wendler, H; Chepel, V; Ferreira-Marques, R; Goncalves, I; Lindote, A; Lopes, I; Neves, F; Cortes, G; Poch, A; Pretel, C; Couture, A; Cox, J; O'brien, S; Wiescher, M; Dillman, I; Heil, M; Kappeler, F; Mosconi, M; Plag, R; Voss, F; Walter, S; Wisshak, K; Dolfini, R; Rubbia, C; Domingo-Pardo, C; Tain, J L; Eleftheriadis, C; Savvidis, I; Frais-Koelbl, H; Griesmayer, E; Furman, W; Konovalov, V; Goverdovski, A; Ketlerov, V; Haas, B; Haight, R; Reifarth, R; Igashira, M; Koehler, P; Kossionides, E; Lampoudis, C; Lozano, M; Quesada, J; Massimi, C; Vannini, G; Mengoni, A; Oshima, M; Papadopoulos, C; Vlastou, R; Pavlik, A; Pavlopoulos, P; Plompen, A; Rullhusen, P; Rauscher, T; Rosetti, M; Ventura, A

    2011-01-01

    Neutron-induced fission cross-sections of minor actinides have been measured using the n_TOF white neutron source at CERN, Geneva, as part of a large experimental program aiming at collecting new data relevant for nuclear astrophysics and for the design of advanced reactor systems. The measurements at n_TOF take advantage of the innovative features of the n_TOF facility, namely the wide energy range, high instantaneous neutron flux and good energy resolution. Final results on the fission cross-section of 233U, 245Cm and 243Am from thermal to 20 MeV are here reported, together with preliminary results for 241Am. The measurement have been performed with a dedicated Fast Ionization Chamber (FIC), a fission fragment detector with a very high efficiency, relative to the very well known cross-section of 235U, measured simultaneously with the same detector.

  3. Calculations of Branching Ratios for Radiative-Capture, One-Proton, and Two-Neutron Channels in the Fusion Reaction $^{209}$Bi+$^{70}$Zn

    Ichikawa, Takatoshi; 10.1143/JPSJ.79.074201

    2010-01-01

    We discuss the possibility of the non-one-neutron emission channels in the cold fusion reaction $^{70}$Zn + $^{209}$Bi to produce the element Z=113. For this purpose, we calculate the evaporation-residue cross sections of one-proton, radiative-capture, and two-neutron emissions relative to the one-neutron emission in the reaction $^{70}$Zn + $^{209}$Bi. To estimate the upper bounds of those quantities, we vary model parameters in the calculations, such as the level-density parameter and the height of the fission barrier. We conclude that the highest possibility is for the 2n reaction channel, and its upper bounds are 2.4$%$ and at most less than 7.9% with unrealistic parameter values, under the actual experimental conditions of [J. Phys. Soc. Jpn. {\\bf 73} (2004) 2593].

  4. Interaction at the barrier in the systems 9,10,11Be+209Bi: Well-established facts and open questions

    The experimental data relative to the interaction for the systems 9,10,11Be+209Bi at the Coulomb barrier are critically discussed and compared also with present theories. The break-up (BU) of the two loosely bound projectiles, 9,11Be, seems to influence the fusion process by ''hindering'' the fusion cross-sections; but, contrary to expectations, the 11Be halo structure has no influence, since no ''enhancement'' is evident from the existing data. Attempt to describe simultaneously all the 9Be+209Bi system data: fusion, elastic scattering and BU, within a coupled-channel (CC) approach is only partly successful. It is important, from a theoretical viewpoint, to include in the CC formalism as well as possible the BU process both to continuum states as well as to unbound resonances. More accurate and well-focused experiments are also necessary to pin down this problem. (orig.)

  5. Calculations of branching ratios for radiative-capture, one-proton, and two-neutron channels in the fusion reaction 209Bi+70Zn

    We discuss the possibility of the non-one-neutron emission channels in the cold fusion reaction 70Zn+209Bi to produce the element Z=113. For this purpose, we calculate the evaporation-residue cross sections of one-proton, radiative-capture, and two-neutron emissions relative to the one-neutron emission in the reaction 70Zn+209Bi. To estimate the upper bounds of those quantities, we vary model parameters in the calculations, such as the level-density parameter and the height of the fission barrier. We conclude that the highest possibility is for the 2n reaction channel, and its upper bounds are 2.4% and at most less than 7.9% with unrealistic parameter values, under the actual experimental conditions of [J.Phys.Soc.Jpn.73(2004)2593]. (author)

  6. Breakup of 9Be on 209Bi above and near the Coulomb barrier as a molecular single-particle effect: Its influence on complete fusion and scattering

    The breakup of the 9Be projectile on the 209Bi target at bombarding energies above and near the Coulomb barrier is studied in the adiabatic two-center shell model approach. The effect of 9Be→n+2α breakup channel on complete fusion, elastic and inelastic cross sections is investigated. Results show that the breakup of the projectile 9Be could be due to a molecular single-particle effect shortly before the colliding nuclei reach the Coulomb barrier

  7. Cross Sections of the (HI, αn) Channel in the Cold-Fusion-Type Reactions 209 Bi + 40 Ar and 208 Pb + 37 Cl

    By using an off-line radiochemistry technique, production cross sections of 240 Cm(T1/2 = 27 d) in the 209 Bi + 40 Ar and 208 Pb + 37 Cl reactions at the bombarding energy Elab ≤ 230 MeV were determined to be 0,5 ± 0,2 and 0,6 ± 0,3 n b, respectively. The production of 240 Cm was attributed to the 1 n-deexcitation channel of the composite systems 249 Md and 245 Es. The measured 240 Cm production cross sections represent upper cross section limits for the (HI, αn) channel of the reactions under study, which limits are about 100 times lower than the section values reported by Nomura et al. for the (40 Ar, αx n) channels with x = 1,2 of the 209 Bi + 40 Ar reaction at Elab208 MeV. In this connection, presented and discussed is an up-to-date summary of the available data on cross sections of the (HI, αx n) channels in the cold-fusion-type reactions induced by projectiles 37 Cl to 50 Ti on targets of 203,205 Tl, 208 Pb and 209 Bi. Appreciable E C(β+)-delayed fission effects were detected in the 209 Bi + 40 Ar and 206,208 Pb + 37 Cl reactions. In particular, our data reveal the occurrence of E C(β+)-delayed fission in the decay chains 242 Es(E C, ∼7 s) 242 Cf and 238 Bk(E C, ∼2 m) 238 Cm. 28 refs., 4 figs., 4 tabs

  8. Towards measurement of the 209Bi(n,γ)210m,gBi cross sections at SARAF

    The Main Incentives For This Work Is To Exploit The Large Proton Currents And High Neutron Flux Capabilities At The Soreq Applied Research Accelerator Facility (Saraf)Along Witha Liquid Lithium Target To Perform Sensitive Measurements Of Interest In Reactor Design And Safety. The First Measurement To Be Performed Is Neutron Activation Of209bi. This Measurement Is Important For Proposed Pb-Bi Eutectic Coolants For Gen Iv Reactors And For Targets For Accelerator Driven Systems (Ads). The Activity Of One Of The Reaction Products,210mbi, Is Very Difficult To Measure Because Of Long Half-Life (3 Million Years). Successful Measurements And Comparison With The Activation Of 210gbi (The 210bi Ground State) Requires High Neutron Flux And Very Sensitive Measurements. We Plan To Perform The Activation Using The 30 Kevmaxwellianlike Neutron Spectrum Produced By The 7li(P,N)7be Reaction Near Threshold. Subsequent To The Activation, The Plan Is To Measure Directly The γ-Decays From The Decay Products,206tl For The 210mbiand 206pb For The 210gbi Activation, In The Underground Laboratory Hades At Sck-Cen In Mol, Belgium.Level Diagram And Previous Measurements Of This Ratio Are Shown . This Reaction Is Also Of Significance For Nuclear Astrophysics Since It Is The End Of The Chain For S-Process For Nucleo-Synthesis In Heavy Stars, With The Maxwellianneutrons Mimicking Environment In Asymptotic Giant Branch (Agb) Stars

  9. Study of the di-nuclear system $^{A}$Rb + $^{209}$Bi (Z$_{1}$ + Z$_{2}$ = 120)

    The exact location of the next spherical shell closures beyond Z = 82, N = 126 is still an open question. According to model predictions shell closures are expected at Z = 114 or 120 or 126 and N = 184. Also experimental data cannot yet give a definite answer. Known nuclei with Z = 114 are too neutron‐deficient with respect to the N = 184 shell and nuclei with Z = 120 and beyond are still unknown. An option for studying reactions of super-heavy systems at Z = 120 and neutron numbers up to 184 becomes possible with the use of $^{209}$Bi targets and neutron‐rich beams. By studying quasi-fission and fusion‐fission reactions, which have significantly larger production cross‐sections than the evaporation residues, a possible influence of shell closures at Z = 120, N = 184 can be explored. Well suitable for such studies will be neutron‐rich rubidium beams at energies of about 5 MeV/u delivered by the HIE‐ISOLDE facility.

  10. Fission cross section calculations for 209Bi target nucleus based on fission reaction models in high energy regions

    Kaplan Abdullah

    2015-01-01

    Full Text Available Implementation of projects of new generation nuclear power plants requires the solving of material science and technological issues in developing of reactor materials. Melts of heavy metals (Pb, Bi and Pb-Bi due to their nuclear and thermophysical properties, are the candidate coolants for fast reactors and accelerator-driven systems (ADS. In this study, α, γ, p, n and 3He induced fission cross section calculations for 209Bi target nucleus at high-energy regions for (α,f, (γ,f, (p,f, (n,f and (3He,f reactions have been investigated using different fission reaction models. Mamdouh Table, Sierk, Rotating Liquid Drop and Fission Path models of theoretical fission barriers of TALYS 1.6 code have been used for the fission cross section calculations. The calculated results have been compared with the experimental data taken from the EXFOR database. TALYS 1.6 Sierk model calculations exhibit generally good agreement with the experimental measurements for all reactions used in this study.

  11. Exploring contributions from incomplete fusion in Li,76+209Bi and Li,76+198Pt reactions

    Parkar, V. V.; Jha, V.; Kailas, S.

    2016-08-01

    We use the breakup absorption model to simultaneously describe the measured cross sections of complete fusion (CF), incomplete fusion (ICF), and total fusion (TF) in nuclear reactions induced by weakly bound nuclei Li,76 on 209Bi and 198Pt targets. The absorption cross sections are calculated using the continuum discretized coupled channels (CDCC) method with different choices of short-range imaginary potentials to get the ICF, CF, and TF cross sections. It is observed that the cross sections for deuteron ICF / deuteron capture and α ICF / α capture are of similar magnitude, in the case of the 6Li projectile, while the cross sections for the triton ICF / triton capture is more dominant than that of α ICF / α capture in the case of the 7Li projectile. Both these observations are also corroborated by the experimental data. The ratio of ICF to TF cross sections, which defines the value of fusion suppression factor, is found to be in agreement with the data available from the literature. The cross-section ratios of CF/TF and ICF/TF show opposite behavior at below-barrier energies the former decreases while the latter increases as the energy is lowered, which shows the dominance of ICF at below-barrier energies. We have also studied the correlation of the ICF cross sections with the noncapture breakup (NCBU) cross sections as a function of energy, which shows that the NCBU is more significant than ICF at below-barrier energies.

  12. Exploring contributions from incomplete fusion in $^{6,7}$Li+$^{209}$Bi and $^{6,7}$Li+$^{198}$Pt reactions

    Parkar, V V; Kailas, S

    2016-01-01

    We use the breakup absorption model to simultaneously describe the measured cross-sections of the Complete fusion (CF), Incomplete fusion (ICF), and Total fusion (TF) in nuclear reactions induced by weakly bound nuclei $^{6,7}$Li on $^{209}$Bi and $^{198}$Pt targets. The absorption cross-sections are calculated using the Continuum Discretized Coupled Channels (CDCC) method with different choices of short range imaginary potentials to get the ICF, CF and TF cross-sections. It is observed that the cross-sections for deuteron-ICF/deuteron-capture are of similar magnitude as the $\\alpha$-ICF/$\\alpha$-capture, in case of $^{6}$Li projectile, while the cross-sections for triton-ICF/triton-capture is more dominant than $\\alpha$-ICF/$\\alpha$-capture in case of $^{7}$Li projectile. Both these observations are also corroborated by the experimental data. The ratio of ICF to TF cross-sections, which defines the value of fusion suppression factor is found to be in agreement with the data available from the literature. The...

  13. Experimental study of the neutron induced fission cross-section of 234U, 237Np and 243Am with time-of-flight spectrometry technics

    The current work concentrates on the measurements of the nuclear data needed for solving the problem of transmutation of radiotoxic waste. It includes fission cross-section of 234U in the energy range from thermal to 1 MeV, 237Np and 243Am in the resonance region and average group capture cross-section of 234U and 236U. Almost all of these data are recommended by IAEA as a first priority needs for transmutation problem. Another objective is to obtain the high resolution data of the fission cross-section of the 234U on the fission barrier to confirm the existence of the fine structure, attributed to the vibrational resonances in the third well of the fission barrier. The Dissertation summarizes more, than 10 years of the experiments, performed on the pulsed neutron sources IBR-2 and IBR-30 of Frank Laboratory of Neutron Physics of the Joint Institute for Nuclear Research (FLNP JINR) in Dubna, Russia; 'Fakel' of Russian Scientific Center 'Kurchatov's Institute' and n-TOF of CERN. The TOF technique was used for neutron energy spectrometry and various kinds of detectors to mark the fission events. The independent measurements of the same isotopes done on different neutron sources and sometimes with different techniques gives strong, self-consistent set of data. (author)

  14. Measurements of energy dependence of average number of prompt neutrons from neutron-induced fission of 235U, 241Am and 243Am from 0.5 to 12 MeV

    The energy dependence measurements results of average number of prompt neutrons from neutron-induced fission of 235U, 241Am, 243Am and total gamma-rays energy for 235U and 243Am from 0.5 to 12 MeV are presented. The measurements were carried out with neutron beam from uranium target of electron linac of All-Union Scientific Research Institute of Experimental Physics using time-of-flight technique on 28.5 m flight-path. The neutrons and gamma-rays from fission were detected by a big liquid scintillator detector (BLSD) loaded with gadolinium, events of fission - by parallel plate avalanche detector for fission fragments. Measurement of energy dependence of anti νp, Eγtot and determination of BLSD efficiency (relative to anti νp and Eγtot for 252Cf) were carried out simultaneously. Least squares fitting results give anti νp=3.05+0.14degEn for 241Am and anti νp=3.20+.15degEn for 243Am. (orig.)

  15. Developments of 207Pb, 208Pb and 209Bi target wheels in the synthesis of 107Ns, 108Hs and 109Mt

    The developments of 207Pb, 208Pb and 209Bi target wheels and their applications in heavy-ion fusion reactions are reviewed. In both, fabrication and use, the centers of the evaporator or accelerator beams are focussed at wheel radii of 155 mm to specially shaped frames which generate very homogeneous target layers and very constant reaction and counting rates in the experiment. Target areas of up to ∼98% of a wheel's circumference of 974 mm can be provided. The preparation procedures for necessary C backings and protecting layers of C are described, and details are given for the developments of high-vacuum evaporations of 207Pb, 208Pb and 209Bi with deposition yields of 35-55% from tantalum crucibles. The applications of the target wheels in heavy-ion fusion reactions with beams of 54Cr and 58Fe at energies near the Coulomb barrier and intensities of ∼1012 particles/s are mentioned. The target parameters for the production runs of the new chemical elements 107Ns, 108Hs and 109Mt are included. (orig.)

  16. Calculation of neutron cross sections for 90Zr, 208Pb and 209Bi in the energy range of 0.5-25 MeV by using the optical model potentials

    Neutron total cross sections and differential elastic scattering cross sections for the nuclides 90Zr, 208Pb and 209Bi were calculated using different global spherical optical potential (SOP) parameter sets at neutron energies from 0.5-25 MeV. Calculated cross sections for the corresponding nuclides were compared with their experimental data obtained by the EXFOR file to select the best fit parameter sets. It is found that the parameter sets of Ferer Rapaport for 90Zr and Bechetti and Greenless for 208Pb and 209Bi are the best fitted set to obtain the experimental data of total cross sections and angular distributions of these nuclides. (author)

  17. The damping of the single-particle proton strengths in 1isub(11/2) and 1jsub(15/2) states of 209Bi

    15 proton states have been mixed with the low-lying vibrational states as well as the vibrational states arising from the giant resonances in 208Pb to search for the broad fragmentations of the 1 'one' j15/2 and 'one' i11/2 states as observed in the most recent (α,t) reaction on 208Pb. The distribution of the shell-model strengths of these two high-spin states can be explained on the basis of the core polarisation effect on these two proton states of 209Bi. Knowledge of the altered shell-model energies of the proton states of 208Pb is necessary for the search for magicity in the superheavy nuclei. (author)

  18. Neutron-induced fission cross section of (nat)Pb and (209)Bi from threshold to 1 GeV: An improved parametrization

    Tarrio, D; Audouin, L; Berthier, B; Duran, I; Ferrant, L; Isaev, S; Le Naour, C; Paradela, C; Stephan, C; Trubert, D; Abbondanno, U; Aerts, G; Alvarez-Velarde, F; Andriamonje, S; Andrzejewski, J; Assimakopoulos, P; Badurek, G; Baumann, P; Becvar, F; Belloni, F; Berthoumieux, E; Calvino, F; Calviani, M; Cano-Ott, D; Capote, R; Carrapico, C; Carrillo de Albornoz, A; Cennini, P; Chepel, V; Chiaveri, E; Colonna, N; Cortes, G; Couture, A; Cox, J; Dahlfors, M; David, S; Dillmann, I; Dolfini, R; Domingo-Pardo, C; Dridi, W; Eleftheriadis, C; Embid-Segura, M; Ferrari, A; Ferreira-Marques, R; Fitzpatrick, L; Frais-Koelbl, H; Fujii, K; Furman, W; Goncalves, I; Gonzalez-Romero, E; Goverdovski, A; Gramegna, F; Griesmayer, E; Guerrero, C; Gunsing, F; Haas, B; Haight, R; Heil, M; Herrera-Martinez, A; Igashira, M; Jericha, E; Kadi, Y; Kappeler, F; Karadimos, D; Karamanis, D; Kerveno, M; Ketlerov, V; Koehler, P; Konovalov, V; Kossionides, E; Krticka, M; Lampoudis, C; Leeb, H; Lederer, C; Lindote, A; Lopes, I; Losito, R; Lozano, M; Lukic, S; Marganiec, J; Marques, L; Marrone, S; Martinez, T; Massimi, C; Mastinu, P; Mendoza, E; Mengoni, A; Milazzo, P.M; Moreau, C; Mosconi, M; Neves, F; Oberhummer, H; O'Brien, S; Oshima, M; Pancin, J; Papachristodoulou, C; Papadopoulos, C; Patronis, N; Pavlik, A; Pavlopoulos, P; Perrot, L; Pigni, M.T; Plag, R; Plompen, A; Plukis, A; Poch, A; Praena, J; Pretel, C; Quesada, J; Rauscher, T; Reifarth, R; Rosetti, M; Rubbia, C; Rudolf, G; Rullhusen, P; Salgado, J; Santos, C; Sarchiapone, L; Sarmento, R; Savvidis, I; Tagliente, G; Tain, J.L; Tavora, L; Terlizzi, R; Vannini, G; Vaz, P; Ventura, A; Villamarin, D; Vlachoudis, V; Vlastou, R; Voss, F; Walter, S; Wendler, H; Wiescher, M; Wisshak, K

    2011-01-01

    Neutron-induced fission cross sections for (nat)Pb and (209)Bi were measured with a white-spectrum neutron source at the CERN Neutron Time-of-Flight (n\\_TOF) facility. The experiment, using neutrons from threshold up to 1 GeV, provides the first results for these nuclei above 200 MeV. The cross sections were measured relative to (235)U and (238)U in a dedicated fission chamber with parallel plate avalanche counter detectors. Results are compared with previous experimental data. Upgraded parametrizations of the cross sections are presented, from threshold energy up to 1 GeV. The proposed new sets of fitting parameters improve former results along the whole energy range.

  19. Comparison of reactions for the production of 258,257Db: 208Pb(51V,xn) and 209Bi(50Ti,xn)

    Gates, Jacklyn M.

    2008-01-01

    Excitation functions for the 1n and 2n exit channels of the 208Pb(51V,xn)259-xDb reaction were measured. A maximum cross section of the 1n exit channel of 2070+1100/-760 pb was measured at an excitation energy of 16.0 +- 1.8 MeV. For the 2n exit channel, a maximum cross section of 1660+450/-370 pb was measured at 22.0 +- 1.8 MeV excitation energy. The 1n excitation function for the 209Bi(50Ti,n)258Db reaction was remeasured, resulting in a cross section of 5480+1750/-1370 pb at an excitati...

  20. Energy dependence of the optical potentials for the 9Be +208Pb and 9Be +209Bi systems at near-Coulomb-barrier energies

    Gómez Camacho, A.; Yu, N.; Zhang, H. Q.; Gomes, P. R. S.; Jia, H. M.; Lubian, J.; Lin, C. J.

    2015-04-01

    We analyze the energy dependence of the interacting optical potential, at near barrier energies, for two systems involving the weakly bound projectile 9Be and the heavy 208Pb and 209Bi targets, by the simultaneous fit of elastic scattering angular distributions and fusion excitation functions. The approach used consists of dividing the optical potential into two parts. A short-range potential VF+i WF that is responsible for fusion, and a superficial potential VDR+i WDR for direct reactions. It is found, for both systems studied, that the fusion imaginary potential WF presents the usual threshold anomaly (TA) observed in tightly bound systems, whereas the direct reaction imaginary potential WDR shows a breakup threshold anomaly (BTA) behavior. Both potentials satisfy the dispersion relation. The direct reaction polarization potential predominates over the fusion potential and so a net overall behavior is found to follow the BTA phenomenon.

  1. Measurement of the Neutron Capture Cross Sections of $^{233}$U, $^{237}$Np, $^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm with a Total Absorption Calorimeter at n_TOF

    Beer, H; Wiescher, M; Cox, J; Rapp, W; Embid, M; Dababneh, S

    2002-01-01

    Accurate and reliable neutron capture cross section data for actinides are necessary for the poper design, safety regulation and precise performance assessment of transmutation devices such as Fast Critical Reactors or Accelerator Driven Systems (ADS). The goal of this proposal is the measurement of the neutron capture cross sections of $^{233}$U, $^{237}$Np, $^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm at n_TOF with an accuracy of 5~\\%. $^{233}$U plays an essential role in the Th fuel cycle, which has been proposed as a safer and cleaner alternative to the U fuel cycle. The capture cross sections of $^{237}$Np,$^{240,242}$Pu, $^{241,243}$Am and $^{245}$Cm play a key role in the design and optimization of a strategy for the Nuclear Waste Transmutation. A high accuracy can be achieved at n_TOF in such measurements due to a combination of features unique in the world: high instantaneous neutron fluence and excellent energy resolution of the facility, innovative Data Acquisition System based on flash ADCs and t...

  2. Determination of the neutron resonance parameters for 206Pb and of the thermal neutron capture cross section for 206Pb and 209Bi

    Chapter 1 describes the motivation of the measurements (accelerator driven systems, stellar nucleosynthesis, neutron induced reactions on 206Pb), the present status of the neutron capture data for 206Pb and 209Bi and the structure of this work. In Chapter 2 the basic reaction theory underlying this work is described. The neutron induced reaction mechanism and formalism are explained. The parameterisation of the cross section in terms of R-matrix theory is discussed and we put particular emphasis on the statistical behaviour of the resonance parameters and the impact of the angular distribution of gamma rays following neutron capture. The relation between experimental observables and the resonance parameters is discussed together with general comments related to resonance shape analysis. Chapter 3 is focused on the determination of resonance parameters for 206Pb. We performed high-resolution transmission and capture measurements at the Time-Of-Flight (TOF) facility GELINA of the IRMM at Geel (B) and determined the resonance parameters. For nuclei like 206Pb, where the total width is dominated by Γn, the capture area allows to determine G. Transmission measurements were carried out to determine Γn, and the statistical factor g of resonances. Before performing a Resonance Shape Analysis (RSA) on the transmission and capture data, we verified the neutron flux and resolution at GELINA. We also compared the characteristics of GELINA with those of the n-TOF facility at CERN. A special emphasis is placed on the total energy detection technique using C6D6 detectors. This technique was applied for the determination of the capture cross section. To reduce systematic bias effects on the capture cross section, the response of the detectors was determined by Monte Carlo simulations, which has been validated by experiments. Using these response functions the partial capture cross sections for individual resonances of 206Pb have been deduced, by unfolding the response of the C6D

  3. Excitation functions of residual nuclei production from 40–2600 MeV proton-irradiated 206,207,208,natPb and 209Bi

    Yu E Titarenko; V F Batyaev; V M Zhivun; V O Kudryashov; K A Lipatov; A V Ignatyuk; S G Mashnik

    2007-02-01

    The work is aimed at experimental determination of the independent and cumulative yields of radioactive residual nuclei produced in intermediate-energy proton-irradiated thin targets made of highly isotopic enriched and natural lead (206,207,208,natPb) and 209Bi. 5972 radioactive product nuclide yields have been measured in 55 thin targets induced by 0.04, 0.07, 0.10, 0.15, 0.25, 0.6, 0.8, 1.2, 1.4, 1.6 and 2.6 GeV protons extracted from the ITEP U-10 proton synchrotron. The measured data have been compared with data obtained at other laboratories as well as with theoretical simulations by seven codes. We found that the predictive power of the tested codes is different but is satisfactory for most of the nuclides in the spallation region, though none of the codes agree well with the data in the whole mass region of product nuclides and all should be improved further.

  4. A new evaluation of neutron data for the 209Bi between 10-5 eV and 20 MeV

    A new evaluation of neutron induced cross-sections on 209Bi has been completed within the full energy range 10-5 eV - 20 MeV and put under ENDF format. A careful study of the resonance region led to a consistent set of resonance parameters. On this basis, the tabulated cross-sections (total, elastic, capture) have been calculated using the Reich-Moore formalism. At higher energies a consistent set of optical model parameters has been obtained by fitting mainly the total cross-section between 0.7 and 150 MeV and elastic scattering angular distributions from 4 to 24 MeV. The so obtained neutron penetrabilities have been used for Hauser-Feshbach statistical model calculations which have been completed with pre-equilibrium and direct interaction components to get elastic and inelastic cross sections, angular distributions, secondary neutron spectra and gamma production. All the results are generally in good agreement with the available experimental data

  5. Modes of transference and rupture of the nucleus with neutron halos 6 He on 209 Bi near of the Coulomb barrier

    In recent experiments, the fusion of the exotic radioactive nucleus 6 He with 209 Bi has been studied for the first time at energies above and below the Coulomb barrier. A considerable enhancement in the fusion was observed, which implies a reduction of about 25% in the nominal fusion barrier. Some previous theoretical works suggest that this striking effect may be caused by the coupling to neutron transfer channels with a positive Q-value which would lead to a neutron flow and the consequent formation of a neck between the projectile and the target. Later, in the current work, we ran two new experiments on the same reaction using the FN Tandem Van de Graaff (10 MV) accelerator and the dual superconducting TwinSol system, both of them belonging to the University of Notre Dame, USA. This time, the purpose was to study one- and two-neutron transfer and the 6 He projectile breakup at laboratory energies of 14.7, 16.2, 17.9, 19.0 and 22.5 MeV. A strong group of 4 He was observed (with an effective Q-value about .5 MeV) whose integrated cross section results exceptionally high, exceeding the fusion cross section both above and below the barrier. The simultaneously measured elastic scattering angular distribution required high total cross sections so that this yield is confirmed. Preliminary coupled channels calculations sing the computer program called Fresco developed at the University of Surrey (England) suggested that the reaction mechanisms may be better described as a direct nuclear breakup and two-neutron transfer to unbound states in 211 Bi. These calculations predicted also an enhancement in the fusion cross section below the barrier due to the transfer and breakup channel coupling, which strongly suggests that this channel is the 'doorway state' that explains the fusion barrier reduction observed in previous experiments. It was found that the 4 He group fully dominates the total reaction cross section at the measured energies and we show evidence that a new

  6. Measurements of Neutron-Induced Fission Cross Sections of 205Tl, 204, 206, 207, 208Pb, and 209Bi using Quasi-Monoenergetic Neutrons in the Energy Range 35 - 174 MeV

    Tutin, Gennady A.; Ryzhov, Igor V.; Eismont, Vilen P.; Mitryukhin, Andrey G.; Oplavin, Valery S.; Soloviev, Sergey M.; Blomgren, Jan; Condè, Henri; Olsson, Nils; Renberg, Per-Ulf

    2005-05-01

    Cross sections for neutron-induced fission of 205Tl, 204, 206, 207, 208Pb, and 209Bi were measured in the energy range from 35 MeV to 174 MeV. The experiments were done at the neutron beam facility of The Svedberg Laboratory, using a multi-section Frisch-gridded ionization chamber for detection of the fission fragments. The neutron-induced fission cross section of 238U was employed as a reference. The results of the measurements are compared with existing experimental data.

  7. Measurements of neutron-induced fission cross-sections of 205Tl, 204,206,207,208Pb and 209Bi with a multi-section Frisch-gridded ionization chamber

    Ryzhov, I. V.; Tutin, G. A.; Mitryukhin, A. G.; Oplavin, V. S.; Soloviev, S. M.; Blomgren, J.; Renberg, P.-U.; Meulders, J. P.; El Masri, Y.; Keutgen, Th.; Prieels, R.; Nolte, R.

    2006-06-01

    Neutron-induced fission cross-sections of 205Tl, 204,206,207,208Pb and 209Bi have been measured in the energy range from 30 to 180 MeV. The measurements were performed with quasi-monoenergetic neutron beams using a multi-section Frisch-gridded ionization chamber. The neutron-induced fission cross-sections of 238U were used as reference data. The experimental techniques are described in detail as well as the data processing. The results are compared with existing experimental data.

  8. Measurements of neutron-induced fission cross-sections of 205Tl, 204,206,207,208Pb and 209Bi with a multi-section Frisch-gridded ionization chamber

    Neutron-induced fission cross-sections of 205Tl, 204,206,207,208Pb and 209Bi have been measured in the energy range from 30 to 180 MeV. The measurements were performed with quasi-monoenergetic neutron beams using a multi-section Frisch-gridded ionization chamber. The neutron-induced fission cross-sections of 238U were used as reference data. The experimental techniques are described in detail as well as the data processing. The results are compared with existing experimental data

  9. Modes of transference and rupture of the nucleus with neutron halos {sup 6} He on {sup 209} Bi near of the Coulomb barrier; Modos de transferencia y rompimiento del nucleo con halo neutronico {sup 6} He sobre {sup 209} Bi cerca de la barrera de Coulomb

    Lizcano C, D

    2003-07-01

    In recent experiments, the fusion of the exotic radioactive nucleus {sup 6} He with {sup 209} Bi has been studied for the first time at energies above and below the Coulomb barrier. A considerable enhancement in the fusion was observed, which implies a reduction of about 25% in the nominal fusion barrier. Some previous theoretical works suggest that this striking effect may be caused by the coupling to neutron transfer channels with a positive Q-value which would lead to a neutron flow and the consequent formation of a neck between the projectile and the target. Later, in the current work, we ran two new experiments on the same reaction using the FN Tandem Van de Graaff (10 MV) accelerator and the dual superconducting TwinSol system, both of them belonging to the University of Notre Dame, USA. This time, the purpose was to study one- and two-neutron transfer and the {sup 6} He projectile breakup at laboratory energies of 14.7, 16.2, 17.9, 19.0 and 22.5 MeV. A strong group of {sup 4} He was observed (with an effective Q-value about .5 MeV) whose integrated cross section results exceptionally high, exceeding the fusion cross section both above and below the barrier. The simultaneously measured elastic scattering angular distribution required high total cross sections so that this yield is confirmed. Preliminary coupled channels calculations sing the computer program called Fresco developed at the University of Surrey (England) suggested that the reaction mechanisms may be better described as a direct nuclear breakup and two-neutron transfer to unbound states in {sup 211} Bi. These calculations predicted also an enhancement in the fusion cross section below the barrier due to the transfer and breakup channel coupling, which strongly suggests that this channel is the 'doorway state' that explains the fusion barrier reduction observed in previous experiments. It was found that the {sup 4} He group fully dominates the total reaction cross section at the

  10. Yield of Radionuclides and Isomers Measured in Fragmentation of the ^{nat}W and ^{186}W (97%) Targets with Protons at 630, 420 and 270 MeV

    Karamian, S A; Chaloun, P; Filossofov, D V; Henzl, V; Henzlova, D; Kalinnikov, V G; Korolev, N A; Lebedev, N A; Novgorodov, A F; Collins, C B; Popescu, I I; Ur, C A

    2004-01-01

    Yields and cross sections of the radioactive nuclide formation have been measured via induced activity gamma-spectra after irradiation of the natural composition W and enriched ^{186)W targets at Dubna synchrocyclotron. Spallation and fission products have been represented among the detected nuclides. The high-spin isomers of Hf and Lu were produced and the isomer-to-ground state ratios could be estimated. The nuclide yields have also been calculated using the LAHET code at 6 values of proton energy in the range from 100 to 800 MeV both for ^{nat)W and for enriched ^{186)W targets. Measured isotope yields are generally in agreement with the calculations, however, the code is incapable to predict the isomer-to-ground state ratios. In experiment, it has been shown that the ^{177m}Lu, ^{178m2}Hf and ^{179m2}Hf high-spin isomers are produced with 2.5 times higher yield in the 97% enriched ^{186)W target as compared to the ^{nat)W target at identical irradiations. This makes significance for the creation of high-a...

  11. Wet-chemistry method for the separation of no-carrier-added 211At/211gPo from 209Bi target irradiated by alpha-beam in cyclotron

    We present a fast and effective wet-chemistry method, used to obtain the pure alpha-emitter 211At/211gPo (T1/2 = 7.214 h/516 ms), produced by 209Bi(α,2n) reaction in NCA form. It is a selective radiochemical separation of the At radionuclides from the target and the impurities, characterized by a radionuclidic purity close to 100%, based on the dissolution and the dilution of the irradiated target in acidic medium, on the extraction with DIPE, followed by the back-extraction with NaOH. As a result, we obtain a yield greater than 90-97% in a range from 0.75M to 2.00M. (author)

  12. Motivation for New Measurements on 241, 242, 243Am Isotopes

    The initial objective of this work was an updated review on the Am isotopes data since the next official release (3.1) of the JEFF3 evaluated data file is foreseen around June 2005. Alternatively, this work searches for the possible reasons of the observed discrepancies between differential and integral measurement results. In particular, strong differences are encountered on σγth values and epithermal branching ratio values for the 241Am. Although the JEF2.2 validation is used as guide in parallel with a systematic study of all differential and integral results available, the need for new measurements clearly shows up. This paper finally draws up a list of desired and feasible new differential and integral measurements on the Am isotopes

  13. Optical model analysis over a wide range of nuclei using polarized neutron scattering data

    Polarized neutron scattering data for the nuclei 27Al, natCr, natCu, 89Y, natW, natPb, 209Bi, 232Th and 238U were analyzed in terms of spherical, coupled channels and microscopic optical model potentials. The measurements at typical 7.75 MeV neutron energy were performed at the Stuttgart SCORPION facility. (author)

  14. Residual nuclide formation in 206,207,208,natPb and 209Bi induced by 0.04 - 2.6 GeV protons as well as in 56Fe induced by 0.3 - 2.6 GeV protons

    This work is aimed at experimental determination of independent and cumulative yields of radioactive residual product nuclei in the intermediate energy proton-irradiated thin targets made of highly isotopic enriched and natural lead (206,207,208,natPb), bismuth (209Bi), and highly isotopic enriched iron (56Fe). 5972 independent and cumulative yields of radioactive residuals nuclei have been measured in 55 thin Pb and Bi targets irradiated by 0.04, 0.07, 0.10, 0.15, 0.25, 0.6, 0.8, 1.2, 1.4, 1.6, and 2.6 GeV protons. Besides, 219 yields have been measured in 0.3, 0.5, 0.75, 1.0, 1.5, and 2.6 GeV proton-irradiated Fe target. In both cases, the protons were extracted from the ITEP U-10 synchrotron. The measured data are compared with experimental results obtained elsewhere and with theoretical calculations by seven codes. The predictive power was found to be different for each of the codes tested, but was satisfactory on the whole in the case of spallation products. At the same time, none of the codes can describe well the product yields throughout the whole product mass range, and all codes must be further improved. (authors)

  15. New measurement of neutron capture resonances of 209Bi

    Domingo-Pardo, C; Abbondanno, U; Aerts, G; Alvarez-Pol, H; Alvarez-Velarde, F; Andriamonje, Samuel A; Andrzejewski, J; Assimakopoulos, Panayiotis; Audouin, L; Badurek, G; Baumann, P; Becvar, F; Berthoumieux, E; Calviño, F; Cano-Ott, D; Capote, R; Carrillode Albornoz, A; Cennini, P; Chepel, V; Chiaveri, Enrico; Colonna, N; Cortés, G; Couture, A; Cox, J; Dahlfors, M; David, S; Dillman, I; Dolfini, R; Dridi, W; Durán, I; Eleftheriadis, C; Embid-Segura, M; Ferrant, L; Ferrari, A; Ferreira-Marques, R; Fitzpatrick, L; Frais-Kölbl, H; Fujii, K; Furman, W; Gallino, R; Gonçalves, I; Gonzalez-Romero, E; Goverdovski, A; Gramegna, F; Griesmayer, E; Guerrero, C; Gunsing, F; Haas, B; Haight, R; Heil, M; Herrera-Martínez, A; Igashira, M; Isaev, S; Jericha, E; Kadi, Y; Kappeler, F; Karamanis, D; Karadimos, D; Kerveno, M; Ketlerov, V; Köhler, P; Konovalov, V; Kossionides, E; Krticka, M; Lamboudis, C; Leeb, H; Lindote, A; Lopes, I; Lozano, M; Lukic, S; Marganiec, J; Marques, L; Marrone, S; Mastinu, P; Mengoni, A; Milazzo, P M; Moreau, C; Mosconi, M; Neves, F; Oberhummer, Heinz; Oshima, M; O'Brien, S; Pancin, J; Papachristodoulou, C; Papadopoulos, C; Paradela, C; Patronis, N; Pavlik, A; Pavlopoulos, P; Perrot, L; Plag, R; Plompen, A; Plukis, A; Poch, A; Pretel, C; Quesada, J; Rauscher, T; Reifarth, R; Rosetti, M; Rubbia, Carlo; Rudolf, G; Rullhusen, P; Salgado, J; Sarchiapone, L; Savvidis, I; Stéphan, C; Tagliente, G; Taín, J L; Tassan-Got, L; Tavora, L; Terlizzi, R; Vannini, G; Vaz, P; Ventura, A; Villamarín, D; Vincente, M C; Vlachoudis, V; Vlastou, R; Voss, F; Walter, S; Wendler, H; Wiescher, M; Wisshak, K

    2006-01-01

    The neutron capture cross section of Bi209 has been measured at the CERN n TOF facility by employing the pulse-height-weighting technique. Improvements over previous measurements are mainly because of an optimized detection system, which led to a practically negligible neutron sensitivity. Additional experimental sources of systematic error, such as the electronic threshold in the detectors, summing of gamma-rays, internal electron conversion, and the isomeric state in bismuth, have been taken into account. Gamma-ray absorption effects inside the sample have been corrected by employing a nonpolynomial weighting function. Because Bi209 is the last stable isotope in the reaction path of the stellar s-process, the Maxwellian averaged capture cross section is important for the recycling of the reaction flow by alpha-decays. In the relevant stellar range of thermal energies between kT=5 and 8 keV our new capture rate is about 16% higher than the presently accepted value used for nucleosynthesis calculations. At th...

  16. Electrochemical oxidation of 243Am(III) in nitric acid by a terpyridyl-derivatized electrode

    Dares, C. J.; Lapides, A. M.; Mincher, B. J.; Meyer, T. J.

    2015-11-05

    A high surface area, tin-doped indium oxide electrode surface-derivatized with a terpyridine ligand has been applied to the oxidation of trivalent americium to Am(V) and Am(VI) in nitric acid. Potentials as low as 1.8 V vs. the saturated calomel electrode are used, 0.7 V lower than the 2.6 V potential for one-electron oxidation of Am(III) to Am(IV) in 1 M acid. This simple electrochemical procedure provides, for the first time, a method for accessing the higher oxidation states of Am in non-complexing media for developing the coordination chemistries of Am(V) and Am(VI) and, more importantly, for separation of americium from nuclear waste streams.

  17. Fission fragment mass distribution studies for 28Si + 197Au, 209Bi, 235U reactions

    In reactions with heavy ions, complete fusion and quasi-fission are the competing processes at energies above the Coulomb barrier. The quasi-fission process, in which the system reseparates before reaching a compact compound nucleus, is a major hurdle in forming heavy and superheavy evaporation residues (ER) in heavy-ion reactions. Fission fragment mass distribution for the fully equilibrated compound nucleus is decided at the scission point due to a long descent from saddle to scission. At higher excitation energies, the shell effects are washed out and the mass distribution is expected to be symmetric. The width of the distribution strongly depends on the entrance channel properties, such as mass asymmetry, deformation of interacting nuclei, collision energy, and the Coulomb factor Z1 Z2. Any sudden change in the width of the mass distribution would indicate departure from full equilibration, while onset of mass asymmetry or a sudden increase in width would be a strong signal of quasi fission

  18. Fission of 209Bi, natPb and 197Au in the particle field of a fast accelerator driven system

    Highlights: ► Fission rates of Bi, Pb and Au were measured in a particle field similar to that of fast ADS. ► The experimental results on fission rates are in agreement with MCNPX calculations. ► The most up to date fission cross-sections and related parameterizations were used. ► New parameterizations were produced from the published cross-section data. - Abstract: Accelerator driven systems (ADS) are expected to have particle spectra of significantly greater energy range than that of current power reactors. The Energy plus Transmutation (EpT) set-up of the Joint Institute for Nuclear Research, Dubna, Russia, is designed to emulate the neutron spectrum in a fast ADS through the use of a spallation target surrounded by a blanket of natural uranium. The spectrum is further modified by a reflective layer of polyethylene and an internal absorbing layer of cadmium. The spallation target of EpT was irradiated with a beam of 4 GeV deuterons, and the fission rates of bismuth, lead and gold samples, placed in the target-blanket region were recorded using a fission track detector technique. The fission rates were also calculated using the MCNPX Monte Carlo code with the INCL4 cascade model and cross sections for nucleon induced fission obtained from literature. Agreement between the measured and calculated results indicates the model’s ability to predict the particle spectra and spatial distribution

  19. Q- and Z-dependence of angular momentum transfer in deeply inelastic collisions of 86Kr with 209Bi

    The dependence of the in-plane and out-of-plane angular correlations of fragments from fissioning heavy products on the kinetic energy and Z of the light reaction partner have been measured. From the dependence of the angular correlations on Q-value and hence energy loss, together with existing data from which the total angular-integrated cross section as a function of energy loss can be extracted, the dependence of the angular momentum transferred to the heavy product on the initial orbital angular momentum or impact parameter has been determined. The resulting dependence is qualitatively consistent with the sticking limit for a reaction intermediate of touching deformed fragments. More specific nuclear models generally underestimate the angular momentum transfer, although the one-body proximity-friction model accounts for the major fraction of the angular momentum transfer. A recent model incorporating both one-body proximity friction and collective excitations accounts quite well for the observed angular momentum transfer. The Z-dependence of the anisotropy shows the importance of angular momentum fractionation for the less probable events, where the Z of the fissioning system is appreciably less than that of the target. The transferred angular momentum is shown to be fairly strongly aligned along the perpendicular to the reaction plane, with alignment values of 0.6 to 0.8. The component of angular momentum not along the perpendicular to the reaction plane is found to be primarily oriented perpendicular rather than parallel to the recoil directions. The absolute fission probabilities are found to be qualitatively consistent with J-dependent calculations using the J-values deduced from the angular correlations. (Auth.)

  20. Study of comparative reliability of computer simulation codes in estimating the cross sections for intermediate-energy proton interactions with nuclei of ADT materials

    The experimental data obtained by the authors on the production cross sections of residual nuclei in the 100-2600 MeV proton interactions with 59Co, 63,65Cu, nat,206,207,208Pb, 209Bi nuclei (thin targets) and with natW nucleus (thick target) are compared with the results of predictive simulation by ten codes. The reliability of the codes is estimated by quantitative ranking separately for a few combinations of proton energies and target materials making allowance for different generation channels of residual product nuclei. Despite quite satisfactory results of comparing between the experimental and simulated data in some cases, none of the simulation codes can be considered to show the required degree of applicability to all of the reactions studied

  1. Measurement of the scattering of polarized neutrons on heavy nuclei and analysis by means of the optical nuclear model

    In the present thesis experiments are described, which were performed with polarized neutrons at the Stuttgart neutron scattering facility SCORPION. The spectrum of the nuclei studied ranges from the spherical nuclei 206Pb, 208Pb, and 209Bi to the strongly deformed nuclei 181Ta, natW, 232Th, and 228U. Measured was the elastic and inelastic scattering of neutrons at energies around 7.75 MeV in an angular range from 21 to 124 degrees. The detected proton-recoil protons were transformed in line spectra by the unfolding procedure FANTI and corrected to finite geometry (program XJANE). The differential cross sections could be absolutely normed by additional polyethylene measurements. In the following data analysis (in the framework of the spherical and deformed optical model) it has been succeeded to fix the model parameters - especially those of the spin-orbit term. Special regard was dedicated to the study of the imaginary spin-orbit contribution. In all nuclei a significant improvement of the fit resulted, when an imaginary spin-orbit potential was introduced. (orig.)

  2. Elastic magnetic scattering of electrons, and radial distribution of valence nucleons. Study of the magnetisation of 49Ti, 51V, 59Co, 87Sr, 93Nb and 209Bi nuclei

    After an introduction on the use of elastic scattering of electrons, of magnetic scattering, and of their combination, this research thesis describes the theoretical framework of electron magnetic scattering, and the properties of the highest multi-poles. The author then presents the experimental installation, describes the experimental procedure from data acquisition to the derivation of final form factors. These form factors are then analysed and interpreted with respect to valence wave forms. Experimental and analysis results are compared with results of three different Hartree-Fock calculations. The limitations of these interpretations and theoretical calculations are discussed, notably by reference to the most recent calculations on core polarisation and on meson exchange currents. Results are also compared with those of other experiments

  3. Sub-coulomb transfer method of a nucleon for measure orbital radii

    The neutron transfer method is revised to measure neutron orbital radii and possible interest systems to apply it are determined. Its were carried out DWBA preliminary calculations for the system 209 Bi(d,t) 208 Bi. (Author)

  4. Experimental test of a new neutron threshold detector and its application

    2002-01-01

    The possibility of using 209Bi as a new threshold detector to measurc high-energy neutrons was investigated for the first time. At the same time the experiment measured successfully the emitted neutron fiuence rate, energy spectrum and dose equivalent rate distributions in the heavy ion target area using a detector complex including 209Bi, 115In, 27A1, 19F and 12C samples.

  5. Role of projectile breakup in {sup 6}He and {sup 6}Li induced fusion reactions around barrier energies

    Kumari, Anju; Kharab, Rajesh, E-mail: kharabrajesh@rediffmail.com

    2015-09-15

    The influence of projectile breakup on fusion cross section for {sup 6}He + {sup 209}Bi, {sup 6}He + {sup 64}Zn, {sup 6}Li + {sup 209}Bi and {sup 6}Li + {sup 64}Zn reactions at near barrier energies is studied within the framework of quantum diffusion approach. The breakup does not affect the fusion induced by {sup 6}He, whereas a significant suppression for {sup 6}Li induced reaction is observed in below barrier energy region.

  6. Measurements of minor actinides cross sections for transmutation

    The existing reactors produce two kinds of nuclear waste: the fission products and heavy nuclei beyond uranium called minor actinides (Americium and Curium isotopes). Two options are considered: storage in deep geological site and/or transmutation by fast neutron induced fission. These studies involve many neutron data. Unfortunately, these data bases have still many shortcomings to achieve reliable results. The aim of these measurements is to update nuclear data and complement them. We have measured the fission cross section of 243Am (7370 y) in reference to the (n,p) elastic scattering to provide new data in a range of fast neutrons (1-8 MeV). A statistical model has been developed to describe the reaction 243Am (n,f). Moreover, the cross sections from the following reactions have been be extracted from these calculations: inelastic scattering 243Am (n,n') and radiative capture 243Am (n,γ) cross sections. The direct measurements of neutron cross sections are often a challenge considering the short half-lives of minor actinides. To overcome this problem, a surrogate method using transfer reactions has been used to study few isotopes of curium. The reactions 243Am (3He, d)244Cm, 243Am (3He, t)243Cm and 243Am (3He, α)242Am allowed to measure the fission probabilities of 243,244Cm and 242Am. The fission cross sections of 242,243Cm (162,9 d, 28,5 y) and 241Am (431 y) have been obtained by multiplying these fission probabilities by the calculated compound nuclear neutron cross section relative to each channel. For each measurement, an accurate assessment of the errors was realized through variance-covariance studies. For measurements of the reaction 243Am(n,f), the analysis of error correlations allowed to interpret the scope of these measures within the existing measurements. (author)

  7. Method of preparation of tracer radionuclide 239Np using extraction chromatography

    This poster describes the preparation of tracers 239Np from 243Am. Used method involves stabilization of Np(IV) by ascorbic acid and ferric nitrate, separation of 239Np from 243Am using extraction chromatography and determination of activity of the solution obtained with 239Np using HPGe detector. In the experiment we used the commercially available sorbent TEVA Resin from the company Eichrom Technologies.

  8. Neutron elastic scattering in the energy region 1.5 to 4.0 MeV for radiogenic lead and bismuth

    Elastic scattering of 1.5 to 4.0 MeV neutrons from radiogenic lead, Pb sub (r), and 209Bi has been measured using a time-of-flight technique. The experimental results show the existence of a b broad maximun in the angle integrated elastic cross section centered at a neutron energy of about 3 MeV for both elements. Further, this cross-section maximum is more pronounced for 209Bi than for Pb sub (r). The data were analysed in terms of an optical model potential with spherical symmetry. The energy dependence of the total shape elastic cross sections calculated for Pb sub (r) and 209Bi from this model shows only minor differences, which are caused by the small mass difference and the fact that nuclear structure effects are not taken into account in the optical model. The observed cross section differences between Pb sub (r) and 209Bi have been explained as a compound nucleus effect caused by the essentially larger ground state spin of 209Bi as compared to Pb sub (r). Different formalisms have been used to correct the calculated compound elastic cross sections for level width fluctuations. (Author)

  9. High-energy neutron-induced fission cross sections of natural lead and bismuth-209

    Calviño Tavares, Francisco; Cortés Rossell, Guillem Pere; Poch Parés, Agustí; Pretel Sánchez, Carme

    2011-01-01

    The CERN Neutron Time-Of-Flight (n TOF) facility is well suited to measure small neutron- induced ssion cross sections, as those of subactinides. The cross section ratios of natPb and 209Bi relative to 235U and 238U were measured using PPAC detectors. The fragment coincidence method allows to unambiguously identify the ssion events. The present experiment provides the rst results for neutron-induced ssion up to 1 GeV for natPb and 209Bi. A good agreement with previous exper...

  10. Laser spectroscopy of the ground-state hyperfine structure in H-like and Li-like bismuth

    The LIBELLE experiment performed at the experimental storage ring (ESR) at the GSI Helmholtz Center in Darmstadt aims for the determination of the ground state hyperfine (HFS) transitions and lifetimes in hydrogen-like (209Bi82+) and lithium-like (209Bi80+) bismuth. The study of HFS transitions in highly charged ions enables precision tests of QED in extreme electric and magnetic fields otherwise not attainable in laboratory experiments. While the HFS transition in H-like bismuth was already observed in earlier experiments at the ESR, the LIBELLE experiment succeeded for the first time to measure the HFS transition in Li-like bismuth in a laser spectroscopy experiment

  11. The vacuum-polarization contribution to the hyperfine structure splitting of hydrogen-like atoms

    A calculation of the vacuum-polarization contribution to the hyperfine splitting for hydrogen-like atoms is presented. The extended nuclear charge distribution is taken into account. For the experimentally interesting case 209Bi82+ we predict a Δλ = -1.6 nm shift for the transition wave length of the ground state hyperfine splitting. (orig.)

  12. Self-energy correction to the hyperfine structure splitting of the 1 s and 2 s states in hydrogen ions

    The one-loop self-energy correction to the hyperfine structure splitting of the 1 s- and 2 s-states of hydrogenlike ions is calculated both for the point and finite nucleus. The results of the calculation are combined with other corrections to find the ground state hyperfine splitting in lithiumlike 209 Bi80+ and 165 Ho64+

  13. Performance and operation of advanced superconducting electron cyclotron resonance ion source SECRAL at 24 GHz.

    Zhao, H W; Lu, W; Zhang, X Z; Feng, Y C; Guo, J W; Cao, Y; Li, J Y; Guo, X H; Sha, S; Sun, L T; Xie, D Z

    2012-02-01

    SECRAL (superconducting ECR ion source with advanced design in Lanzhou) ion source has been in routine operation for Heavy Ion Research Facility in Lanzhou (HIRFL) accelerator complex since May 2007. To further enhance the SECRAL performance in order to satisfy the increasing demand for intensive highly charged ion beams, 3-5 kW high power 24 GHz single frequency and 24 GHz +18 GHz double frequency with an aluminum plasma chamber were tested, and some exciting results were produced with quite a few new record highly charged ion beam intensities, such as (129)Xe(35+) of 64 eμA, (129)Xe(42+) of 3 eμA, (209)Bi(41+) of 50 eμA, (209)Bi(50+) of 4.3 eμA and (209)Bi(54+) of 0.2 eμA. In most cases SECRAL is operated at 18 GHz to deliver highly charged heavy ion beams for the HIRFL accelerator, only for those very high charge states and very heavy ion beams such as (209)Bi(36+) and (209)Bi(41+), SECRAL has been operated at 24 GHz. The total operation beam time provided by SECRAL up to July 2011 has exceeded 7720 hours. In this paper, the latest performance, development, and operation status of SECRAL ion source are presented. The latest results and reliable long-term operation for the HIRFL accelerator have demonstrated that SECRAL performance for production of highly charged heavy ion beams remains improving at higher RF power with optimized tuning. PMID:22380167

  14. Method of measurement of cross sections of heavy nuclei fission induced by intermediate energy protons

    The purpose of this work is experimental studies of the energy dependence of the fission cross sections of heavy nuclei, natPb, 209Bi, 232Th, 233U, 235U, 238U, 237Np and 239Pu, by protons at the energies from 200 to 1000 MeV. At present experiment the method based on use of the gas parallel plate avalanche counters (PPACs) for registration of complementary fission fragments in coincidence and the telescope of scintillation counters for direct counting of the incident protons on the target has been used. First preliminary results of the energy dependences of proton induced fission cross sections for natPb, 209Bi, 235U and 238U are reported. (author)

  15. Studies of fragment spin as a function of fragment mass in heavy ion induced fission reactions

    Measurement on fragment spin as a function of its mass has been carried out over a wide range of bombarding energy in 12C, 16O + 209Bi and 12C, 16O + 232Th reactions. The mass dependence of fragment spin for 12C, 16O + 232Th reactions is observed to be in marked contrast to that for the 12C, 16O + 209Bi reactions. The present results have been analysed within the statistical model by taking into account the finite relaxation time for the equilibration of the collective spin modes. It is found that the observed feature in 12C, 16O + 232Th reactions are characteristic of incomplete equilibration of the collective spin modes where the mass relaxation process at extreme mass asymmetry terminates before full statistical equilibration of the collective spin modes are reached

  16. Transition energy and lifetime for the ground state hyperfine splitting of high Z lithium-like ions

    Shabaev, V M; Tupitsyn, I; Yerokhin, V A; Artemiev, A N; Kühl, T; Tomaselli, M; Zherebtsov, O M

    1998-01-01

    The ground state hyperfine splitting values and the transition probabilities between the hyperfine structure components of high Z lithiumlike ions are calculated in the range Z=49-83. The relativistic, nuclear, QED and interelectronic interaction corrections are taken into account. It is found that the Bohr-Weisskopf effect can be eliminated in a combination of the hyperfine splitting values of the hydrogenlike and lithiumlike ions of an isotope. This gives a good possibility for testing the QED effects in a combination of the strong electric and magnetic fields of the heavy nucleus. Using the experimental result for the 1s hyperfine splitting in ^{209}Bi^{82+}, the 2s hyperfine splitting in ^{209}Bi^{80+} is calculated to be \\Delta E=0.7981(2) eV while the contribution derived from QED constitutes 0.0007(1) eV.

  17. High-energy Neutron-induced Fission Cross Sections of Natural Lead and Bismuth-209

    Tarrio, D; Carrapico, C; Eleftheriadis, C; Leeb, H; Calvino, F; Herrera-Martinez, A; Savvidis, I; Vlachoudis, V; Haas, B; Koehler, P; Vannini, G; Oshima, M; Le Naour, C; Gramegna, F; Wiescher, M; Pigni, M T; Audouin, L; Mengoni, A; Quesada, J; Becvar, F; Plag, R; Cennini, P; Mosconi, M; Rauscher, T; Couture, A; Capote, R; Sarchiapone, L; Vlastou, R; Domingo-Pardo, C; Dillmann, I; Pavlopoulos, P; Karamanis, D; Krticka, M; Jericha, E; Ferrari, A; Martinez, T; Trubert, D; Oberhummer, H; Karadimos, D; Plompen, A; Isaev, S; Terlizzi, R; Cortes, G; Cox, J; Cano-Ott, D; Pretel, C; Colonna, N; Berthoumieux, E; Vaz, P; Heil, M; Lopes, I; Lampoudis, C; Walter, S; Calviani, M; Gonzalez-Romero, E; Embid-Segura, M; Stephan, C; Igashira, M; Papachristodoulou, C; Aerts, G; Tavora, L; Berthier, B; Rudolf, G; Andrzejewski, J; Villamarin, D; Ferreira-Marques, R; Tain, J L; O'Brien, S; Reifarth, R; Kadi, Y; Neves, F; Poch, A; Kerveno, M; Rubbia, C; Lazano, M; Dahlfors, M; Wisshak, K; Salgado, J; Dridi, W; Ventura, A; Andriamonje, S; Assimakopoulos, P; Santos, C; Voss, F; Ferrant, L; Patronis, N; Chiaveri, E; Guerrero, C; Perrot, L; Vicente, M C; Lindote, A; Praena, J; Baumann, P; Kappeler, F; Rullhusen, P; Furman, W; David, S; Marrone, S; Tassan-Got, L; Gunsig, F; Alvarez-Velarde, F; Massimi, C; Mastinu, P; Pancin, J; Papadopoulos, C; Tagliente, G; Haight, R; Chepel, V; Kossionides, E; Badurek, G; Marganiec, J; Lukic, S; Pavlik, A; Goncalves, I; Duran, I; Alvarez, H; Abbondanno, U; Fujii, K; Milazzo, P M; Moreau, C

    2011-01-01

    The CERN Neutron Time-Of-Flight (n\\_TOF) facility is well suited to measure small neutron-induced fission cross sections, as those of subactinides. The cross section ratios of (nat)Pb and (209)Bi relative to (235)U and (238)U were measured using PPAC detectors. The fragment coincidence method allows to unambiguously identify the fission events. The present experiment provides the first results for neutron-induced fission up to 1 GeV for (nat)Pb and (209)Bi. A good agreement with previous experimental data below 200 MeV is shown. The comparison with proton-induced fission indicates that the limiting regime where neutron-induced and proton-induced fission reach equal cross section is close to 1 GeV.

  18. Nuclear structure of 216Ra at high spin

    High-spin states of 216Ra (Z = 88, N = 128) have been investigated through 209Bi(10B, 3n) reaction at an incident beam energy of 55 MeV and 209Bi(11B, 4n) reaction at incident beam energies ranging from 65 to 78 MeV. Based on γγ coincidence data, the level scheme for 216Ra has been considerably extended up to ∼ 33 h spin and 7.2 MeV excitation energy in the present experiment with placement of 28 new γ-transitions over what has been reported earlier. Tentative spin-parity assignments are done for the newly proposed levels on the basis of the DCa ratios corresponding to strong gates. Empirical shell model calculations were carried out to provide an understanding of the underlying nuclear structure. (author)

  19. Studies of heavy ion reactions and transuranic nuclei. Progress report, August 1, 1979-July 31, 1980

    The study of heavy-ion reaction mechanisms at the SuperHILAC and LAMPF is reported. Preprints of five articles and manuscripts of four recent conference papers are given, along with complete citations of publications and a list of personnel. Significant work was performed in the following areas: the bombarding energy dependence of the 209Bi + 136Xe reaction; the fragment yields for specific Z and A for projectile-like fragments produced in the reaction of 8.3-MeV/u 56Fe ions with targets of 56Fe, 165Ho, 209Bi, and 238U; and time distributions of fragments from delayed fission after muon capture for muonic 235U, 238U, 237Np, 239Pu, and 242Pu

  20. Nuclear structure of 216Ra at high spin

    S Muralithar; G Rodrigues; R P Singh; R K Bhowmik; P Mukherjee; B Sethi; I Mukherjee

    2012-09-01

    High-spin states of 216Ra ( = 88, = 128) have been investigated through 209Bi(10B, 3n) reaction at an incident beam energy of 55 MeV and 209Bi(11B, 4n) reaction at incident beam energies ranging from 65 to 78 MeV. Based on coincidence data, the level scheme for 216Ra has been considerably extended up to $∼ 33\\hbar$ spin and 7.2 MeV excitation energy in the present experiment with placement of 28 new -transitions over what has been reported earlier. Tentative spin-parity assignments are done for the newly proposed levels on the basis of the DCO ratios corresponding to strong gates. Empirical shell model calculations were carried out to provide an understanding of the underlying nuclear structure.

  1. Superheavy research at RIKEN

    At RIKEN, Japan, we performed experiments to study the productions and decays of the heaviest elements produced by 208Pb- and 209Bi- based 'cold fusion' reactions. A gas-filled recoil separator GARIS was used for the study. In the study of 209Bi(70Zn, n) reaction, we observed two decay chains originating from an isotope of the 113th element, 178113, which were assigned firstly by generic correlation of the alpha decay chains connected into the previously known decay of 266Bh and 262Db via previously unknown alpha decays of 278113, 274Rg, and 270Mt. In addition, decay properties of an isotope 266Bh and its daughter nucleus 262Db produced by the 248Cm(23Na, 5n) reaction were studied. 266Bh was clearly identified from the correlation of the known nuclide, 262Db, providing further confirmation of the discovery of 278113.

  2. Production and decay properties of 272111 and its daughter nuclei

    The production and decay of 272111 has been investigated using a gas-filled recoil ion separator in irradiations of 209Bi targets with 64Ni beam at 320, 323 and 326 MeV. We have observed 14 α-decay chains in total, that can be assigned, on the basis of their time correlations, to subsequent decays from 272111 produced in the 209Bi(64Ni, 1n) reaction. The present result is the first clear confirmation for the discovery of 272111 and its α-decay products, 264Bh and 268Mt, reported previously by a GSI group. New information on their half-lives and decay energies as well as the excitation function is presented. (author)

  3. Thermal flucatuations in a classical theory with shape degrees of freedom for heavy ion collisions

    Samaddar, S. K.; Sperber, D.; Zielińska-Pfabe, M.; Sobel, M. I.; Garpman, S. I.

    1981-02-01

    We use a classical dynamical theory with shape degrees of freedom to describe deep inelastic scattering of heavy ions, and include thermal fluctuations by means of the Fokker-Planck equation. The degrees of freedom allow for neck formation, mass transfer, and stretching of the two-nucleus system. Inertias are calculated for these degrees of freedom, and dissipative and conservative forces are used. Fluctuations are calculated by considering the second moments of the distribution and determining a temperature from the excitation energy at each time. We calculate distributions in final energy, angle, charge, and mass, including some double differential cross sections. Results are in good agreement with data. NUCLEAR REACTIONS Classical dynamical model, shape degrees of freedom, Fokker-Planck equation, thermal fluctuations; angular, energy, mass, and charge distributions are calculated for the reactions 209Bi + 84Kr, 209Bi + 136Xe, and 197Au + 63Cu.

  4. Update to nuclear data standards for nuclear measurements. Summary report of a consultants' meeting

    This document is an update of the 1991 NEANDC/INDC Nuclear Standards File (INDC(SEC)-101) to indicate the status and extension of cross section standards for the 10B(n,α) reaction in the energy region below 20 Mev; and the H(n,n), 235U9(n,f), 238U(n,f), and 209Bi(n,f) reactions for selected energy regions above 20 Mev. Refs, figs, tabs

  5. Low-energy fusion dynamics of weakly bound nuclei: A time dependent perspective

    Diaz-Torres A.; Boselli M.

    2016-01-01

    Recent dynamical fusion models for weakly bound nuclei at low incident energies, based on a time-dependent perspective, are briefly presented. The main features of both the PLATYPUS model and a new quantum approach are highlighted. In contrast to existing timedependent quantum models, the present quantum approach separates the complete and incomplete fusion from the total fusion. Calculations performed within a toy model for 6Li + 209Bi at near-barrier energies show that converged excitation ...

  6. Formation of superheavy elements in heavy-ion collisions

    Denisov, Vitali

    2001-01-01

    The cold fusion reactions related to 208Pb and 209Bi targets leading to superheavy elements (SHE) with Z=104-112 have been successfully considered in our model recently. Here we briefly discuss this model and extend our consideration to fusion reactions between similar target and projectile. The reactions between weakly deformed target close to Pb and 76Ge, 82Se projectiles are also studied. The available experimental cross-sections are well described. The nucleus-nucleus interaction potentia...

  7. Asymptotic and near-target direct breakup of 6Li and 7Li

    Kalkal, Sunil; Simpson, E. C.; Luong, D. H.; Cook, K. J.; Dasgupta, M.; Hinde, D. J.; Carter, I. P.; Jeung, D. Y.; Mohanto, G.; Palshetkar, C. S.; Prasad, E.; Rafferty, D. C.; Simenel, C.; Vo-Phuoc, K.; Williams, E.; Gasques, L. R.; Gomes, P. R. S.; Linares, R.

    2016-04-01

    Background: Li,76 and 9Be are weakly bound against breakup into their cluster constituents. Breakup location is important for determining the role of breakup in above-barrier complete fusion suppression. Recent works have pointed out that experimental observables can be used to separate near-target and asymptotic breakup. Purpose: Our purpose is to distinguish near-target and asymptotic direct breakup of Li,76 in reactions with nuclei in different mass regions. Method: Charged particle coincidence measurements are carried out with pulsed Li,76 beams on 58Ni and 64Zn targets at sub-barrier energies and compared with previous measurements using 208Pb and 209Bi targets. A detector array providing a large angular coverage is used, along with time-of-flight information to give definitive particle identification of the direct breakup fragments. Results: In interactions of 6Li with 58Ni and 64Zn, direct breakup occurs only asymptotically far away from the target. However, in interactions with 208Pb and 209Bi, near-target breakup occurs in addition to asymptotic breakup. Direct breakup of 7Li into α -t is not observed in interactions with 58Ni and 64Zn. However, near-target dominated direct breakup was observed in measurements with 208Pb and 209Bi. A modified version of the Monte Carlo classical trajectory model code platypus, which explicitly takes into account lifetimes associated with unbound states, is used to simulate sub-barrier breakup reactions. Conclusions: Near-target breakup in interactions with Li,76 is an important mechanism only for the heavy targets 208Pb and 209Bi. There is insignificant near-target direct breakup of 6Li and no direct breakup of 7Li in reactions with 58Ni and 64Zn. Therefore, direct breakup is unlikely to suppress the above-barrier fusion cross section in reactions of Li,76 with 58Ni and 64Zn nuclei.

  8. Sensitivity of calculated cross sections on the optical model parameters

    After reminding the place of the optical model within the framework of nuclear data evaluation we present the sensitivity-analysis of physical quantities deduced from the optical model on the optical potential parameters in the particular case of the interaction n + 209Bi. This analysis is extended to the statistical model used at low incident energies. The consequences on the parameter fitting procedure are described

  9. Measurement of fusion cross section with neutron halo nuclei

    Fusion cross sections of 11Be, 10Be and 9Be have been measured on 209Bi target at 30-70MeV. Due to the neutron halo effect of 11Be, a large enhancement or suppression of the fusion cross section around the Coulomb barrier was theoretically predicted. Comparing the excitation function of 11Be with 10Be at near the Coulomb barrier region, no significant difference has been observed. ((orig.))

  10. Proton-induced nuclide production in heavy target elements at medium energies

    Cross sections for the proton-induced production of residual nuclei in natPb and 209Bi were measured for proton energies between 70 MeV and 1.6 GeV. A comparison with calculated cross sections using an INC/E-model, the hybrid model of preequilibrium reactions and a semiempirical formula has been performed showing that for applications which depend on accurate data it is still necessary to measure cross sections. 21 refs., 5 figs

  11. Complete and incomplete fusion competition in 11B-induced fission reaction on medium mass targets at intermediate energies

    Demekhina, N. A.; Karapetyan, G. S.; Balabekyan, A. R.

    2014-01-01

    The cross sections for the binary fission of 197Au, 181Ta and 209Bi targets induced by 11B ions were measured at intermediate energies. The fission products cross sections were studied by means of activation analysis in off-line regime observed gamma-ray spectra. The fission cross section is reconstructed on the basis of charge and mass distribution of the fission products.

  12. Influence of the angular momentum on nuclear fission

    Tanikawa, Masashi [Tokyo Univ. (Japan). Faculty of Science

    1996-03-01

    The effects of the angular momentum on the mechanism of nuclear fission are studied about the reaction systems of compound nucleus of {sup 210}P and {sup 239}Np by the time-of-flight (TOF) method. The reaction systems in this work are {sup 209}Bi+P, {sup 206}Pb+{alpha}, {sup 206}Po+{alpha}, {sup 198}Pt+{sup 12}C, {sup 238}U+P and {sup 232}Th+{sup 7}Li. Target was prepared by vacuum evaporating of each about 100 {mu}g/cm{sup 2} of {sup 209}Bi, {sup 206}Pb and {sup 198}Pt on 10 {mu}g/cm{sup 2} of carbon film. On compound nucleus {sup 210}Po, {sup 210}Po fissions at Ex=45McV but it fissions after 1 or 2 neutrons emission at higher excited energy (Ex=57 MeV). TKE shows almost the same values except higher value of {sup 209}Bi+P. The decreasing tendency of width of TKE distribution with increasing the angular momentum is found at the first time in this work. The effect of the angular momentum on the fission is small in the case of low angular momentum. On the compound nucleus {sup 239}Np, the effects are shown at the asymmetric fission part of the mass distribution. (S.Y.)

  13. Isospin effect on probing nuclear dissipation with fission cross sections

    Tian, J.; Ye, W.

    2016-08-01

    Nuclear dissipation retards fission. Using the stochastic Langevin model, we calculate the drop of fission cross section caused by friction over its standard statistical-model value, σfdrop, as a function of the presaddle friction strength for fissioning nuclei 195Bi, 202Bi, and 209Bi as well as for different angular momenta. We find that friction effects on σfdrop are substantially enhanced with increasing isospin of the Bi system and become greater with decreasing angular momentum. Our findings suggest that in experiments, to better constrain the strength of presaddle dissipation through the measurement of fission excitation functions, it is optimal to yield those compound systems with a high isospin and a low spin. Furthermore, we analyze the data of fission excitation functions of 210Po and 209Bi systems, which are populated in p +209Bi and p +208Pb reactions and which have a high isospin and a low spin, and find that Langevin calculations with a presaddle friction strength of (3-5) ×10-21 s-1 describe these experimental fission data very well.

  14. Measurements of Fission Cross Sections of Actinides

    Wiescher, M; Cox, J; Dahlfors, M

    2002-01-01

    A measurement of the neutron induced fission cross sections of $^{237}$Np, $^{241},{243}$Am and of $^{245}$Cm is proposed for the n_TOF neutron beam. Two sets of fission detectors will be used: one based on PPAC counters and another based on a fast ionization chamber (FIC). A total of 5x10$^{18}$ protons are requested for the entire fission measurement campaign.

  15. Translation of selected papers published in Nuclear Constants, No. 3(57), Moscow 1984

    The document contains the English translation of 6 papers selected for the nuclear data interest, (mainly the determination and the evaluation of the fast fission cross sections of 232Th, 235U, 238U, 237Np, 243Am) which were published in ''Topics in Atomic Science and Technology'', Series Nuclear Constants, No. 3(57), Moscow (1984). The original report was distributed as INDC(CCP)-240/G. Refs, figs and tabs

  16. Discoveries of Elements 113, 115 and 117

    Discovery of two isotopes of the new element 117 in the 249Bk + 48Ca reaction is described. A new 243Am + 48Ca experiment was carried out to firmly establish the discoveries of new elements 115 and 113. A total of thirty one decay chains of 288115 are now observed in the Am reaction. In addition, four new decay chains are assigned to 289115.

  17. Neutron-induced fission cross section measurement of 233U, 241Am and 243Am in the energy range 0.5 MeV En 20 MeV at nTOF at CERN

    Belloni, F. [Instituto Nazionale de Fisica Nucleare-Italy and CEA-France; Milazzo, P. M. [Instituto Nazionale de Fisica Nucleare, Trieste, Italy; Calviani, M. [Laboratori Nazionali di Legnaro, Italy and CERN, Geneva, Switzerland; Colonna, N. [Instituto Nazionale di Fisica Nucleare, Bari, Italy; Mastinu, P. F. [INFN, Laboratori Nazionali di Legnaro, Italy; Abbondanno, U. [Instituto Nazionale de Fisica Nucleare, Trieste, Italy; Aerts, G. [French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette; Alvarez, H. [University of Santiago de Compostela, Spain; Alvarez-Velarde, F. [Centro de Investigaciones Energeticas Medioambientales y Technol., Madrid, Spain; Andriamonje, S. [French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette; Andrzejewski, J. [University of Lodz, Lodz, Poland; Assimakopoulos, P. A. [University of Ioannina, Greece; Audouin, L. [Centre National de la Recherche Scidntifique/IN2P3-IPN, Orsay, France; Badurek, G. [Vienna University of Technology, Austria; Barbagallo, M. [Instituto Nazionale di Fisica Nucleare, Bari, Italy; Baumann, P. [CNRS, Strasbourg, France; Becvar, F. [Charles University, Prague, Czech Republic; Berthoumieux, E. [French Atomic Energy Commission (CEA), Centre de Saclay, Gif sur Yvette; Calvino, F. [Universidad Politecnica de Madrid, Spain; Cerutti, F. [CERN, Geneva, Switzerland; Cano-Ott, D. [CIEMAT, Spain; Capote, R. [IAEA-Vienna, Austria and Universidad de Sevilla, Spain; Carrapico, C. [Instituto Tecnológico e Nuclear (ITN), Lisbon, Portugal; Carrillo de Albornoz, A. [Instituto Tecnológico e Nuclear (ITN), Lisbon, Portugal; Cennini, P. [CERN, Geneva, Switzerland; Chepel, V. [University of Ciombra, Portugal; Chiaveri, E. [CERN, Geneva, Switzerland; Cortes, G. [Universitat Politecnica de Catalunya, Barcelona, Spain; Couture, A. [University of Notre Dame, IN; Cox, J. [University of Notre Dame, IN; Dahlfors, M. [CERN, Geneva, Switzerland; David, S. [CNRS, Orsay, France; Dillmann, I. [Institut fur Kernphysik, Karlsruhe, Germany; Dolfini, R. [Universita di Pavia, Italy; Domingo-Pardo, C. [CSIC-Universidad de Valencia; Koehler, Paul [ORNL; The n_TOF Collaboration, [CERN, Geneva, Switzerland

    2012-01-01

    Neutron-induced fission cross section measurements of 233U, 243Am and 241Am relative to 235U have been carried out at the neutron time-of-flight facility n TOF at CERN. A fast ionization chamber has been employed. All samples were located in the same detector; therefore the studied elements and the reference 235U target are subject to the same neutron beam.

  18. Analysis of the evaluated data discrepancies for minor actinides and development of improved evaluation

    Ignatyuk, A. [Institute of Physics and Power Engineering, Obninsk (Russian Federation)

    1997-03-01

    The work is directed on a compilation of experimental and evaluated data available for neutron induced reaction cross sections on {sup 237}Np, {sup 241}Am, {sup 242m}Am and {sup 243}Am isotopes, on the analysis of the old data and renormalizations connected with changes of standards and on the comparison of experimental data with theoretical calculation. Main results of the analysis performed by now are presented in this report. (J.P.N.)

  19. Actinides separation and long-lived fission products from the high activity effluent

    The aim of this document is to study the decontamination of a high activity effluent in minor actinides-α transmitters (241Am, 243Am, 243Cm, 245Cm, 237Np, 238Pu, 242Pu, 235U, 238U) and long-life fissions products (133Cs, 137Cs) and then the separation of Am, Cm, Np, Cs and Pu, U traces. (TEC). 16 figs., 1 tab

  20. Isoscaling and fission modes in the yields of the Kr and Xe isotopes from photofission of actinides

    Drnoyan, J.; Zhemenik, V. I.; Mishinsky, G. V.

    2016-05-01

    Yields of Kr and Xe isotopes in photofission of 232Th, 238U, 237Np, 244Pu, 243Am, and 248Cm were tested for isoscaling dependence. Isoscaling for Kr is revealed. For Xe, isoscaling is found to be affected by the STI and STII fission modes governed by the N = 82 and N = 88 neutron shells. The work was performed at the Flerov Laboratory of Nuclear Reactions, Joint Institute for Nuclear Research (JINR).

  1. Placental transfer of americium and plutonium in mice

    Actinide element release to the environment and subsequent transfer through food chains to pregnant women may present a radiation hazard to fetuses in utero. To measure americium incorporation, four groups of pregnant mice were intravenously dosed with four concentrations of 243Am citrate in late pregnancy. Concentrations of 243Am in fetuses, placentas, and maternal femur, liver, carcass and pelt were determined 48 hr after injection. Doses were chosen so that the number of atoms of 243Am in each injected dose was equal to the number of atoms of 239Pu used in an earlier study of transplacental movement. Results indicate that, atom for atom, americium is incorporated into fetal tissue in lesser amounts (10-25 times) than is plutonium when intravenously administered to pregnant mice in equal atom amounts. Tissue analyses indicated that, at low dose levels, the average fraction of the dose incorporated into the fetuses decreased as the dose to the pregnant mouse was increased. A similar pattern was noted for placentas and maternal femurs. Data indicate that one must make extrapolations from low dose data only to make reasonable and realistic estimates of the transplacental movement and fetal incorporation of environmental levels of actinide elements in man and other species. (author)

  2. Program DDCS for nucleon and composite particle DDX of nucleon induced reactions up to tens of MeV

    DDCS is a program for calculating the neutron or proton induced reactions of medium-heavy nuclei in the incident energy range up to 50 MeV including 5 emission processes. This program is written in FORTAN-77 on microscopic computer 486. DDCS is constructed within the framework of optical model, generalized master equation of the exciton model, and the evaporation model. The effect of recoil nucleus is considered in this program. DDCS has been used to calculate reactions of n + 56Fe, n + 93Nb, P + 120Sn, P + 197Au, and P + 209Bi. Pretty good results in agreement with the experimental data were obtained

  3. Low-energy fusion dynamics of weakly bound nuclei: A time dependent perspective

    Diaz-Torres, A.; Boselli, M.

    2016-05-01

    Recent dynamical fusion models for weakly bound nuclei at low incident energies, based on a time-dependent perspective, are briefly presented. The main features of both the PLATYPUS model and a new quantum approach are highlighted. In contrast to existing timedependent quantum models, the present quantum approach separates the complete and incomplete fusion from the total fusion. Calculations performed within a toy model for 6Li + 209Bi at near-barrier energies show that converged excitation functions for total, complete and incomplete fusion can be determined with the time-dependent wavepacket dynamics.

  4. Anti p-nucleus interaction

    Status and future prospects of antiproton-nucleus scattering experiments are presented. These scattering experiments were conducted at antiproton beam momentums of 300 and 600 MeV/c on target nuclei of 6Li, 12C, 16O, 18O, 40Ca, 48Ca, and 208Pb. Antiproton-proton reactions investigated antiproton-nucleus bound or resonant states in antiproton reactions with d, 6Li, 12C, 63Cu, and 209Bi. Inelastic scattering experiments investigated the spin-isospin dependence of the NN interactions. 19 refs., 1 fig., 1 tab

  5. Nuclear Matter Incompressibility Effect on the Cross Section of Fusion Reactions with a weakly bound projectile

    Seyyedi, S A

    2015-01-01

    Fusion reactions with a weakly bound projectile are studied using the double-folding model along with a repulsive interaction modifying term. Using this modified potential, including nuclear matter incompressibility effects, the fusion reaction cross sections and suppression parameters are calculated for 9Be +209Bi,208Pb,29Si and 27Al reactions. The results show that applying these effects at energies near the Coulomb barrier improves the agreement between the calculated and experimental cross sections, and modifies the mean values of the suppression parameter.

  6. Low-energy fusion dynamics of weakly bound nuclei: A time dependent perspective

    Diaz-Torres A.

    2016-01-01

    Full Text Available Recent dynamical fusion models for weakly bound nuclei at low incident energies, based on a time-dependent perspective, are briefly presented. The main features of both the PLATYPUS model and a new quantum approach are highlighted. In contrast to existing timedependent quantum models, the present quantum approach separates the complete and incomplete fusion from the total fusion. Calculations performed within a toy model for 6Li + 209Bi at near-barrier energies show that converged excitation functions for total, complete and incomplete fusion can be determined with the time-dependent wavepacket dynamics.

  7. Comparison of Complementary Reactions in the Production of Mt

    Nelson, Sarah; Gregorich, Kenneth; Dragojevic, Irena; Ellison, Paul; Garcia, Mitch Andre; Gates, Jacklyn; Stavsetra, Liv; Ali, Mazhar; Nitsche, Heino

    2009-01-21

    The new reaction 208Pb(59Co,n)266Mt was studied using the Berkeley Gas-filled Separator at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. A cross section of 7.7+5.2-3.3 pb was measured at a compound nucleus excitation energy of 14.9 MeV. The measured decay properties of 266Mt and its daughters correspond well with existing data. We compare this experimental result to transactinide compound nucleus formation model predictions, and the previously studied 209Bi(58Fe,n)266Mt reaction.

  8. Measurements of neutron-induced fission cross sections of Pb and Bi at intermediate energies

    Neutron-induced fission cross sections of natPb and 209Bi have been measured relative to the 238U(n.f) cross section at energies 96 MeV for lead and 133 MeV for bismuth. The measurements were performed at the quasi-mono-energetic neutron beam facility of The Svedberg Laboratory in Uppsala using Frisch-gridded ionization chamber. The results obtained are compared with other experimental data. The present state of the Bi standard recommended by IAEA is discussed. (author)

  9. Statistical interpretation of the correlation between intermediate mass fragment multiplicity and transverse energy

    Multifragment emission following 129Xe+197Au collisions at 30A, 40A, 50A, and 60A MeV has been studied with multidetector systems covering nearly 4π in solid angle. The correlations of both the intermediate mass fragment and light charged particle multiplicities with the transverse energy are explored. A comparison is made with results from a similar system 136Xe+209Bi at 28A MeV. The experimental trends are compared to statistical model predictions. copyright 1999 The American Physical Society

  10. Measurement of nuclear cross sections using radioactive beams

    One of the main applications of the production and use of nuclear radioactive beams is the measurement of nuclear cross sections. In this work is used a 6 He nuclear radioactive beam (β emitting with half life 806.7 ms) for the study of the reaction 6 + 209 Bi which could have several products. This investigation was realized in collaboration with the personnel of the Nuclear Structure laboratory at the University of Notre Dame (U.S.A.) and the National institute of Nuclear Research and CONACyT by Mexico. (Author)

  11. Self-energy correction to the hyperfine structure splitting of hydrogenlike Atoms

    A first testing ground for QED in the combined presence of a strong Coulomb field and a strong magnetic field is provided by the precise measurement of the hyperfine structure splitting of hydrogenlike 209Bi. We present a complete calculation of the one-loop self-energy correction to the first-order hyperfine interaction for various nuclear charges. In the low-Z regime we almost perfectly agree with the Zα expansion, but for medium and high Z there is a substantial deviation. copyright 1996 The American Physical Society

  12. Measurement of nuclear cross sections using radioactive beams; Medicion de secciones eficaces nucleares usando haces radiactivos

    Lizcano, D.; Aguilera, E.F.; Martinez Q, E. [Instituto Nacional de Investigaciones Nucleares, A.P. 18-1027, 11801 Mexico D.F. (Mexico)

    2000-07-01

    One of the main applications of the production and use of nuclear radioactive beams is the measurement of nuclear cross sections. In this work is used a {sup 6} He nuclear radioactive beam ({beta} emitting with half life 806.7 ms) for the study of the reaction {sup 6} + {sup 209} Bi which could have several products. This investigation was realized in collaboration with the personnel of the Nuclear Structure laboratory at the University of Notre Dame (U.S.A.) and the National institute of Nuclear Research and CONACyT by Mexico. (Author)

  13. A quasimolecular treatment of light-particle emission in incomplete-fusion reactions

    The light-particle emission in incomplete-fusion reactions has been analyzed within the framework of a simple model in which the fusion process plays an important role. A quasimolecular interpretation of the fusion has been employed in the model. The numerical results are in good agreement with the experimental data both at forward and backward angles for the reactions 159Tb(14N,α), 209Bi(14N,α) both at the energy 115 MeV and 197Au(22Ne,α) at the energy 178 MeV. (author)

  14. Fusion by diffusion model revisited

    A complete set of 27 excitation functions for synthesis of superheavy nuclei produced in cold fusion reactions was analyzed in terms of the "Fusion by Diffusion Model" of Swiatecki et al., modified to account for the angular momentum dependence of the fusion hindrance factor. The data on cold fusion reactions originate from experiments carried out at GSI Darmstadt, RIKEN Tokyo and LBNL Berkeley in which 208Pb and 209Bi targets were bombarded with the variety of projectiles ranging from 48,50Ti to 70Zn. (author)

  15. Nuclear physics research program at the 30 MeV Karaj cyclotron

    Noshad, H. E-mail: hnoshad@seai.neda.net.ir; Soheyli, S.; Lamehi-Rachti, M.; Talebi-Taher, A.R.; Aslani, Gh.; Maboudi-Moghaddam, S.; Rahighi, J.; Kakuee, O.R.; Heydari, N

    2002-08-01

    A versatile reaction chamber and its accessories as well as a multiparameter data acquisition system were designed, assembled, and installed in the R and D hall at NRCAM to allow nuclear measurements. The {sup 209}Bi(p,f) and {sup 197}Au(p,f) reaction experiments at E{sub p}=30 MeV were performed. The good agreement between our experimental results as compared with previously published data are presented here to show the reliability of our apparatus. In the case of the bismuth reaction, the fission cross section obtained by using pair spectrometry as well as its associated error have been measured for the first time.

  16. An empirical fit to estimated neutron emission cross sections from proton induced reactions

    Moumita Maiti; Maitreyee Nandy; S N Roy; P K Sarkar

    2003-01-01

    Neutron emission cross section for various elements from 9Be to 209Bi have been calculated using the hybrid model code ALICE-91 for proton induced reactions in the energy range 25 MeV to 105 MeV. An empirical expression relating neutron emission cross section to target mass number and incident proton energy has been obtained. The simple expression reduces the computation time significantly. The trend in the variation of neutron emission cross sections with respect to the target mass number and incident proton energy has been discussed within the framework of the model used.

  17. Remark on: the neutron spherical optical-model absorption.

    Smith, A. B.; Nuclear Engineering Division

    2007-06-30

    The energy-dependent behavior of the absorption term of the spherical neutron optical potential for doubly magic {sup 208}Pb and the neighboring {sup 209}Bi is examined. These considerations suggest a phenomenological model that results in an intuitively attractive energy dependence of the imaginary potential that provides a good description of the observed neutron cross sections and that is qualitatively consistent with theoretical concepts. At the same time it provides an alternative to some of the arbitrary assumptions involved in many conventional optical-model interpretations reported in the literature and reduces the number of the parameters of the model.

  18. Studies of giant multipole resonances with intermediate energy heavy ions

    The role of intermediate energy heavy ions in the study of giant multipole resonances is explored, with emphasis on gamma decay coincidence experiments. Experiments on 208Pb bombarded by 22 MeV/nucleon and 84 MeV/nucleon 17O are discussed and compared. The role of Coulomb excitation in the 84 MeV/nucleon data is emphasized and some consequences for study of isovector resonance strength are explored. A comparison of the excitation and decay of the isovector giant dipole resonance in 208Pb and 209Bi excited with 84 MeV/nucleon 17O scattering is presented. 19 refs., 15 figs., 1 tab

  19. Recent Advances in Nuclear Reaction Theories for Weakly Bound Nuclei: Reexamining the Problem of Inclusive Breakup

    Moro, Antonio M.; Lei, Jin

    2016-05-01

    The problem of the calculation of inclusive breakup cross sections in nuclear reactions is reexamined. For that purpose, the theory proposed by Ichimura et al. (Phys Rev C 32:431, 1985) is revisited, both in its prior and post representations. We briefly outline the connection of this theory with that proposed by Udagawa and Tamura (Phys Rev C 24:1348, 1981) and apply both theories to the inclusive breakup of ^6Li on ^{209}Bi at near-barrier energies, comparing also with available data. The relative importance of elastic versus non-elastic breakup, as a function of the incident energy and of the projectile separation energy, is also investigated.

  20. The newly observed 113th element

    The convincing candidate event of the isotope of the 113th element, 278113, and its daughter nuclei, 274111 and 271Mt, were observed, for the first time, in the 209Bi + 70Zn reaction. The experiment was performed at RIKEN (The Institute of Physical and Chemical Research) Linear Accelerator Facility using a GAs-filled Recoil Ion Separator GARIS. The experiments to confirm the productions and decays of isotopes 265Hs(Z=108), 271Ds(Z=110), 272Rg(Z=111), and 277112(Z=112) were also done. (author)

  1. Study of rare alpha decays with scintillating bolometers

    Cardani, L., E-mail: laura.cardani@roma1.infn.it [Dipartimento di Fisica, Sapienza University of Roma, Roma I-00185 (Italy); INFN, Sezione di Roma, Roma I-00185 (Italy)

    2013-08-01

    Rare α decays can be studied with an unprecedented sensitivity by means of scintillating bolometers, as these detectors can provide a large source mass as well as an excellent resolution and can disentangle the nature of the interacting particle thanks to the different light yield. As an example of the results that can be obtained with this technique, I report the conclusive test on the identification of {sup 209}Bi decay and the measurement of the half-life of this isotope. In addition, I present a measurement with a PbWO{sub 4} scintillating bolometer, in which the lead isotopes decays were studied.

  2. Systematics of fission cross sections at the intermediate energy region

    Fukahori, Tokio; Chiba, Satoshi [Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan). Tokai Research Establishment

    1997-03-01

    The systematics was obtained with fitting experimental data for proton induced fission cross sections of Ag, {sup 181}Ta, {sup 197}Au, {sup 206,207,208}Pb, {sup 209}Bi, {sup 232}Th, {sup 233,235,238}U, {sup 237}Np and {sup 239}Pu above 20 MeV. The low energy cross section of actinoid nuclei is omitted from systematics study, since the cross section has a complicated shape and strongly depends on characteristic of nucleus. The fission cross sections calculated by the systematics are in good agreement with experimental data. (author)

  3. Effect of the breakup process on the direct reaction with a 6Li projectile

    We investigate the effect of the breakup process on the direct reaction (DR) for 6Li. In order to study this effect, we introduce the experimental and semiexperimental ratio factors Rexpt and Rth by using the semiexperimental and experimental α-production cross sections and DR cross sections. The average values of the ratio Rexpt (Rth) for the 6Li+208Pb and 6Li+209Bi systems are 0.90 (0.91) and 0.86 (0.85), respectively. From these results, it can be seen that the α-production cross sections are the main contribution to the DR cross sections.

  4. Observation of 186mTa

    2006-01-01

    Unreported tantalum isomer 18mTa has been produced through the reaction 186W(n,p) by irradiation of natW with 14 MeV neutrons. The activity of 186Ta and 186Ta was measured using HPGe detectors and several X-γ as well as γ-γ coincidence arrangements. The 186mTa has been identified by means of measuring known γ rays from 186Ta p-decay. The half-life of 186mTa has been determined to be (1.5±0.1) min.

  5. Observation of 186mTa

    Unreported tantalum isomer 186mTa has been produced through the reaction 186W(n,p) by irradiation of natW with 14 MeV neutrons. The activity of 186mTa and 186Ta was measured using HPGe detectors and several X-γ as well as γ-γ coincidence arrangements. The 186mTa has been identified by means of measuring known γ rays from 186Ta β-decay. The half-life of 186mTa has been determined to be (1.5±0.1) min. (authors)

  6. Evidence for isotope 265Bh(Z=107)

    New isotope 265Bh (Z=107) was produced in bombardment of a 243Am target with 135 MeV 26Mg ions at HIRFL. Identification was made by observation of correlated α-particle decays between the new isotope 265Bh and its 261Db and 257Lr daughters with four pairs of detectors. The experimental results show that the half-life of 265Bh is 0.94-0.31+0.70 s and its α energy is (9.24 ± 0.05) MeV. (authors)

  7. Spectroscopic Tools Applied to Element Z = 115 Decay Chains

    Forsberg U.

    2014-03-01

    Full Text Available Nuclides that are considered to be isotopes of element Z = 115 were produced in the reaction 48Ca + 243Am at the GSI Helmholtzzentrum für Schwerionenforschung Darmstadt. The detector setup TASISpec was used. It was mounted behind the gas-filled separator TASCA. Thirty correlated α-decay chains were found, and the energies of the particles were determined with high precision. Two important spectroscopic aspects of the offline data analysis are discussed in detail: the handling of digitized preamplified signals from the silicon strip detectors, and the energy reconstruction of particles escaping to upstream detectors relying on pixel-by-pixel dead-layer thicknesses.

  8. The production of transplutonium elements in France

    The development of the program for the production of transplutonium elements, 241Am, 243Am and 244Cm, in France, required a major effort from the technological and chemical standpoints. Pre-existing hot cells were reconditioned and others specially built for these production operations. From the chemical standpoint, the development of extractive chromatography on the preparative scale has allowed the definition of simple processes. This type of process, initially developed for the treatment of Pu/Al targets, is ideal for the treatment of industrial wastes for their decontamination and for the production of 241Am

  9. Rapid determination of 237Np in soil samples by multi-collector inductively-coupled plasma mass spectrometry and gamma spectrometry

    Yi, Xiaowei; Shi, Yanmei; Xu, Jiang; He, Xiaobing; ZHANG, HAITAO; Lin, Jianfeng

    2013-01-01

    A radiochemical procedure is developed for the determination of 237Np in soil with multi-collector inductively-coupled plasma mass spectrometry (MC-ICP-MS) and gamma-spectrometry. 239Np (milked from 243Am) was used as an isotopic tracer for chemical yield determination. The neptunium in the soil is separated by thenoyl-trifluoracetone extraction from 1 M HNO3 solution after reducing Np to Np(IV) with ferrous sulfamate, and then purified with Dowex 1 × 2 anion exchange resin. 239Np in the resu...

  10. Spectroscopy of element 115 decay chains

    Rudolph, Dirk [Lund University, Sweden; Forsberg, U. [Lund University, Sweden; Golubev, P. [Lund University, Sweden; Sarmiento, L. G. [Lund University, Sweden; Yakushev, A. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Andersson, L.-L. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Di Nitto, A. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Duehllmann, Ch. E. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Gates, J. M. [Lawrence Berkeley National Laboratory (LBNL); Gregorich, K. E. [Lawrence Berkeley National Laboratory (LBNL); Gross, Carl J [ORNL; Hessberger, F. P. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Herzberg, R.-D [University of Liverpool; Khuyagbaatar, J. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Kratz, J. V. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Rykaczewski, Krzysztof Piotr [ORNL; Schaedel, M. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Aberg, S. [Lund University, Sweden; Ackermann, D. [GSI-Hemholtzzentrum fur Schwerionenforschung, Darmstadt, Germany; Block, M. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Brand, H. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Carlsson, B. G. [Lund University, Sweden; Cox, D. [University of Liverpool; Derkx, X. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Eberhardt, K. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Even, J. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Fahlander, C. [Lund University, Sweden; Gerl, J. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Jaeger, E. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Kindler, B. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Krier, J. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Kojouharov, I. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Kurz, N. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Lommel, B. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Mistry, A. [University of Liverpool; Mokry, C. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Nitsche, H. [Lawrence Berkeley National Laboratory (LBNL); Omtvedt, J. P. [Paul Scherrer Institut, Villigen, Switzerland; Papadakis, P. [University of Liverpool; Ragnarsson, I. [Lund University, Sweden; Runke, J. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Schaffner, H. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Schausten, B. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Thoerle-Pospiech, P. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Torres, T. [Gesellschaft fur Schwerionenforschung (GSI), Germany; Traut, T. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Trautmann, N. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany; Tuerler, A. [Paul Scherrer Institut, Villigen, Switzerland; Ward, A. [University of Liverpool; Ward, D. E. [Lund University, Sweden; Wiehl, N. [Johannes Gutenberg-Universitaet Mainz, Mainz, Germany

    2013-01-01

    A high-resolution a, X-ray and -ray coincidence spectroscopy experiment was conducted at the GSI Helmholtzzentrum fu r Schwerionenforschung. Thirty correlated a-decay chains were detected following the fusion-evaporation reaction 48Ca + 243Am. The observations are consistent with previous assignments of similar decay chains to originate from element Z = 115. The data includes first candidates of fingerprinting the decay step Mt --> Bh with characteristic X rays. For the first time, precise spectroscopy allows the derivation of excitation schemes of isotopes along the decay chains starting with elements Z > 112. Comprehensive Monte-Carlo simulations accompany the data analysis. Nuclear structure models provide a first level interpretation.

  11. Migration studies of radionuclides at the WIPP site

    A study was made of the effects on radionuclide migration from the solid TRU waste of inorganic and organic ligands in brine media. Typical organic waste meterials were exposed to synthetic brine at 700 for up to 1 year. Pure brine and brine/organic waste extracts were used to determine actinide and lathanide (153Gd, 144Ce, 152Eu, 243Am) distribution coefficients K/sub d/ between geological media and the brine. Results show that brine containing extract from plywood, etc. reduces considerably the K/sub d/

  12. Preparation of targets for nuclear chemistry experiments at DANCE

    In this paper, we describe the separation chemistry and electrodepositions conducted for the preparation of 241Am, 243Am and 233U targets used for cross-section measurements at DANCE. Thick, adherent deposits were prepared using molecular plating from isopropyl alcohol solutions. Improved yields and thicknesses were observed for 241Am electrodeposition after the material was purified using TRU resin from Eichrom. Similarly, 233U deposits were improved after purification with an anion exchange column in 9 M HBr followed by purification using UTEVA resin from Eichrom. (author)

  13. New Detection System for Heavy Element Research

    Tsyganov, Y S; Voinov, A A; Shumeyko, M V

    2015-01-01

    New detection system design for heavy element research with 48Ca projectile has been reported. This system is based on application of 32 position sensitive strip PIPS detector and low pressure pentane filled TOF detector application in 48Ca induced nuclear reactions. To suppress beam associated background products new version of real time method of active correlations has been applied. Examples of applications in 249Bk+48Ca and 243Am+48Ca reactions are presented. The system development to operate together with the digital ORNL detection system to provide a quick search for recoil to alpha correlation chains has been discussed too.

  14. Sequential determination of Pu and Am radioisotopes in environmental samples; a comparison of two separation procedures

    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

  15. Atlas of giant dipole resonances. Parameters and graphs of photonuclear reaction cross sections

    Parameters of giant dipole resonances (GDR) observed in photonuclear reaction cross sections using various beams of incident photons are presented. Data, given for 200 stable isotopes from 2H to 243Am including their natural compositions, were collected from papers published over the years 1951-1996. GDR parameters, such as energy positions, amplitudes and widths, are included into the table and organized by element, isotope and reaction. Graphs of the majority of the photonuclear reaction cross sections, included in the international nuclear data library EXFOR by the end of 1998, are presented. The graphs are provided for 182 stable isotopes and natural compositions. (author)

  16. Research of vertical migration of radionuclides in the soil at testing 'Red forest' area

    Researches of vertical migration of Chernobyl origin radionuclides at testing 'Red forest' rea in 5-km ChNPP-zone were carried out. The γ- and β- spectrometer measurements of soil samples were carried out using the anticompton spectrometer and a beta spectrometer. Presence of 60Co, 134, 137Cs, 154,155Eu, 241Am to depth of 30 cm in all soil cuts was fixed. The sites with sod-low-podzol sandy soils on alluvial sands contain 137Cs, 90Sr and 241Am to depth of 60 cm. The presence 243Am and 243Cm was found in the top layers of soils at territory of testing area.

  17. Multiparticle emission in the pre-equilibrium decay of light and heavy nuclei in α-induced reaction up to 60 MeV

    α-particle induced excitation functions for the reactions 55Mn(α,n)58Co, 55Mn(α,2n)57Co, 55Mn(α,3n)56Co, 55Mn(α,4n)55Co, 55Mn(α,αn)54Mn, 55Mn(α,2p3n)54Mn, 55Mn(α,α3n)52Mn, 209Bi(α,3n)210At and 209Bi(α,4n)209At have been measured up to 60 MeV α-particle using the stack foil activation technique. The reactions 55Mn(α,4n)55Co and 55Mn(α,α3n)52Mn have been studied for the first time. The theoretical comparison with a pre-equilibrium (PE) geometry dependent hybrid (GHD) model has been made. The initial exciton number n0=4 with different configurations (1n+2p+1h), (2n+2p+0h) and (2n+1p+1h) has been tested. It is found that configuration (2n+2p+0h) is the best set of choice. The pre-equilibrium fraction fPE of the total excitation function has also been calculated at different excitation energy. (author). 23 refs, 10 figs, 2 tabs

  18. NMR Evidence for the Topologically Nontrivial Nature in a Family of Half-Heusler Compounds

    Zhang, Xiaoming

    2016-03-16

    Spin-orbit coupling (SOC) is expected to partly determine the topologically nontrivial electronic structure of heavy half-Heusler ternary compounds. However, to date, attempts to experimentally observe either the strength of SOC or how it modifies the bulk band structure have been unsuccessful. By using bulk-sensitive nuclear magnetic resonance (NMR) spectroscopy combined with first-principles calculations, we reveal that 209Bi NMR isotropic shifts scale with relativity in terms of the strength of SOC and average atomic numbers, indicating strong relativistic effects on NMR parameters. According to first-principles calculations, we further claim that nuclear magnetic shieldings from relativistic p1/2 states and paramagnetic contributions from low-lying unoccupied p3/2 states are both sensitive to the details of band structures tuned by relativity, which explains why the hidden relativistic effects on band structure can be revealed by 209Bi NMR isotropic shifts in topologically nontrivial half-Heusler compounds. Used in complement to surface-sensitive methods, such as angle resolved photon electron spectroscopy and scanning tunneling spectroscopy, NMR can provide valuable information on bulk electronic states.

  19. Measurement of activation cross-sections for high-energy neutron-induced reactions of Bi and Pb

    Zaman, Muhammad; Kim, Guinyun; Kim, Kwangsoo; Naik, Haladhara; Shahid, Muhammad; Lee, Manwoo

    2015-08-01

    The cross-sections for 209Bi(n, 4n)206Bi, 209Bi(n, 5n)205Bi, natPb(n, xn)204mPb, natPb(n, xn)203Pb, natPb(n, xn)202mPb,natPb(n, xn)201Pb, natPb(n, xn)200Pb, natPb(n, αxn)203Hg and natPb(n, p xn)202Tl reactions were determined at the Korean Institute of Radiological and Medical Sciences (KIRAMS), Korea in the neutron energy range of 15.2 to 37.2 MeV. The above cross-sections were obtained by using the activation and off-line γ-ray spectrometric technique. The quasi-monoenergetic neutron used for the above reactions are based on the 9Be(p, n) reaction. Simulations of the spectral flux from the Be target were done using the MCNPX program. The cross-sections were estimated with the TALYS 1.6 code using the default parameter. The data from the present work and literature were compared with the data from the EAF-2010 and the TENDL-2013 libraries, and calculated values of TALYS 1.6 code. It shows that appropriate level density model, the γ-ray strength function, and the spin cut-off parameter are needed to obtain a good agreement between experimental data and theoretical values from TALYS 1.6 code.

  20. Studies of heavy-ion reactions and transuranic nuclei

    This report contain papers on the following topics: The Cold-Fusion Saga; Decay Patterns of Dysprosium Nuclei Produced in 32S + 118,124Sn Fusion Reactions; Unexpected Features of Reactions Between Very Heavy Ions at Intermediate Bombarding Energies; Correlations Between Neutrons and Charged Products from the Dissipative Reaction 197Au+208Pb at E/A = 29 MeV; Dissipative Dynamics of Projectile-Like Fragment Production in the Reaction 209Bi+136Xe at E/A = 28.2 MeV; Dynamical Production of Intermediate-Mass Fragments in Peripheral 209Bi+136Xe Collisions at Elab/A = 28.2 MeV; The Rochester 960-Liter Neutron Multiplicity Meter; A Simple Pulse Processing Concept for a Low-Cost Pulse-Shape-Based Particle Identification; A One-Transistor Preamplifier for PMT Anode Signals; A Five-Channel Multistop TDC/Event Handler for the SuperBall Neutron Multiplicity Meter; Construction of the SuperBall -- a 16,000-Liter Neutron Detector for Calorimetric Studies of Intermediate-Energy Heavy-Ion Reactions; A Computer Code for Light Detection Efficiency Calculations for Photo-multipliers of a Neutron Detector; Evaluation of Gd-Loaded Liquid Scintillators for the SuperBall Neutron Calorimeter; and Measurement of the Interaction of Cosmic-Ray μ- with a Muon Telescope

  1. NMR Evidence for the Topologically Nontrivial Nature in a Family of Half-Heusler Compounds

    Zhang, Xiaoming; Hou, Zhipeng; Wang, Yue; Xu, Guizhou; Shi, Chenglong; Liu, Enke; Xi, Xuekui; Wang, Wenhong; Wu, Guangheng; Zhang, Xi-Xiang

    2016-03-01

    Spin-orbit coupling (SOC) is expected to partly determine the topologically nontrivial electronic structure of heavy half-Heusler ternary compounds. However, to date, attempts to experimentally observe either the strength of SOC or how it modifies the bulk band structure have been unsuccessful. By using bulk-sensitive nuclear magnetic resonance (NMR) spectroscopy combined with first-principles calculations, we reveal that 209Bi NMR isotropic shifts scale with relativity in terms of the strength of SOC and average atomic numbers, indicating strong relativistic effects on NMR parameters. According to first-principles calculations, we further claim that nuclear magnetic shieldings from relativistic p1/2 states and paramagnetic contributions from low-lying unoccupied p3/2 states are both sensitive to the details of band structures tuned by relativity, which explains why the hidden relativistic effects on band structure can be revealed by 209Bi NMR isotropic shifts in topologically nontrivial half-Heusler compounds. Used in complement to surface-sensitive methods, such as angle resolved photon electron spectroscopy and scanning tunneling spectroscopy, NMR can provide valuable information on bulk electronic states.

  2. Simulated nucleon–nucleon and nucleon–nucleus reactions in the frame of the cascade exciton model at high and intermediate energies

    A Abdel-Hafiez; Shaker El-Shater; M F Zaki

    2015-04-01

    In this study, we have used the cascade exciton model (CEM) to investigate different characteristics of nuclear reactions. Number of nucleon–nucleon collisions in Pb+Pb collisions as a function of impact parameter and rapidity distributions of negative particles from p+Ar and p+Xe interactions at lab = 200 GeV/c have been studied. We could create inclusive spectra of pions for separate charged states from reactions and total neutron multiplicities per primary reaction at 1000 MeV for different thin targets. Also, cross-sections for the reactions 209Bi(p, f) and 209Bi(n, f) were studied. Interactions of 1.0 GeV protons with C, Al, Cu, Sn, and Pb are presented in this study. All the calculated characteristics are compared with other theoretical calculations and compared with the experimental data. CEM shows good agreement with both theoretical and experimental results. In this study, we have used quantum molecular dynamic (QMD) as a theoretical model to compare our results.

  3. Communication of nuclear data progress No. 23 (2000)

    The 23th issue of Communication of Nuclear Data Progress (CNDP) presents the achievements obtained last year in nuclear data field in China. It includes the measurements of double differential cross section of 9Be at 5.9 and 6.4 MeV and 186W(n,γ)187W reaction cross section from 0.50 to 1.5 MeV; researches on three body breakup process and energy balance in UNF code, theoretical calculations of n + 141Pr, 239,240Pu, P + 209Bi reactions; evaluations of n + 90,91,92,94,96,0Zr, NatCu, 135,136,137,138Ba neutron data, γ + 209Bi photo nuclear reaction data and fission yield from 235U fission; investigation on the systematics of isomeric cross section ratios for neutron-induced reactions around 14 MeV; progress report on prompt γ-ray data evaluation, and a brief report on the test of the fission rate for 238U. Also the activities and cooperation on nuclear data in China are summarized

  4. Collective dyanamics of intermediate-energy heavy-ion collisions

    Exclusive measurements of massive projectile-like fragments (PLF), intermediate-mass fragments (IMF), light charged particles (lcp), and neutrons have been performed for the reactions 209Bi + 136Xe and 197Au+208Pb at the lower boundary (∼29MeV/u) of the Fermi energy regime. Unexpectedly, the measurements provide compelling evidence for very simple reaction dynamics dominated by collective degrees of freedom. Invariant emission patterns of neutrons or lcp's indicate a binary first reaction stage, followed by the decay of the hot reaction products, for essentially the entire range of impact parameters. Non-evaporative light particles and cold IMF's are observed in peripheral collisions. IMF's seen in 209Bi + 136Xe collisions are possibly due to non-adiabatic neck rupture. Experimental correlations between particle multiplicity, and massive-fragment energy, deflection angle, and Z distribution suggest the presence of exchange-induced transport phenomena. In both reactions, the initially available kinetic energy is only partially damped. Together, these new observations challenge the present paradigm

  5. Comparison of complementary reactions for the production of 261,262Bh

    Two heavy-ion induced fusion reactions producing 261,262Bh were studied using the Berkeley Gas-filled Separator at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. An excitation function for the production of 262Bh via the reaction 209Bi(54Cr,n)262Bh was measured with a maximum cross section from a fit to the data of 430 ± 110 pb observed at a compound nucleus excitation energy of 15.7 MeV. New data have been measured for the 1n exit channel of the 208Pb(55Mn, n)262Bh reaction. We present an updated excitation function with an observed maximum cross section of 530±100 pb at a compound nucleus excitation energy of 14.1 MeV. Events corresponding to the 2n exit channel for the 209Bi(54Cr,2n)261Bh and 208Pb(55Mn,2n)261Bh reactions were also observed and are presented as partial excitation functions. The measured decay properties correspond well with existing experimental data. We compare these experimental results to cross section predictions from a model by Swiatecki et al. and discuss entrance channel effects on the magnitude of 1n cross sections

  6. Superheavy research at RIKEN

    Morita, Kosuke [Superheavy Element Laboratory, RIKEN Nishina Center for Accelerator Based Science, RIKEN Hirosawa 2-1, Wako-shi, Saitama 351-0198 (Japan)

    2010-03-01

    At RIKEN, Japan, we performed experiments to study the productions and decays of the heaviest elements produced by {sup 208}Pb- and {sup 209}Bi- based 'cold fusion' reactions. A gas-filled recoil separator GARIS was used for the study. In the study of {sup 209}Bi({sup 70}Zn, n) reaction, we observed two decay chains originating from an isotope of the 113th element, {sup 178}113, which were assigned firstly by generic correlation of the alpha decay chains connected into the previously known decay of {sup 266}Bh and {sup 262}Db via previously unknown alpha decays of {sup 278}113, {sup 274}Rg, and {sup 270}Mt. In addition, decay properties of an isotope {sup 266}Bh and its daughter nucleus {sup 262}Db produced by the {sup 248}Cm({sup 23}Na, 5n) reaction were studied. {sup 266}Bh was clearly identified from the correlation of the known nuclide, {sup 262}Db, providing further confirmation of the discovery of {sup 278}113.

  7. Correlation between strain and defects in Bi implanted Si

    Palade, C.; Lepadatu, A.-M.; Slav, A.; Ciurea, M. L.; Lazanu, S.

    2016-06-01

    The strain in Si containing group-V impurities is a topical subject of study due to its potential applications in quantum computing. In this paper we study 209Bi implanted Si concerning the correlation between the strain produced by stopped Bi ions and trapping characteristics of the defects resulted from implantation. The depths distributions of stopped ions and primary defects are simulated and the distributions of permanent defects are modelled for Si implanted with low fluence 209Bi ions of 28 MeV kinetic energy. For comparison, these depths distributions were similarly calculated for 127I ions with the same fluence and energy, implanted in Si. The results are compared with each other and correlated with the characteristics of traps in these systems, previously obtained. We demonstrate that the intensity of the strain field is the most important factor in changing of trap parameters, while the superposition between the region with strain and the region where defects are located is a second order effect.

  8. Impact of temperature on single event upset measurement by heavy ions in SRAM devices

    The temperature dependence of single event upset (SEU) measurement both in commercial bulk and silicon on insulator (SOI) static random access memories (SRAMs) has been investigated by experiment in the Heavy Ion Research Facility in Lanzhou (HIRFL). For commercial bulk SRAM, the SEU cross section measured by 12C ions is very sensitive to the temperature. The temperature test of SEU in SOI SRAM was conducted by 209Bi and 12C ions, respectively, and the SEU cross sections display a remarkable growth with the elevated temperature for 12C ions but keep constant for 209Bi ions. The impact of temperature on SEU measurement was analyzed by Monte Carlo simulation. It is revealed that the SEU cross section is significantly affected by the temperature around the threshold linear energy transfer of SEU occurrence. As the SEU occurrence approaches saturation, the SEU cross section gradually exhibits less temperature dependency. Based on this result, the experimental data measured in HIRFL was analyzed, and then a reasonable method of predicting the on-orbit SEU rate was proposed. (semiconductor devices)

  9. Production of transplutonium elements. Overview of some national programmes

    In the last fifteen years programmes of production of transplutonium element isotopes have been well established or decided in various countries. These productions concern essentially 241Am, 243Am, 244Cm, 248Cm and 252Cf isotopes. In western world the most ambitious programme is developped by the USA in OAK RIDGE and SAVANNAH RIVER facilities for the production of transcurium elements, especially 252Cf; LOS ALAMOS, ROCKY FLATS and HANFORD facilities for 241Am production. Other western nations produced in the past or possess a permanent programme; for example kilogram amount of 241Am has been produced in RFA, while in France productions of 241Am, 243Am and 244Cm are run in routine. Various other countries are involved in the production of transplutonium isotopes but this correspond often to punctual productions. Informations related to the soviet's programme are scarce, but productions of mg quantities of transcurium elements are known. This paper gives 63 references about these programmes with special emphasis on the chemical processes

  10. EA-MC Neutronic Calculations on IAEA ADS Benchmark 3.2

    The neutronics and the transmutation properties of the IAEA ADS benchmark 3.2 setup, the 'Yalina' experiment or ISTC project B-70, have been studied through an extensive amount of 3-D Monte Carlo calculations at CERN. The simulations were performed with the state-of-the-art computer code package EA-MC, developed at CERN. The calculational approach is outlined and the results are presented in accordance with the guidelines given in the benchmark description. A variety of experimental conditions and parameters are examined; three different fuel rod configurations and three types of neutron sources are applied to the system. Reactivity change effects introduced by removal of fuel rods in both central and peripheral positions are also computed. Irradiation samples located in a total of 8 geometrical positions are examined. Calculations of capture reaction rates in 129I, 237Np and 243Am samples and of fission reaction rates in 235U, 237Np and 243Am samples are presented. Simulated neutron flux densities and energy spectra as well as spectral indices inside experimental channels are also given according to benchmark specifications. Two different nuclear data libraries, JAR-95 and JENDL-3.2, are applied for the calculations

  11. NMR Evidence for the 8.5 K Phase Transition in Americium Dioxide

    Tokunaga, Yo; Nishi, Tsuyoshi; Kambe, Shinsaku; Nakada, Masami; Itoh, Akinori; Homma, Yoshiya; Sakai, Hironori; Chudo, Hiroyuki

    2010-05-01

    We report here the first NMR study of americium dioxide (AmO2). More than 30 years ago, a phase transition was suggested to occur in this compound at 8.5 K based on magnetic susceptibility data, while no evidence had been obtained from microscopic measurements. We have prepared a powder sample of 243AmO2 containing 90 at. % 17O and have performed 17O NMR at temperatures ranging from 1.5 to 200 K. After a sudden drop of the 17O NMR signal intensity below 8.5 K, at 1.5 K we have observed an extremely broad spectrum covering a range of ˜14 kOe in applied field. These data provide the first microscopic evidence for a phase transition as a bulk property in this system. In addition, the 17O NMR spectrum has been found to split into two peaks in the paramagnetic state, an effect which has not been reported for actinide dioxides studied up to now. We suggest that the splitting is induced by self-radiation damage from the alpha decay of 243Am.

  12. Transuranium analysis methodologies for biological and environmental samples

    Analytical procedures for the most abundant transuranium nuclides in the environment (i.e., plutonium and, to a lesser extent, americium) are available. There is a lack of procedures for doing sequential analysis for Np, Pu, Am, and Cm in environmental samples, primarily because of current emphasis on Pu and Am. Reprocessing requirements and waste disposal connected with the fuel cycle indicate that neptunium and curium must be considered in environmental radioactive assessments. Therefore it was necessary to develop procedures that determine all four of these radionuclides in the environment. The state of the art of transuranium analysis methodology as applied to environmental samples is discussed relative to different sample sources, such as soil, vegetation, air, water, and animals. Isotope-dilution analysis with 243Am (239Np) and 236Pu or 242Pu radionuclide tracers is used. Americium and curium are analyzed as a group, with 243Am as the tracer. Sequential extraction procedures employing bis(2-ethyl-hexyl)orthophosphoric acid (HDEHP) were found to result in lower yields and higher Am--Cm fractionation than ion-exchange methods

  13. New development of advanced superconducting electron cyclotron resonance ion source SECRAL (invited).

    Zhao, H W; Sun, L T; Lu, W; Zhang, X Z; Guo, X H; Cao, Y; Zhao, H Y; Feng, Y C; Li, J Y; Ma, H Y; Shang, Y; Ma, B H; Wang, H; Li, X X; Xie, D Z

    2010-02-01

    Superconducting electron cyclotron resonance ion source with advance design in Lanzhou (SECRAL) is an 18-28 GHz fully superconducting electron cyclotron resonance (ECR) ion source dedicated for highly charged heavy ion beam production. SECRAL, with an innovative superconducting magnet structure of solenoid-inside-sextupole and at lower frequency and lower rf power operation, may open a new way for developing compact and reliable high performance superconducting ECR ion source. One of the recent highlights achieved at SECRAL is that some new record beam currents for very high charge states were produced by 18 GHz or 18+14.5 GHz double frequency heating, such as 1 e microA of (129)Xe(43+), 22 e microA of (209)Bi(41+), and 1.5 e microA of (209)Bi(50+). To further enhance the performance of SECRAL, a 24 GHz/7 kW gyrotron microwave generator was installed and SECRAL was tested at 24 GHz. Some promising and exciting results at 24 GHz with new record highly charged ion beam intensities were produced, such as 455 e microA of (129)Xe(27+) and 152 e microA of (129)Xe(30+), although the commissioning time was limited within 3-4 weeks and rf power only 3-4 kW. Bremsstrahlung measurements at 24 GHz show that x-ray is much stronger with higher rf frequency, higher rf power. and higher minimum mirror magnetic field (minimum B). Preliminary emittance measurements indicate that SECRAL emittance at 24 GHz is slightly higher that at 18 GHz. SECRAL has been put into routine operation at 18 GHz for heavy ion research facility in Lanzhou (HIRFL) accelerator complex since May 2007. The total operation beam time from SECRAL for HIRFL accelerator has been more than 2000 h, and (129)Xe(27+), (78)Kr(19+), (209)Bi(31+), and (58)Ni(19+) beams were delivered. All of these new developments, the latest results, and long-term operation for the accelerator have again demonstrated that SECRAL is one of the best in the performance of ECR ion source for highly charged heavy ion beam production

  14. New development of advanced superconducting electron cyclotron resonance ion source SECRAL (invited)

    Superconducting electron cyclotron resonance ion source with advance design in Lanzhou (SECRAL) is an 18-28 GHz fully superconducting electron cyclotron resonance (ECR) ion source dedicated for highly charged heavy ion beam production. SECRAL, with an innovative superconducting magnet structure of solenoid-inside-sextupole and at lower frequency and lower rf power operation, may open a new way for developing compact and reliable high performance superconducting ECR ion source. One of the recent highlights achieved at SECRAL is that some new record beam currents for very high charge states were produced by 18 GHz or 18+14.5 GHz double frequency heating, such as 1 e μA of 129Xe43+, 22 e μA of 209Bi41+, and 1.5 e μA of 209Bi50+. To further enhance the performance of SECRAL, a 24 GHz/7 kW gyrotron microwave generator was installed and SECRAL was tested at 24 GHz. Some promising and exciting results at 24 GHz with new record highly charged ion beam intensities were produced, such as 455 e μA of 129Xe27+ and 152 e μA of 129Xe30+, although the commissioning time was limited within 3-4 weeks and rf power only 3-4 kW. Bremsstrahlung measurements at 24 GHz show that x-ray is much stronger with higher rf frequency, higher rf power. and higher minimum mirror magnetic field (minimum B). Preliminary emittance measurements indicate that SECRAL emittance at 24 GHz is slightly higher that at 18 GHz. SECRAL has been put into routine operation at 18 GHz for heavy ion research facility in Lanzhou (HIRFL) accelerator complex since May 2007. The total operation beam time from SECRAL for HIRFL accelerator has been more than 2000 h, and 129Xe27+, 78Kr19+, 209Bi31+, and 58Ni19+ beams were delivered. All of these new developments, the latest results, and long-term operation for the accelerator have again demonstrated that SECRAL is one of the best in the performance of ECR ion source for highly charged heavy ion beam production. Finally the future development of SECRAL will be

  15. Continuum spectra analysis of (p, d) and (n, d) reactions on Bi in several tens of MeV energy region

    Theoretical analyses of the double differential cross sections for proton and neutron induced deuteron pickup reactions on 209Bi are described. Neutron induced reaction cross-section data were analyzed at incident energies from about 41 MeV to 65 MeV and at 20deg laboratory angle, while proton induced reaction cross-section data were analyzed at the incident energy of 42 MeV and at 25deg laboratory angle. Spectrum regions are treated in the direct reaction scheme, i.e., several tens of MeV energy region. The double differential cross section - energy spectra were analyzed using the DWBA-based cross sections and the asymmetric Lorentzian form strength response function having energy dependent spreading width. Both the (n,d) and (p,d) spectra are fairly well reproduced by the theoretical calculations in the tens of MeV energy region. (author)

  16. A route for polonium 210 production from alpha-particle irradiated bismuth-209 target

    A method is proposed for production of polonium-210 via the 209Bi(α,3n)210 At nuclear reaction. Bombardment of a bismuth-209 target was performed with a 37 MeV alpha-particle beam that leads to the production of astatine-210 (T1/2 = 8.1 h), which decays to polonium-210. It is purified from the bismuth target matrix by employing liquid-liquid extraction using tributyl phosphate (TBP) in para-xylene from 7 M hydrochloric acid. Back extraction of polonium-210 was performed by 9 M nitric acid. This method allows to purify a tracer amount of Po-210 (2.6 x 10-13 mol) from macroscopic amount of Bi (2.8 x 10-2 mol).

  17. New result in the production and decay of an isotope, 278113, of the 113th element

    An isotope of the 113th element, i.e., 278113, was produced in a nuclear reaction with a 70Zn beam on a 209Bi target. We observed six consecutive α-decays following the implantation of a heavy particle in nearly the same position in the semiconductor detector under an extremely low background condition. The fifth and sixth decays are fully consistent with the sequential decays of 262Db and 258Lr in both decay energies and decay times. This indicates that the present decay chain consisted of 278113, 274Rg (Z=111), 270Mt (Z=109), 266Bh (Z=107), 262Db (Z=105), and 258Lr (Z=103) with firm connections. This result, together with previously reported results from 2004 and 2007, conclusively leads to the unambiguous production and identification of the isotope 278113 of the 113th element. (author)

  18. Investigation of Neutron Spectra and Transmutation of ^{129}I, ^{237}Np and Other Nuclides with 1.5 GeV Protons from the Dubna Nuclotron Using the Electronuclear Setup "Energy plus Transmutation"

    Krivopustov, M I; Balabekyan, A R; Batusov, Yu A; Bielewicz, M; Brandt, R; Chaloun, P; Chultem, D; Dwivedi, K K; Elishev, A F; Fragopoulou, M; Henzl, V; Henzlová, D; Kalinnikov, V G; Kievets, M K; Krása, A; Krizek, F; Kugler, A; Manolopoulou, Metaxia; Mariin, I I; Nourreddine, A; Odoj, R; Pavliouk, A V; Pronskikh, V S; Robotham, H; Siemon, K; Szuta, M; Stegailov, V I; Solnyshkin, A A; Sosnin, A N; Stoulos, S; Tsoupko-Sitnikov, V M; Tumendelger, T; Wojecehowski, A; Wagner, V; Wan, J S; Westmeier, W; Zamani-Valasiadou, M; Kumawat, H; Kumar, V; Zaverioukha, O S; Zhuk, I V

    2004-01-01

    Experiments which are part of the scientific program "Investigations of physical aspects of electronuclear method of energy production and transmutation for radioactive waste of atomic energetics using relativistic beams from the JINR Synchrophasotron/Nuclotron" (project "Energy plus Transmutation") are described. A large lead target surrounded by a four-section uranium blanket with total weight of 206.4 kg natural uranium was irradiated with 1.5 GeV protons from the new cryogenic accelerator Nuclotron. Radiochemical sensors were exposed to the secondary particle fluences inside and on top of the target assembly. Two long-lived radioactive waste of atomic energetics sensors ^{129}I and ^{237}Np (approximately 1 g weight each) and stable nuclides ^{27}Al, ^{59}Co, ^{127}I, ^{139}La, ^{197}Au and ^{209}Bi as well as natural and enriched uranium were used. In addition, various solid state nuclear track detectors and nuclear emulsions were exposed simultaneously. The experimental results confirm the theoretical e...

  19. Neutron-Induced Fission Cross Sections of Nuclei in the Vicinity of 208Pb at Incident Energies below 60 MeV

    Ryzhov, Igor V.; Tutin, Gennady A.; Eismont, Vilen P.; Mitryukhin, Andrey G.; Oplavin, Valery S.; Soloviev, Sergey M.; Meulders, Jean-Pierre; El Masri, Youssef; Keutgen, Thomas; Prieels, René; Nolte, Ralf

    2005-05-01

    Neutron-induced fission cross sections of 205Tl, 204, 206, 207, 208Pb, and 209Bi have been measured at incident energies of 32.8, 45.3, and 59.9 MeV. The measurements were performed at the Louvain-la-Neuve neutron beam facility using the 7Li (p, n) reaction as neutron source. Fission fragments were detected with a multi-section Frisch-gridded ionization chamber (MFGIC). Neutron fluence measurements were based on the 238U(n, f) reaction. The neutron fluence monitoring procedure was asserted by crosscheck measurement, in which the 59.9-MeV neutron beam fluence was simultaneously determined with the MFGIC and with a fission chamber monitor calibrated relative to a proton-recoil telescope.

  20. Neutron-Induced Fission Cross Sections of Nuclei in the Vicinity of 208Pb at Incident Energies below 60 MeV

    Neutron-induced fission cross sections of 205Tl, 204, 206, 207, 208Pb, and 209Bi have been measured at incident energies of 32.8, 45.3, and 59.9 MeV. The measurements were performed at the Louvain-la-Neuve neutron beam facility using the 7Li (p, n) reaction as neutron source. Fission fragments were detected with a multi-section Frisch-gridded ionization chamber (MFGIC). Neutron fluence measurements were based on the 238U(n, f) reaction. The neutron fluence monitoring procedure was asserted by crosscheck measurement, in which the 59.9-MeV neutron beam fluence was simultaneously determined with the MFGIC and with a fission chamber monitor calibrated relative to a proton-recoil telescope

  1. BISERM version 2. Nuclear data library for evaluation of radiation effects in materials induced by neutrons of intermediate

    This document describes the cross-section data library for studies of radiation effects induced by intermediate energy neutrons. The library contains hydrogen, helium-3 and helium-4 production cross-sections as well as nonelastic and total displacement cross-sections for neutrons in the energy range from threshold to 1 GeV. The cross-sections are given for 259 isotopes from 27Al to 209Bi. All this information is given in 18 compressed files plus one file with the catalogue of the data. The library was composed at the Institute of Nuclear Power Engineering in Obninsk, Russia. It is available on one PC diskette from the IAEA Nuclear Data Section costfree upon request. It requires 4 Mb of disk space after decompression. (author)

  2. A 6-MJ P4 target for heavy ion inertial fusion

    A new target option for energy applications of the heavy ion inertial fusion is analyzed. It has a spherical hohlraum and is irradiated by ion beams along the directions of the zeros of the fourth Legendre polynomial P4. The target performance is simulated with a one-dimensional (1-D) three-temperature hydrodynamics code and with a two-dimensional view factor code. Its efficiency is shown to depend crucially on the structure of the hohlraum wall which, simultaneously, plays a role of the X-ray converter. For the optimized pulse power profile, a 1-D energy gain of G = 78 is calculated with the input energy of Edr = 6.1 MJ in the form of 5 GeV 209Bi ions focused on the target sphere with the outer radius of R = 6.37 mm. (author)

  3. Measuring the cross sections of heavy-metal spallation induced by deuterons with energies of 2, 2.94, and 3.5 GeV per nucleon

    Artyushenko, M. Yu.; Baldin, A. A.; Berlev, A. I.; Bukhal, O. V.; Voronko, V. A.; Gusak, K. V.; Zhuk, I. V.; Kudashkin, I. V.; Paraipan, M.; Potapenko, A. S.; Safronova, A. A.; Sotnikov, V. V.; Tyutyunnikov, S. I.

    2016-07-01

    The cross sections for the spallation of the heavy-metal nuclei 181Ta, 197Au, 207Pb, 209Bi, 232Th, and 238U induced by relativistic deuterons with energies of 2, 2.94, and 3.5 GeV per nucleon are measured using the deuteron beam from the Nuclotron accelerator of the JINR Laboratory of High Energy Physics in Dubna, Russia. The cross-section measurements employ a combined experimental technique involving the solidstate nuclear-track detectors and the activation gamma spectrometry. Adding our measurements to the database of experimental nuclear data will make it possible to test the computer codes used for selecting the parameters of the ADS-type facilities.

  4. Systematics of intermediate energy proton nonelastic and neutron total cross section

    In order to examine the Letaw intermediate energy proton nonelastic cross section systematic formula, we chose the following 12 nuclei: 12C, 16O, 27Al, 40Ca, 56Fe, 63Cu, 90Zr, 107Ag, 118Su, 181Ta, 208Pb, and 238U, which have more experimental data. In order to examine the Pearlstein intermediate energy neutron total cross section systematic formula, we chose the following 10 nuclei: 12C, 16O, 27Al, 56Fe, 63Cu, 107Ag, 181Ta, 208Pb, 209Bi, and 238U, which have more experimental data. New systematic formulas for intermediate energy proton nonelastic and neutron total cross sections are obtained. 11 refs, 22 figs

  5. Excitations of one-valence-proton, one-valence-neutron nucleus {sup 210}Bi from cold-neutron capture

    Cieplicka-Oryńczak, N. [INFN sezione di Milano, Via Celoria 16, 20133 Milano (Italy); Institute of Nuclear Physics, Polish Academy of Sciences, PL-31342 Kraków (Poland); Fornal, B.; Szpak, B. [Institute of Nuclear Physics, Polish Academy of Sciences, PL-31342 Kraków (Poland); Leoni, S.; Bottoni, S. [INFN sezione di Milano, Via Celoria 16, 20133 Milano (Italy); Università degli Studi di Milano, Via Celoria 16, 20133 Milano (Italy); Bazzacco, D. [Dipartimento di Fisica e Astronomia dell’Università, I-35131 Padova (Italy); INFN Sezione di Padova, I-35131 Padova (Italy); Blanc, A.; Jentschel, M.; Köster, U.; Mutti, P.; Soldner, T. [Institute Laue-Langevin, 6, rue Jules Horowitz, 38042 Grenoble Cedex 9 (France); Bocchi, G. [Università degli Studi di Milano, Via Celoria 16, 20133 Milano (Italy); France, G. de [GANIL, Bd. Becquerel, BP 55027, 14076 CAEN Cedex 05 (France); Simpson, G. [LPSC, Université Joseph Fourier Grenoble 1, CNRS/IN2P3, Institut National Polytechnique de Grenoble, F-38026 Grenoble Cedex (France); Ur, C. [INFN Sezione di Padova, Via F. Marzolo 8, I-35131 Padova (Italy); Urban, W. [Faculty of Physics, University of Warsaw, ul. Hoża 69, 02-681, Warszawa (Poland)

    2015-10-15

    The low-spin structure of one-proton, one-neutron {sup 210}Bi nucleus was investigated in cold-neutron capture reaction on {sup 209}Bi. The γ-coincidence measurements were performed with use of EXILL array consisted of 16 HPGe detectors. The experimental results were compared to shell-model calculations involving valence particles excitations. The {sup 210}Bi nucleus offers the potential to test the effective proton-neutron interactions because most of the states should arise from the proton-neutron excitations. Additionally, it was discovered that a few states should come from the couplings of valence particles to the 3{sup −} octupole vibration in {sup 208}Pb which provides also the possibility of testing the calculations involving the core excitations.

  6. Experimental and computer simulation study of radionuclide yields in the ADT materials irradiated with intermediate energy protons

    Titarenko, Yu.E.; Shvedov, O.V.; Batyaev, V.F. [Inst. for Theoretical and Experimental Physics, B. Cheremushkinskaya, Moscow (Russian Federation)] [and others

    1998-11-01

    The results of measurements and computer simulations of the yields of residual product nuclei in {sup 209}Bi, {sup 208,207,206,nat}Pb, {sup 65,63}Cu, {sup 59}Co thin targets irradiated by 0.13, 1.2 and 1.5 GeV protons are presented. The yields were measured by direct high-precision {gamma}-spectrometry. The process was monitored by the {sup 27}Al(p,x){sup 24}Na reaction. 801 cross sections are presented and used in comparisons between the reaction yields obtained experimentally and simulated by the HETC, GNASH, LAHET, INUCL, CEM95, CASCADE, NUCLEUS, YIELDX, QMD and ALICE codes. (author)

  7. Fissility of Bi, Pb, Au, Pt, W, Ta, V, and Ti nuclei measured with 100 MeV compton back-scattered photons

    Photofission cross sections of 209 Bi, nat Pb, 197 Au, nat Pt, nat W, 181 Ta, 51 V, and nat Ti nuclei have been measured at an incident photon energy of 100 MeV using monochromatic photons produced by Compton backscattering at the ROKK-1M facility (BINP, Novosibirsk). Detection of fission fragments has been performed by means of Makrofol track-etch detectors in close contact with metallic foils of the target elements. The values of fissility at 100 MeV deduced for the targets under investigation are found to range between 10-4 and 10-2. The present results show consistency with the fissility trends calculated for 69- and 600-MeV monoenergetic photons using a formalism based on the current two-step model for intermediate-energy photofission reactions. (author). 39 refs., 4 figs., 3 tabs

  8. Nuclear photofissility in the quasi-deuteron energy region

    Paiva, E. de; Tavares, O.A.P. [Centro Brasileiro de Pesquisas Fisicas (CBPF), Rio de Janeiro, RJ (Brazil); Terranova, M.L. [Universita di Roma Tor Vergata (Italy). Dipt. di Scienze e Tecnologie Chimiche

    2001-04-01

    A two hundred experimental photofissility data obtained in the quasi-deuteron region ({approx} 30 - 140 MeV) of photonuclear absorption covering the target nuclei {sup 27} Al, {sup n} {sup at} Ti, {sup 51} V, {sup 154} Sm, {sup 174} Yb, {sup n} {sup at} T Hf, {sup 181} Ta, n{sup a} {sup t} W, {sup nat} Re, {sup nat} Os, {sup n} {sup a} {sup t} Pt, {sup 197} Au, {sup na} {sup t} Tl, {sup 208} Pb, {sup nat} Pb and {sup 209} Bi have been analysed in the framework of the current, two-step model for intermediate-energy photofission reactions. The incoming photon is assumed to be absorber by a neutron-proton pair (Levinger's quasi-deuteron model), followed by a mechanism of evaporation-fission competition for the excited residual nuclei. The experimental features of photofissility have been reproduced successfully by the model. (author)

  9. Excitations of one-valence-proton, one-valence-neutron nucleus 210Bi from cold-neutron capture

    The low-spin structure of one-proton, one-neutron 210Bi nucleus was investigated in cold-neutron capture reaction on 209Bi. The γ-coincidence measurements were performed with use of EXILL array consisted of 16 HPGe detectors. The experimental results were compared to shell-model calculations involving valence particles excitations. The 210Bi nucleus offers the potential to test the effective proton-neutron interactions because most of the states should arise from the proton-neutron excitations. Additionally, it was discovered that a few states should come from the couplings of valence particles to the 3− octupole vibration in 208Pb which provides also the possibility of testing the calculations involving the core excitations

  10. A subject of activation cross section library for IRAC code system

    The IRAC code system has a major activation cross section library, ACSELA94, which has been calculated using ALICE-F code on the basis of selection of geometry depended hybrid models with conditions of 9 incident particles and 136 target nuclides in the range of 1H - 209Bi. The incident energies of light ions (1H, 2H, 4He) and neutrons are from threshold energy to 150 MeV, and of heavy ions (12C, 14N, 16O, 20Ne, 40Ar) are from threshold energy to 500 MeV, respectively. To obtain the general tendency of the calculated cross section, the sum total of individual isotope production cross sections was compared with nonelastic cross section. It was found that they are in good agreement with the both in which the mass number of target nuclides is from 15 to 185. Furthermore some subjects of the cross section in ACSELA94 were found out. (author)

  11. Study of giant resonances in heavy nuclei

    The electrodisintegration cross section for181Ta,208Pb and 209Bi was measured by counting the emitted neutrons, with incident electrons in the energy range 8-22 MeV. The data was analysed using the virtual photon method, in order to obtain a multipole decomposition and the intensities of Magnetic Dipole and Electric Quadrupole, isoscalar and isovector, in the Giant Resonance. The results obtained for the isovector Giant Quadrupole Resonance are compared with the measured photodisintegration cross section, using data from Saclay and Livermore. This comparision indicates that the photodisintegration data can be well explained assuming an isovector E2 Resonance located between 120 and 130 A-1/3 MeV, with an intensity of one isovector E2 sum. (author)

  12. Decay analysis of 9Be induced reactions using stable and non deformed targets

    The pursuit of investigation of decay of compound and non compound nuclear reactions inscribes the cogitation of various processes subsequent to collision between projectile and target nuclei. Hitherto extensive studies have been devoted to understand the structure aspect associated with numerous dominant reaction mechanisms of nuclei. The Decay cross-sections of 217Rn* and 218Fr* formed in reactions 9Be+208Pb and 9Be+209Bi have been studied in framework of DCM at energies varying from Ec.m=(42.0- 67.0) MeV where both the targets have same neutron magicity (N = 126) effect. All calculations have been done for β2-deformed choice of fragmentation and optimum orientation approach

  13. Mechanism of fission of neutron-deficient actinoids nuclides

    Sueki, Keisuke; Nakahara, Hiromichi [Tokyo Metropolitan Univ., Hachioji (Japan). Faculty of Science; Tanase, Masakazu; Nagame, Yuichiro; Shinohara, Nobuo; Tsukada, Kazuaki

    1996-01-01

    A heavy ion reaction ({sup 19}F+{sup 209}Bi) is selected. The reaction produces neutron-deficient {sup 228}U which is compound nucleus with a pair of Rb(z=37) and Cs(Z=55). Energy dissipation problem of nucleus was studied by measuring the isotope distribution of two fissile nuclides. Bismuth metal evaporated on aluminium foil was irradiated by {sup 19}F with the incident energy of 105-128 MeV. We concluded from the results that the excess energy of reaction system obtained with increasing the incident energy is consumed by (1) light Rb much more than Cs and (2) about 60% of energy is given to two fission fragments and the rest 40% to the translational kinetic energy or unknown anomalous {gamma}-ray irradiation. (S.Y.)

  14. Alternating parity bands in doubly odd 218Ac129 and octupole instability in the light actinide region

    High-spin states of doubly odd 218Ac129 have been investigated using in-beam α, γ and conversion electron spectroscopy techniques through the 209Bi(12(13)C,3(4)n) fusion-evaporation reactions. The level scheme of 218Ac shows three interconnected, alternating parity structures, each one linked by strong E1 transitions. Two of these bands are strikingly similar to the known scheme of the isotone 217Ra and this analogy is shown to persist for the pair 220Ac, 219Ra. The relation between the structure of 218Ac and its neighbors is thoroughly discussed showing that the first signals of octupole collectivity appear for N = 129. (orig.)

  15. Studies of giant multipole resonances with intermediate energy heavy ions

    Beene, J.R.

    1989-01-01

    The role of intermediate energy heavy ions in the study of giant multipole resonances is explored, with emphasis on gamma decay coincidence experiments. Experiments on /sup 208/Pb bombarded by 22 MeV/nucleon and 84 MeV/nucleon /sup 17/O are discussed and compared. The role of Coulomb excitation in the 84 MeV/nucleon data is emphasized and some consequences for study of isovector resonance strength are explored. A comparison of the excitation and decay of the isovector giant dipole resonance in /sup 208/Pb and /sup 209/Bi excited with 84 MeV/nucleon /sup 17/O scattering is presented. 19 refs., 15 figs., 1 tab.

  16. Measurement of neutron-induced activation cross-sections using spallation source at JINR and neutronic validation of the Dubna code

    Manish Sharma; V Kumar; H Kumawat; J Adam; V S Barashenkov; S Ganesan; S Golovatiouk; S K Gupta; S Kailas; M I Krivopustov; H S Palsania; V Pronskikh; V M Tsoupko-Sitnikov; N Vladimirova; H Westmeier; W Westmeier

    2007-02-01

    A beam of 1 GeV proton coming from Dubna Nuclotron colliding with a lead target surrounded by 6 cm paraffin produces spallation neutrons. A Th-foil was kept on lead target (neutron spallation source) in a direct stream of neutrons for activation and other samples of 197Au, 209Bi, 59Co, 115In and 181Ta were irradiated by moderated beam of neutrons passing through 6 cm paraffin moderator. The gamma spectra of irradiated samples were analyzed using gamma spectrometry and DEIMOS software to measure the neutron cross-section. For this purpose neutron fluence at the positions of samples is also estimated using PREPRO software. The results of cross-sections for reactions 232Th(, ), 232Th(, 2), 197Au(, ), 197Au(, ), 197Au(, ), 59Co(, ), 59Co(, ), 181Ta(, ) and 181Ta(, ) are given in this paper. Neutronics validation of the Dubna Cascade Code is also done using cross-section data by other experiments.

  17. Status of heavy element research using GARIS at RIKEN

    A gas-filled recoil separator GARIS was installed at the RIKEN Linear Accelerator facility. Using the separator, two reactions, 208Pb(64Ni, 1n), and 209Bi(64Ni, 1n), were investigated. In the first reaction we observed fourteen α-decay chains which were assigned to be the decays starting from the isotope 271Ds(Z=110). The α-decay energies as well as the decay times coincided well with the values reported by GSI group. Existence of an isomeric state in 271Ds became clear from the present work. In the second reaction we have observed 14 α-decay chains that can be assigned to subsequent decays from 272111. The present result is the first clear confirmation for the discovery of 272111 and its α-decay products, 264Bh and 268Mt, reported previously by a GSI group. New information on their half-lives and decay energies is presented

  18. JINR Rapid Communications. Collection

    The present collection of rapid communications from JINR, Dubna, contains nine separate reports on quasi-classical description of one-nucleon transfer reactions with heavy ions, elastic and inelastic scattering in the high energy approximation, experimental study of fission and evaporation cross sections for 6 He + 209 Bi reaction, d↑ + 12 C → p + X at Θp = 0o in the region of high internal momenta in the deuteron, the Nuclotron internal targets, actively screened superconducting magnets, using of polarized target in backward elastic dp scattering, application of transputers in the data acquisition system of the INESS-ALPHA spectrometer, narrow dibaryon resonances with isotopic spin I=2. 93 refs., 27 figs., 4 tabs

  19. A study on the characteristics of beryllium isotopes by using extended optical model analyses at near-coulomb-barrier energies

    Within the framework of an extended optical model, simultaneous χ2 analyses were performed for elastic scattering and fusion cross section data for the 10Be+208Pb system at near-Coulomb-barrier energies. The result showed that both direct reaction (DR) and fusion potentials extracted from χ2 analyses separately satisfied the dispersion relation and that the expected threshold anomaly appeared in both the DR and the fusion parts. Using the extracted DR potential, we examined the effects of projectile breakup on the fusion cross-sections, σexpF . Finally, the present results for the 10Be + 208Pb system were compared with the analysis previously made for the 9Be + 208Pb and the 9Be + 209Bi systems.

  20. Extended optical model analyses of elastic scattering, direct reaction, and fusion cross sections for the 9Be+208Pb system at near-Coulomb-barrier energies

    Based on the extended optical model approach in which the polarization potential is decomposed into direct reaction (DR) and fusion parts, simultaneous χ2 analyses are performed for elastic scattering, DR, and fusion cross section data for the 9Be+208Pb system at near-Coulomb-barrier energies. Similar χ2 analyses are also performed by taking into account only the elastic scattering and fusion data as was previously done by the present authors, and the results are compared with those of the full analysis including the DR cross section data as well. We find that the analyses using only elastic scattering and fusion data can produce very consistent and reliable predictions of cross sections, particularly when the DR cross section data are incomplete. Discussions are also given on the results obtained from similar analyses made earlier for the 9Be+209Bi system

  1. Development of an odd-Z-projectile reaction for heavy element synthesis: 208Pb(64Ni, n)271Ds and 208Pb(65Cu, n)272111

    Seven 271Ds decay chains were identified in the bombardment of 208Pb targets with 311.5- and 314.3-MeV 64Ni projectiles using the Berkeley Gas-filled Separator. These data, combined with previous results, provide an excitation function for this reaction. From these results, an optimum energy of 321 MeV was estimated for the production of 272111 in the reaction 208Pb(65Cu, n). One decay chain was observed, resulting in a cross section of 1.7-1.4+3.9 pb. This experiment confirms the discovery of element 111 by the Darmstadt group who used the 209Bi(64Ni, n)272111 reaction

  2. Elaboration of a model of the nuclear fragmentation and application to the method of isotopic separation of projectile fragments

    In this thesis the experimental results on the cross sections for the production of 36P in the fragmentation of 403 MeV/u 40Ar on a carbon target are presented. Furthermore some models of the nuclear fragmentation are elaborated and compared by means of experimental data for the production of gold and cerium isotopes in the reaction 12C+209Bi at 400 MeV/u, of chlorine, sulfur, aluminium, magnesium, and oxygen isotopes in the reactions 40Ar+12C at 600 MeV/u and 48Ca+9Be at 212 MeV/u, and of cobalt, manganese, vanadium, and scandium isotopes together with the charge distributions for A=43 and A=44 in the reactions 40Ar+64Cu at 2 GeV/u and 56Fe+12C at 600 MeV/u. (HSI)

  3. Inclusive measurement of (p,πsup(-)xn) double charge exchange reactions on bismuth from threshold to 800 MeV

    The energy dependence of the total angle-integrated cross section for the production of astatine isotopes from (p,πsup(-)xn) double charge exchange reactions on bismuth (sup(209)Bi) was measured from 120 to 800 MeV using activation and radiochemical techniques. Chemical yields were estimated by direct radioassaying of sup(211)At activity in thin (approximately 1 mg/cmsup(2)), irradiated bismuth targets. Calculations of the contributions of secondary (2-step) reactions to these measured astatine yields were performed, based partially upon the observed sup(211)At activity although even at the highest energies, the contribution to products lighter than sup(207)At was negligible. These data for products with as many as 7 neutrons removed from the doubly coherent product (sup(210)At) display nearby gaussian shapes for the mass distributions of the astatine residues with the maximum occurring for about sup(204)At. The most probable momentum transfer deduced from these distributions for the initial πsup(-) production step was 335 MeV/c. The observed excitation functions display a behaviour similar to that observed for the yield of sup(210)Po from a (p,πsup(O)) reaction on sup(209)Bi, but radically different from that observed for inclusive πsup(-) reactions on a heavy nucleus. These data are discussed in terms of recent theoretical approaches to negative pion production from bismuth. In addition, a simple, schematic model is developed to treat the rapidly decreasing percentage of the total inclusive πsup(-) emission which is observed for this double charge exchange reaction. This model reflects the capacity of a nucleus to a source of internal energetic protons

  4. Experimental and Theoretical Study of the Residual Product Nuclide Yields in 100-2600 MeV Proton-Irradiated Thin Targets

    Titarenko, Y E; Karpikhin, E I; Zhivun, V M; Koldobsky, A B; Mulambetov, R D; Kvasova, S V; Fischenko, D V; Barashenkov, V S; Mashnik, S G; Prael, R E; Sierk, A J; Yasuda, H; Saitó, M; Titarenko, Yury E.; Batyaev, Vyacheslav F.; Karpikhin, Evgeny I.; Zhivun, Valery M.; Koldobsky, Aleksander B.; Mulambetov, Ruslan D.; Kvasova, Svetlana V.; Fischenko, Dmitry V.; Barashenkov, Vladilen S.; Mashnik, Stepan G.; Prael, Richard E.; Sierk, Arnold J.; Yasuda, Hideshi; Saito, Masaki

    2002-01-01

    The work is aimed at experimental determining and computer simulating the independent and cumulative yields of residual product nuclei in the target and structure materials of the transmutation facilities driven by high-current accelerators. The ITEP U-10 accelerator was used in 48 experiments to obtain more than 4000 values of the yields of radioactive residual product nuclei in 0.1-2.6 GeV proton-irradiated thin 182,183,184,186-W, nat-W, 56-Fe, 58-Ni, 93-Nb, 232-Th, nat-U, 99-Tc, 59-Co 63,65-Cu, nat-Hg, 208-Pb, and 27-Al targets. The results of verifying the LAHET, CEM95, CEM2k, CASCADE, CASCADE/INPE, YIELDX, HETC, INUCL, and other simulation codes are presented.

  5. Target accuracy of MA nuclear data and progress in validation by post irradiation experiments with the fast reactor 'JOYO'

    This paper presents a discussion about the target accuracy of MA nuclear data for fast reactor cycle system development, as well as the validation work on those nuclear data by PIE analyses. The PIE analyses are in progress on fuels and MA samples (237Np, 241Am, 243Am, 244Cm) irradiated at the experimental fast reactor 'JOYO'. The analysis result on the first examined MA sample suggested the necessity of re-evaluation of the isomeric ratio for 241Am capture reaction both in ENDF/B-VI and in JENDL-3.3. The above result contributes to the uncertainty-reduction both of burnup reactivity loss and of gamma energy release from fuel assemblies. (author)

  6. Up-to-date status and problems of the experimental nucleon-induced fission cross section data base at intermediate energies

    The review presents a critical consideration of all experimental data known to the authors by the end of 1998, for nuclei from 181Ta to 243Am and in the projectile energy range up to 30 GeV for protons and up to 450 MeV for neutrons. Special attention was paid to elements in the W-Bi region which are regarded as the most prospective materials for neutron-producing targets for ADS. The experimental data on nucleon-induced fission fragment angular distributions were systematized for the first time for projectile energies above 20 MeV . Data on neutron-induced fission cross sections and angular distributions are compared with proton-induced data. The large dispersion of some results and other problems of experimental data base are discussed. The possibilities of new experiments with proton beams and quasi-monoenergetic neutron beams are discussed

  7. New isotope 265Bh

    A new isotope 265Bh was produced and identified at the Sector Focus Cyclotron of the Heavy Ion Research Facility in Lanzhou. This experiment was performed via the reaction of an 243Am target with 168 MeV 26Mg ions. Identification was made by observation of correlated α -particle decays between the new isotope 265Bh and its 261Db and 257Lr daughter nuclei using a set of rotating-wheels system. A total of 8 correlated decay events of 265Bh and 4 decay events of 264Bh were observed. 265Bh decays with a 0.94 -0.31+0.70 s half-life by emission of α-particles with an average energy of 9.24 ±0.05 MeV. The half-life and α decay energy of 265Bh from this experiment are in agreement with theoretical predictions. (orig.)

  8. Excretion analysis of a case of old internal contamination with 241Am

    Two radiochemical methods were used in parallel to determine 241Am in the urine and feces of a person who had been internally contaminated with that radionuclide 25 years before. Both methods used feces and urine mineralizations. The first method comprised coprecipitation of Am together with alkaline earth metals by using bismuth phosphate, single separation on a catex, double separation on an anex, and extraction of Am into TTA in benzene. The other method consists of double coprecipitation of Am, viz., with calcium oxalate and with Fe(OH)3, followed by double separation on an anex and a single separation on a catex. In both methods, 243Am served as the recovery indicator and in the preparation of electrodeposition samples. The samples were measured by alpha spectrometry using PIPS detectors

  9. Analysis of Intermediate Energy Photonuclear Reactions

    The Cascade-Exciton Model (CEM) of nuclear reactions has been extended to describe photonuclear disintegration at intermediate energies. Using the CEM and the ORNL version of the Intranuclear Cascade Model for incident energies higher than the giant dipole resonance (GDR) region, and a group theory formalism based on the Interacting Boson Model in the GDR region, we have analyzed a variety of data for reactions induced by photons with energies up to ∼ 1.2 GeV and target-nuclei from 12C to 243Am. The contributions of different photon absorption mechanisms and the relative role of different particle production mechanisms in these reactions are discussed. 41 refs., 7 figs., 1 tab

  10. Production and Identification of New Isotope 265Bh(Z=107)

    FanHongmei; WuXiaolei; GanZaiguo; GuoJunsheng; QinZhi; LeiXiangguo; LiuHongye; GuoBin; XuHuageng; ChenRuofu; DongChengfu; ZhangFuming; WangHualei; XieChengying; FengZhaoqing; ZhenYong; SongLitao; LuoPeng; XuHushan; ZhouXiaohong; JinGenmin; RenZhongzhou

    2003-01-01

    New Isotope 265Bh was produced in bombardment of a 243Am target with 168 MeV 26Mg ions. The experiment was carried out at the Sector Focus Cyclotron of Heavy Ion Research Facility in Lanzhou in 2003. The reaction products were transported and collected by using helium-jet technique and a set of rotating wheel system. Identification was made by observation of correlated a-particles between the new isotope 265Bh and its 261Db and 257Lr daughter nuclei. A parent-daughter searching mode was used to facilitate detection of α-α correlations. A total of four pairs of PIPS detector (200mm2 active area) were used to measure the kinetic energy of a particles. The a particle energy resolution was about 40 keV for the top detectors and 100 keV for the bottom detectors because of energy degradation in the polypropylene foil.

  11. Alpha-decay properties of 266Bh

    The isotope of 266Bh was produced and identified definitely in bombardments of 243Am target with 162 MeV 26Mg ions at HIRFL. Identification was made by observation of correlated α-particle decays between the Bh isotopes and their Db and Lr daughters using a rotating wheel system. The measured α energy for 266Bh is (9.03 ± 0.08) MeV, and this value close to the 9.07 MeV for 266Bh observed in the first chain of element 113 at RIKEN. The half-life of 266Bh is (0.66)-0.26+0.59s. The Qα value derived from this experiment fits well into the general trend in a 'Qα-N systematics' for the isotopes with Z=107. (authors)

  12. MANTRA: An Integral Reactor Physics Experiment to Infer Actinide Capture Cross-sections from Thorium to Californium with Accelerator Mass Spectrometry

    G. Youinou; C. McGrath; G. Imel; M. Paul; R. Pardo; F. Kondev; M. Salvatores; G. Palmiotti

    2011-08-01

    The principle of the proposed experiment is to irradiate very pure actinide samples in the Advanced Test Reactor at INL and, after a given time, determine the amount of the different transmutation products. The determination of the nuclide densities before and after neutron irradiation will allow inference of effective neutron capture cross-sections. This approach has been used in the past and the novelty of this experiment is that the atom densities of the different transmutation products will be determined using the Accelerator Mass Spectrometry technique at the ATLAS facility located at ANL. It is currently planned to irradiate the following isotopes: 232Th, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 243Am, 244Cm and 248Cm.

  13. Generation of an actinide isotopes cross section set for fast reactor calculations using data from ENDL and ENDF/B-IV

    A Bondarenko format 25-group cross section set of actinide isotopes was generated for the fuel cycle evaluation and the incineration study in fast reactor systems. Evaluated Nuclear Data Library of Lawrence Livermore Laboratory (U.S.) was used as the source data. The actinide isotopes treated are the following 28: Th-232, U-233, U-234, U-235, U-236, U-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-243, Am-241, Am-242, Am-243, Cm-242, Cm-243, Cm-245, Cm-246, Cm-247, Cm-248, Bk-249, Cf-249, Cf-250, Cf-251, Cf-252 and a pseudo-fission product. ENDF/B-IV was used for U-238. The set was then collapsed to one energy group using a large LMFBR core spectrum for the comparison with other one-group sets. (author)

  14. Combined procedure using radiochemical separation of plutonium, americium and uranium radionuclides for alpha-spectrometry

    Radiochemical separation of Pu, Am and U was tested from synthetic solutions and evaporator concentrate samples from nuclear power plants for isolation of each of them for alpha-spectrometry analysis. The separation was performed by anion-exchange chromatography, extraction chromatography, using TRU resin, and precipitation techniques. The aim of the study was to develop a sensitive analytical procedure for the sequential determination of 242Pu, 238Pu, 239+240Pu, 241Am and 235,238U in radioactive wastes. 238Pu, 242Pu, 243Am and 232U were used as tracers. The measurements of α emitting radionuclides were performed by semiconductor detector that is used especially when spectrometric information is needed. For synthetic solutions the chemical recovery was based on associated iron concentration and was about 93%. (author)

  15. Development of fission micro-chambers for nuclear waste incineration studies

    The incineration of transuranic elements by neutron induced fission is a very promising way to reduce long-term radiotoxicity of nuclear waste. The Mini-Inca aims to outline the ideal physical conditions to transmute minor actinides, mainly 241-243Am, 237Np and 244-245Cm. For some actinides there are large discrepancies of neutron cross sections taken from different evaluated nuclear data libraries. These cross sections play a dominant role in transmutation systems. For instance, a factor 20 was pointed out for the 242gsAm thermal neutron capture cross section from JEF-2.2 (5500 barns) and ENDF-B/VI (250 barns) libraries. Computer simulations can lead to controversial results depending on the nuclear data library that was used. To measure the incineration rate of minor actinides, and to provide an unambiguous experimental reference, fission micro-chambers are of great interest. (author)

  16. Analysis of americium-beryllium neutron source composition using the FRAM code

    Hypes, P. A. (Philip A.); Bracken, D. S. (David S.); Sampson, Thomas E.; Taylor, W. A. (Wayne A.)

    2002-01-01

    The FRAM code was originally developed to analyze high-resolution gamma spectra from plutonium items. Its capabilities have since been expanded to include analysis of uranium spectra. The flexibility of the software also enables a capable spectroscopist to use FRAM to analyze spectra in which neither plutonium nor uranium is present in significant amounts. This paper documents the use of FRAM to determine the {sup 239}Pu/{sup 241}Am, {sup 243}Am/{sup 241}Am, {sup 237}Np/{sup 241}Am, and {sup 239}Np/{sup 241}Am ratios in americium-beryllium neutron sources. The effective specific power of each neutron source was calculated from the ratios determined by FRAM in order to determine the americium mass of each of these neutron sources using calorimetric assay. We will also discuss the use of FRAM for the general case of isotopic analysis of nonplutonium, nonuranium items.

  17. Discovery of the new element Z=117 and confirmation of 115

    The discovery of the new chemical element with atomic number Z=117 is presented. The isotopes 293117 and 294117 were produced in fusion reactions between 48Ca and 249Bk. The 249Bk was produced in the High Flux Isotope Reactor and chemically separated at Oak Ridge. Decay chains involving eleven new nuclei were identified by means of the Dubna Gas-Filled Recoil Separator. The measured decay properties show a strong rise of stability for superheavy nuclei toward N=184.The reaction 243Am+48Ca was studied at three energies. Twenty one decay chains of 288115 and one decay chain of 289115 were observed to confirm the earlier discoveries of Z=115 and 117. (authors)

  18. Actinide targets for the synthesis of super-heavy elements

    Roberto, J. B.; Alexander, C. W.; Boll, R. A.; Burns, J. D.; Ezold, J. G.; Felker, L. K.; Hogle, S. L.; Rykaczewski, K. P.

    2015-12-01

    Since 2000, six new super-heavy elements with atomic numbers 113 through 118 have been synthesized in hot fusion reactions of 48Ca beams on actinide targets. These target materials, including 242Pu, 244Pu, 243Am, 245Cm, 248Cm, 249Cf, and 249Bk, are available in very limited quantities and require specialized production and processing facilities resident in only a few research centers worldwide. This report describes the production and chemical processing of heavy actinide materials for super-heavy element research, current availabilities of these materials, and related target fabrication techniques. The impact of actinide materials in super-heavy element discovery is reviewed, and strategies for enhancing the production of rare actinides including 249Bk, 251Cf, and 254Es are described.

  19. Extended probabilistic system assessment calculations within the SKI project-90

    The probabilistic system assessment calculation reported in the SKI Project-90 final documents were restricted to the following nuclides: 14C, 129I, 135Cs, 237Np and 240Pu. In this report we have extended those calculations to another five nuclides: 79Se, 243Am, 240Pu, 93Zr and 99Tc. The execution of probabilistic assessment calculations integrated in the context of SKIs first safety analysis exercise of an hypothetic final repository for high-level nuclear waste in Sweden, was a learning experience of relevance for the conduction of probabilistic safety assessment in future exercises. Some major conclusions and viewpoints of future need related with probabilistic assessment were withdrawn from this work and are presented in our report

  20. Fission cross-section measurements on 233U and minor actinides at the CERN n-TOF facility

    Neutron-induced fission cross-sections of minor actinides have been measured at the white neutron source n-TOF at CERN, Geneva. The studied isotopes include 233U, interesting for Th/U based nuclear fuel cycles, 241,243Am and 245Cm, relevant for transmutation and waste reduction studies in new generation fast reactors (Gen-IV) or Accelerator Driven Systems. The measurements take advantage of the unique features of the n-TOF facility, namely the wide energy range, the high instantaneous neutron flux and the low background. Results for the involved isotopes are reported from ∼30 meV to around 1 MeV neutron energy. The measurements have been performed with a dedicated Fission Ionization Chamber (FIC), relative to the standard cross-section of the 235U fission reaction, measured simultaneously with the same detector. Results are here reported. (authors)

  1. A brief review of ultra-rare alpha decay detection technique

    Three approaches to the measurement of rare alpha decaying products produced in heavy-ion induced nuclear reactions are described. One is based on a chemical extraction and following deposition of the nuclides under investigation onto the surface of the detector, whereas the second one is associated with long-lived products implanted into silicon detectors by using the electromagnetic separation technique. The third approach relates with an application of real-time mode detection of correlated energy-time-position recoil-alpha sequences from 48Ca-induced nuclear reactions with actinide targets, like 242,244Pu, 245,248Cm, 243Am, and 249Cf. Namely with this technique it has became possible to provide a radical suppression of backgrounds in the full fusion (3-5n) reactions aimed at the synthesis of superheavy elements with Z = 113-118

  2. A Brief Review of Ultra-Rare Alpha Decay Detection Technique

    Tsyganov, Yu S

    2006-01-01

    Three approaches to the measurement of a rare alpha decaying products produced in heavy-ion induced nuclear reactions are described. One is based on a chemical extraction and following deposition of the nuclides under investigation onto the surface of the detector, whereas the second one is associated with long-lived products implanted into silicon detectors by using the electromagnetic separation technique. The third approach relates with an application of real-time mode detection of correlated energy-time-position recoil-alpha sequences from $^{48}$Ca-induced nuclear reactions with actinide targets, like $^{242, 244}$Pu, $^{245,248}$Cm, $^{243}$Am, and $^{249}$Cf. Namely with this technique it has became possible to provide a radical suppression of backgrounds in the full fusion (3-5$n$) reactions aimed at the synthesis of superheavy elements with Z=113-118.

  3. The solvent extraction of Am(VI) using centrifugal contactors

    An engineering-scale centrifugal contactor test bed was built at Idaho National Laboratory to perform solvent extraction testing for the partitioning of hexavalent americium. The raffinate simulant feed was spiked with 243Am and 139Ce and treated with sodium bismuthate to oxidize americium to Am(VI), filtered and contacted with 1 M DAAP/dodecane using centrifugal contactors. Extraction efficiency comparable to batch contacts was obtained, indicating for the first time that Am(VI) can be maintained under process conditions. Contrary to expectations, stripping was not as effective as expected. However, this result may actually be advantageous to process design, since a scrub step, previously thought to be impossible due to rapid Am(VI) reduction, may now be considered for future flowsheet tests. (author)

  4. Rapid determination of 237Np in soil samples by multi-collector inductively-coupled plasma mass spectrometry and gamma spectrometry

    A radiochemical procedure is developed for the determination of 237Np in soil with multi-collector inductively-coupled plasma mass spectrometry (MC-ICP-MS) and gamma-spectrometry. 239Np (milked from 243Am) was used as an isotopic tracer for chemical yield determination. The neptunium in the soil is separated by thenoyl-trifluoracetone extraction from 1 M HNO3 solution after reducing Np to Np(IV) with ferrous sulfamate, and then purified with Dowex 1 x 2 anion exchange resin. 239Np in the resulting solution is measured with gamma-spectrometry for chemical yield determination while the 237Np is measured with MC-ICP-MS. Measurement results for soil samples are presented together with those for two reference samples. By comparing the determined value with the reference value of the 237Np activity concentration, the feasibility of the procedure was validated. (author)

  5. Application of high resolution inductively coupled plasma mass spectrometry to the measurement of long-lived radionuclides

    The radioactivity determination of long-lived radionuclides in environmental samples is difficult due to their low concentration and low specific activity. Limits of detection (DL) for long-lived radionuclides (99Tc, 226Ra, 232Th, 237Np, 238U, 243Am) in standard solutions using Inductively Coupled Plasma Mass Spectrometry with a double focusing mass analyzer (HR-ICP-MS) with ultrasonic nebulizer were calculated. DL of most nuclides were under the fg g-1 level. It seems that the analysis by using HR-ICP-MS has the advantage of detection for low level radio nuclides whole half life is more than 1000 y. This method was applied to 226Ra analysis in hot spring waters and 230Th in lake sediments analysis after a simple chemical separation. (author)

  6. Three sources and three components of success in detection of ultra-rare alpha decays at the Dubna Gas-Filled Recoil separator

    Tsyganov, Y S

    2015-01-01

    General philosophy of procedure of detecting rare events in the recent experiments with 48Ca projectile at the Dubna Gas-Filled Recoil Separator(DGFRS) aimed to the synthesis of superheavy elements (SHE) has been reviewed. Specific instruments and methods are under consideration. Some historical sources of the successful experiments for Z=112-118 are considered too. Special attention is paid to application of method of active correlations in heavy-ion induced complete fusion nuclear reactions. Example of application in Z=115 experiment is presented. Brief description of the 243Am + 48Ca -> 291-x115+xn experiment is presented too. Some attention is paid to the role of chemical experiments in discoveries of SHEs. The DGFRS detection/monitoring system is presented in full firstly.

  7. Neutron resonance transmission analysis of reactor spent fuel assemblies

    A method called Neutron Resonance Transmission Analysis (NRTA) is under study which would use a pulsed neutron beam for nondestructive isotopic assay of a complete spent fuel assembly. Neutrons removed from the collimated beam by absorption or scattering in the resonances of the various isotopes in the spent fuel appear as dips in the neutron transmission. The method is completely insensitive to matrix materials such as oxide, fuel cladding, and other structural members. Measurements on spent fuel buttons using the NBS linac as a pulsed neutron source demonstrate a high accuracy capability for the isotopes 234235236238U, 239240241242Pu, 241Am, 243Am, and several fission products. The NRTA method offers high speed and modest operational cost, and it can be implemented with commercially available medical or radiographic γ-ray generators adapted for neutron production. (Auth.)

  8. High-temperature X-ray diffraction studies on La1-2xCaxThxPO4(s) (x = 0, 0.25, 0.5) solid-solution

    Advanced Heavy Water Reactor (AHWR), Compact High Temperature Reactor (CHTR) and Accelerator Driven System (ADS) are being developed in India to use 232Th-233U fuel cycle. Unlike natural uranium, natural thorium contains only trace amounts of fissile material (231Th), which are insufficient to initiate a nuclear chain reaction. It can be used with 233U, 235U and 239Pu as fissile fuel. Because of it, the back end of thorium fuel cycle contains long-lived 231Pa, 229Th, 230Th and low level of minor actinides (237Np, 241Am, 243Am, 244Cm) for final disposal in geological repositories. From a geochemical point of view, monazite (LnPO4 with Ln: rare earths) is the most abundant lanthanide phosphate observed in natural samples). Such minerals appear as the major thorium source on earth, especially in several ores which contain up to 29 wt% of ThO2, 16wt% of UO2, respectively

  9. Monte Carlo modeling of spallation targets containing uranium and americium

    Neutron production and transport in spallation targets made of uranium and americium are studied with a Geant4-based code MCADS (Monte Carlo model for Accelerator Driven Systems). A good agreement of MCADS results with experimental data on neutron- and proton-induced reactions on 241Am and 243Am nuclei allows to use this model for simulations with extended Am targets. It was demonstrated that MCADS model can be used for calculating the values of critical mass for 233,235U, 237Np, 239Pu and 241Am. Several geometry options and material compositions (U, U + Am, Am, Am2O3) are considered for spallation targets to be used in Accelerator Driven Systems. All considered options operate as deep subcritical targets having neutron multiplication factor of k∼0.5. It is found that more than 4 kg of Am can be burned in one spallation target during the first year of operation

  10. The simultaneous neutron and photon interrogation method for fissile and non-fissile element separation in radioactive waste drums

    Measuring α-emitters such as (234,235,236,238U, 238,239,240,242,244Pu, 237Np, 241,243Am, ...), in solid radioactive waste allows us to quantify the α-activity in a drum and then to classify it. The simultaneous photon and neutron interrogation experiment (SIMPHONIE) method dealt with in this paper, combines both active neutron interrogation and induced photofission interrogation techniques simultaneously. Its purpose is to quantify fissile (235U, 239,241Pu, ...) and non-fissile (236,238U, 238,240Pu, ...) elements separately in only one measurement. This paper presents the principle of the method, the experimental setup, and the first experimental results obtained using the DGA/ETCA Linac and MiniLinatron pulsed linear electron accelerators located at Arcueil, France. First studies were carried out with U and Pu bare samples

  11. Determination of fission cross-section and absolute fission yields using track-cum gamma-ray spectrometric technique

    The fission cross-section of 233Pa(2nth, f) using fission track technique has been determined for the first time using thermal neutron flux of the reactor APSARA. This is important from the point of view of advance heavy water reactor (AHWR), which is to be described. On the other hand, the yields of fission products in the fast neutron induced fission of minor actinides are important from the point accelerator driven sub critical system (ADSS). In view of that, absolute yields of fission products in the fast neutron induced fission of 238U, 237Np, 238,240Pu, 243Am and 244Cm have been determined using the fission track-cum gamma-ray spectrometric technique. The total number of fission occurring in the target was estimated by track technique, whereas the activities of the fission products have been determined using gamma-ray spectrometric technique. Detailed procedure and its importance are to be discussed. (author)

  12. Preparation of americium targets for nuclear chemistry experiments at DANCE

    Using 1 gram of 241Am from LANL stocks, the purification steps required to obtain a solution of 241Am from the original material are described. Part of the purified solution was submitted for purity analysis by mass spectrometry, radiochemistry and trace metals analysis. The impurities were expected to be 239Pu and 237Np. A second fraction of this material was used for electroplating three samples onto titanium disks that were suitable for insertion into an instrument package to be placed into the DANCE detector. The purification methods used, the electroplating setup and the solutions to various problems that were encountered in making these targets are discussed. The analytical results are discussed as well as the yields from the electrodeposition process. Comparison of these yields with those from similar experiments utilizing 235U and 243Am are also discussed. (author)

  13. Neutron capture reactions at DANCE

    The Detector for Advanced Neutron Capture Experiments (DANCE) is a 4π BaF2 array consisting of 160 active detector elements. The primary purpose of the array is to perform neutron capture cross section measurements on small (> or approx.100 μg) and/or radioactive (241,243Am, neutron capture and neutron-induced fission cross sections and capture-to-fission ratio (α = σγ/σf) for 235U using a new fission-tagging detector as well as neutron capture cross sections for several astrophysics branch-point nuclei. Results from several of these measurements will be presented along with a discussion of additional physics information that can be extracted from the DANCE data

  14. AN INTEGRAL REACTOR PHYSICS EXPERIMENT TO INFER ACTINIDE CAPTURE CROSS-SECTIONS FROM THORIUM TO CALIFORNIUM WITH ACCELERATOR MASS SPECTROMETRY

    The principle of the proposed experiment is to irradiate very pure actinide samples in the Advanced Test Reactor (ATR) at INL and, after a given time, determine the amount of the different transmutation products. The determination of the nuclide densities before and after neutron irradiation will allow inference of effective neutron capture cross-sections. This approach has been used in the past and the novelty of this experiment is that the atom densities of the different transmutation products will be determined using the Accelerator Mass Spectroscopy (AMS) technique at the ATLAS facility located at ANL. It is currently planned to irradiate the following isotopes: 232Th, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 243Am and 248Cm.

  15. MANTRA: An Integral Reactor Physics Experiment to Infer Actinide Capture Cross-sections from Thorium to Californium with Accelerator Mass Spectrometry

    The principle of the proposed experiment is to irradiate very pure actinide samples in the Advanced Test Reactor at INL and, after a given time, determine the amount of the different transmutation products. The determination of the nuclide densities before and after neutron irradiation will allow inference of effective neutron capture cross-sections. This approach has been used in the past and the novelty of this experiment is that the atom densities of the different transmutation products will be determined using the Accelerator Mass Spectrometry technique at the ATLAS facility located at ANL. It is currently planned to irradiate the following isotopes: 232Th, 235U, 236U, 238U, 237Np, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 243Am, 244Cm and 248Cm.

  16. Updated multi-group cross sections of minor actinides with improved resonance treatment

    The study of minor actinide in transmutation reactors and other future applications makes resonance self-shielding treatment a significant issue for criticality and isotope depletion. Resonance treatment for minor actinides has been carried out by subgroup method with improved interference effect through interference correction. Subgroup data was generated using RMET21 and GENP codes along with multi-group cross section data by NJOY nuclear data processing system. Updated multi-group cross section data library for a neutron transport code nTRACER was compared with solutions from MCNPX. The resonance interaction of uranium with minor actinides has been included by modified interference treatment of interference correction in subgroup methodology. The comparison of cross sections and multiplication factor in pin and assembly problems showed significant improvement from systematic resonance treatment especially for 237Np and 243Am. (author)

  17. Comparative analysis of selected aspects of the MUSE-4 experiments with the JEF-2.2 and JEFF-3.1 libraries

    This paper presents the analysis of some selected experiments of the MUSE-4 program with the ERANOS-2.1 code system using either the JEF-2.2 library or the more recent JEFF-3.1 one; focus has been given to the reactivities calculations and to the spectral indices of the MUSE-4-Reference and SC3-Pb core configurations. Both libraries provide comparable results on the keff of the Reference configuration due to large negative and positive compensating reactivity effects, whereas there is a -400 pcm effect on SC3-Pb. A perturbation analysis demonstrates that the large negative total reactivity effect in this configuration comes from the increase of the lead contribution and from the decrease of the sodium contribution. The new library improves the C/E for all the spectral indices in the fuel zone and for most of them in the lead zone except for 238U and 243Am. (authors)

  18. WWER-1000 spent fuel nuclide inventory at the Kozloduy NPP

    This paper contains a presentation and discussion of selected isotope inventory results for different types of WWER-1000 spent fuel assemblies. Nuclide inventory calculations of spent fuel assemblies at the Kozloduy NPP are routinely performed using the SCALE 4.4a computer code system. Besides the standard 17x17 ORIGEN-S library, a specific library developed at the Kozloduy NPP for each different fuel type at typical irradiation conditions is used. The evaluated concentrations of the most important isotopes - 235U, 236U, 238U, 239Pu, 240Pu, 241Pu, 242Pu - depending on burnup, are compared with fuel supplier data and with data calculated using the HELIOS-1.5 lattice code. The buildup of some other isotopes (237Np, 241Am, 243Am) is presented, too. (authors)

  19. WWER-1000 spent fuel nuclide inventory at the Kozloduy NPP

    This paper contains a presentation and discussion of selected isotope inventory results for different types of WWER-1000 spent fuel assemblies. Nuclide inventory calculations of spent fuel assemblies at Kozloduy NPP are routinely performed using the SCALE 4.4a computer code system. Besides the standard 17x17 ORIGEN-S library, a specific library developed at the Kozloduy NPP for each different fuel type at typical irradiation conditions is used. The evaluated concentrations of the most important isotopes-235U, 236U, 238U, 239Pu, 240Pu, 241Pu, 242Pu-depending on burnup, are compared with fuel supplier data and with data calculated using the HELIOS-1.5 lattice code. The buildup of some other isotopes (237Np, 241Am, 243Am) is presented, too (Authors)

  20. Measurement of the fast neutron capture cross section of 238U relative to 235U(n,f)

    The capture cross section of 238U was measured using the activation technique and 235U(n,f) as a reference cross section. Capture events were measured by detection of two prominent γ-transitions in the decay of the 239U daughter nuclide, 239Np, employing a high resolution Ge(Li) detector. The system was calibrated with samples activated in a thermal neutron flux relative to the capture cross section of gold, and with an absolutely calibrated α-emitter, 243Am, which decays to 239Np. Cross section measurements were carried out in the neutron energy range from 30 keV to 3 MeV. Emphasis was on absolute values between 150 keV and 1 MeV where the 238U(n,γ) cross section and its cross section is small. Background from fission products was found to restrict the accuracy of the measured data at energies > 1.5 MeV

  1. Delayed neutron spectra and their uncertainties in fission product summation calculations

    Miyazono, T.; Sagisaka, M.; Ohta, H.; Oyamatsu, K.; Tamaki, M. [Nagoya Univ. (Japan)

    1997-03-01

    Uncertainties in delayed neutron summation calculations are evaluated with ENDF/B-VI for 50 fissioning systems. As the first step, uncertainty calculations are performed for the aggregate delayed neutron activity with the same approximate method as proposed previously for the decay heat uncertainty analyses. Typical uncertainty values are about 6-14% for {sup 238}U(F) and about 13-23% for {sup 243}Am(F) at cooling times 0.1-100 (s). These values are typically 2-3 times larger than those in decay heat at the same cooling times. For aggregate delayed neutron spectra, the uncertainties would be larger than those for the delayed neutron activity because much more information about the nuclear structure is still necessary. (author)

  2. Measurement of fission cross section with pure Am-243 sample using lead slowing-down spectrometer

    Kobayashi, Katsuhei; Yamamoto, Shuji; Kai, T.; Fujita, Yoshiaki; Yamamoto, Hideki; Kimura, Itsuro [Kyoto Univ. (Japan); Shinohara, Nobuo

    1997-03-01

    By making use of back-to-back type double fission chambers and a lead slowing-down spectrometer coupled to an electron linear accelerator, the fission cross section for the {sup 243}Am(n,f) reaction has been measured relative to that for the {sup 235}U(n,f) reaction in the energy range from 0.1 eV to 10 keV. The measured result was compared with the evaluated nuclear data appeared in ENDF/B-VI and JENDL-3.2, whose evaluated data were broadened by the energy resolution function of the spectrometer. General agreement was seen between the evaluated data and the measurement except that the ENDF/B-VI data were lower in the range from 15 to 60 eV and that the JENDL-3.2 data seemed to be lower above 100 eV. (author)

  3. Discovery of the New Element Z=117 and Confirmation of 115

    Oganessian Yu. Ts.

    2011-10-01

    Full Text Available The discovery of the new chemical element with atomic number Z=117 is presented. The isotopes 293 117 and 294117 were produced in fusion reactions between 48Ca and 249Bk. The 249Bk was produced in the High Flux Isotope Reactor and chemically separated at Oak Ridge. Decay chains involving eleven new nuclei were identified by means of the Dubna Gas-Filled Recoil Separator. The measured decay properties show a strong rise of stability for superheavy nuclei toward N=184.The reaction 243Am+48Ca was studied at three energies. Twenty one decay chains of 288115 and one decay chain of 289115 were observed to confirm the earlier discoveries of Z=115 and 117.

  4. Investigation of neutronic behavior in a CANDU reactor with different (Am, Th, 235U)O2 fuel matrixes

    Recently thorium-based fuel matrixes are taken into consideration for nuclear waste incineration because of thorium proliferation resistance feature moreover its breeding or convertor ability in both thermal and fast reactors. In this work, neutronic influences of adding Am to (Th-235U)O2 on effective delayed neutron fraction, reactivity coefficients and burn up of a fed CANDU core has been studied using MCNPX 2.6.0 computational code. Different atom fractions of Am have been introduced in the fuel matrix to evaluate its effects on neutronic parameters of the modeled core. The computational data show that adding 2% atom fraction of Am to thorium-based fuel matrix won't noticeably change reactivity coefficients in comparison with the fuel matrix containing 1% atom fraction of Am. The use of 2% atom fraction of Am resulted in a higher delayed neutron fraction. According to the obtained data, 32.85 GWd burn up of the higher Americium-containing fuel matrix resulted in 55.2%, 26.5%, 41.9% and 2.14% depletion of 241Am, 243Am, 235U and 232Th respectively. 132.8 kg of 233U fissile element is produced after the burn up time and the nuclear core multiplication factor increases in rate of 2390 pcm. The less americium-containing fuel matrix resulted in higher depletion of 241/243Am, 235U and 232Th while the nuclear core effective multiplication factor increases in rate of 5630 pcm after the burn up time with 9.8 kg additional 233U production.

  5. Separation and activity determination of 239+240Pu, 241Am and Curium (242and244Cm) in evaporator concentrate by Alpha Spectrometry

    Alpha spectrometry analysis was used for activity determinations of Pu, Am and Cm isotopes in evaporator concentrate samples from nuclear power plants. Using a sequential procedure the first step was Pu isolation by an anion exchange column followed by an Am and Cm separation of U and Fe by a co-precipitation with oxalic acid. The precipitate was used for americium and curium separation of strontium by using a TRU resin extraction chromatography column. Due to their chemical similarities and energy difference it was seen that the simultaneous determination of 241Am, 242Cm and 243,244Cm isotopes is possible using the 243Am as tracer, once they have peaks in different region of interest (ROI) in the alpha spectrum. In this work it was used tracers, 238Pu, 243Am, 244Cm and 232U, for determination and quantification of theirs isotopes, respectively. The standard deviations for replicate analysis were calculated and for 241Am it was (1,040 ± 160 mBqKg-1), relative standard deviation 15.38%, and for 239+240Pu it was (551 +- 44 mBqKg-1), relative standard deviation 7.98%. In addition, for the 242Cm isotope the standard deviation for determinations was(75 ± 23 mBqKg-1), with the relative standard deviation 30.67% higher than for 241Am and 239+240Pu. The radiometric yields ranged from 90% to 105% and the lower limit of detection was estimated as being 2.05 mBqKg-1. (author)

  6. Odd-Z Transactinide Compound Nucleus Reactions Including the Discovery of 260Bh

    Several reactions producing odd-Z transactinide compound nuclei were studied with the 88-Inch Cyclotron and the Berkeley Gas-Filled Separator at the Lawrence Berkeley National Laboratory. The goal was to produce the same compound nucleus at or near the same excitation energy with similar values of angular momentum via different nuclear reactions. In doing so, it can be determined if there is a preference in entrance channel, because under these experimental conditions the survival portion of Swiatecki, Siwek-Wilcznska, and Wilczynski's 'Fusion By Diffusion' model is nearly identical for the two reactions. Additionally, because the same compound nucleus is produced, the exit channel is the same. Four compound nuclei were examined in this study: 258Db, 262Bh, 266Mt, and 272Rg. These nuclei were produced by using very similar heavy-ion induced-fusion reactions which differ only by one proton in the projectile or target nucleus (e.g.: 50Ti + 209Bi vs. 51V + 208Pb). Peak 1n exit channel cross sections were determined for each reaction in each pair, and three of the four pairs; cross sections were identical within statistical uncertainties. This indicates there is not an obvious preference of entrance channel in these paired reactions. Charge equilibration immediately prior to fusion leading to a decreased fusion barrier is the likely cause of this phenomenon. In addition to this systematic study, the lightest isotope of element 107, bohrium, was discovered in the 209Bi(52Cr,n) reaction. 260Bh was found to decay by emission of a 10.16 MeV alpha particle with a half-life of 35 ms. The cross section is 59 pb at an excitation energy of 15.0 MeV. The effect of the N = 152 shell is also seen in this isotope's alpha particle energy, the first evidence of such an effect in Bh. All reactions studied are also compared to model predictions by Swiatecki, Siwek-Wilcznska, and Wilczynski's 'Fusion By Diffusion' theory

  7. Nuclear Data and Measurements Series: The energy dependence of the optical-model potential for fast-neutron scattering from bismuth

    Neutron differential-elastic-scattering cross sections of bismuth were measured at 0.5 MeV intervals from 4.5 to 10.0 MeV. At each incident energy ≥40 differential values were obtained, distributed between 180 and 1600. The measured data were combined with lower-energy results previously reported from this laboratory, and others available in the literature, to provide a detailed data base extending from 1.5 to 10.0 MeV. This data base was interpreted in terms of the conventional optical-statistical model and also a model inclusive of the surface-peaked real potential predicted by the dispersion relation. Particular attention was given to the energy dependence of the volume-integral-per-nucleon of the real potential, J/sub v/, to see if there was evidence of the Fermi Surface Anomaly. In the range 3.0 to 10.0 MeV the present data indicate that dJ/sub v//dE is essentially constant, with a relatively large negative value of -6.0 to -9.0 fm3, depending on the model used in the analysis. Below 3.0 MeV, there is some evidence for a decrease in the magnitude of dJ/dE. However, the effect is very small and it is only when this trend is combined with considerations of the J/sub v/ values needed to give correct bound-state energies that evidence for the Fermi Surface Anomaly emerges. J/sub v/ and the geometry of the optical potentials found for 209Bi become equal to those needed to explain the high-energy 208Pb data at about 10.0 MeV. Since dJ/sub v//dE for the latter is smaller in magnitude than for 209Bi, a change in dJ/sub v//dE is clearly indicated near 10.0 MeV. This may effect the extrapolation of higher-energy and charged-particle potentials into the lower-energy neutron domain. 47 refs., 9 figs

  8. A study of non-elastic reaction rates for the ADS materials in the environment of spallation neutrons produced by 1.6 GeV d-beam

    For the design and modeling of Accelerator Driven sub-critical System (ADS) a detailed study of response of ADS materials to the spallation neutrons is required. For this purpose reaction rates of different reactions like (n, xn) and (n, xnyp) in 209Bi, natMo, 56Fe, natNi, 55Mn, natTi and natCo materials are determined in an experiment conducted at Nuclotron of JINR, Dubna, using 1.6 GeV d-beam in the ‘Energy+Transmutation’ set-up. Reaction rates of various (n, xn) and (n, xnyp) reactions are studied in these samples. Results of reaction rates deduced from all the gamma peaks observed in case of 209Bi (n, xn) reactions with x=3−9, natMo (n, γ), (n, 3n), (n, 6n), 56Fe (n, p), (n, p2n), (n, p4n), natNi (n, 2n), (n, 3n), (n, p), (n, d), (n, t), 55Mn (n, γ), (n, 2n), (n, 4n), natTi (n, p), (n, d), (n, t) and natCo (n, γ), (n, xn) reactions with x=2–5 along with (n, p), (n, 2p2n), (n, 2p4n) and (n, 2p6n) are presented. The measured reaction rates for all the elements show good consistency for all the reaction channels and all observed Eγ's of the product nucleus. For all the above mentioned reactions, both experimental as well as theoretical spectrum average cross-sections (σsp.av.cs) are deduced and compared. A close agreement is found between the experimental σsp.av.cs and theoretical σsp.av.cs values. - Highlights: ► (n, xn) spectrum average cross-section for seven elements are calculated. ► Comparison of theoretical and experimental spectrum average cross-sections is done. ► A close agreement is found between the experimental and theoretical cross-sections.

  9. RAPID DETERMINATION OF ACTINIDES IN URINE BY INDUCTIVELY-COUPLED PLASMA MASS SPECTROMETRY AND ALPHA SPECTROMETRY: A HYBRID APPROACH

    Maxwell, S.; Jones, V.

    2009-05-27

    A new rapid separation method that allows separation and preconcentration of actinides in urine samples was developed for the measurement of longer lived actinides by inductively coupled plasma mass spectrometry (ICP-MS) and short-lived actinides by alpha spectrometry; a hybrid approach. This method uses stacked extraction chromatography cartridges and vacuum box technology to facilitate rapid separations. Preconcentration, if required, is performed using a streamlined calcium phosphate precipitation. Similar technology has been applied to separate actinides prior to measurement by alpha spectrometry, but this new method has been developed with elution reagents now compatible with ICP-MS as well. Purified solutions are split between ICP-MS and alpha spectrometry so that long- and short-lived actinide isotopes can be measured successfully. The method allows for simultaneous extraction of 24 samples (including QC samples) in less than 3 h. Simultaneous sample preparation can offer significant time savings over sequential sample preparation. For example, sequential sample preparation of 24 samples taking just 15 min each requires 6 h to complete. The simplicity and speed of this new method makes it attractive for radiological emergency response. If preconcentration is applied, the method is applicable to larger sample aliquots for occupational exposures as well. The chemical recoveries are typically greater than 90%, in contrast to other reported methods using flow injection separation techniques for urine samples where plutonium yields were 70-80%. This method allows measurement of both long-lived and short-lived actinide isotopes. 239Pu, 242Pu, 237Np, 243Am, 234U, 235U and 238U were measured by ICP-MS, while 236Pu, 238Pu, 239Pu, 241Am, 243Am and 244Cm were measured by alpha spectrometry. The method can also be adapted so that the separation of uranium isotopes for assay is not required, if uranium assay by direct dilution of the urine sample is preferred instead

  10. Application of a gamma spectroscopy system to the measurement of neutron cross sections necessary to the development of nuclear energy

    This work concerns the development of nuclear energy and nuclear waste management in particular. Two parts of this study can be distinguished. In the first part (theoretical), a thorium-plutonium fuel based on MOX and dedicated for PWR was investigated in order to transmute plutonium in a potentially low waste fuel cycle. It was shown that this type of fuel is not regenerative but could be used for a transition to the industrial thorium fuel cycle without building new reactors. Thanks to moderated neutron spectra and high loaded actinide mass in the core, U-233 is quickly created (∼300 kg/y) for a loss of about ∼1200 kg of fissile plutonium. In the second part (experimental), we have developed and built a new reaction chamber to measure neutron cross sections of actinides by alpha-gamma spectroscopy. This experimental device (in principle transportable) was commissioned in the high flux reactor of ILL Grenoble. Neutron flux was measured by gamma spectroscopy of irradiated Al and Co samples and was found to be of the order of 6,0. 1014 n.cm-2.s-1 (4%). By the irradiation of 11μg of Am-243 and Pu-242, corresponding capture cross sections were measured in the thermal neutron flux at 50 deg C. These are the results: 243Am(n,γ) 244fond.Am = 4,72±1,42b; 243Am(n,γ) 244totalAm = 74,8±3,25b; 242Pu (n,γ)243Pu = 22,7±1,09b. Uncertainties of the measurements are mostly due to the determination of the neutron flux, efficiency of the electronics and ambiguities related to the definition of the area under α-γ spectra. Although our measured cross sections deviate (by 10-30%) from the corresponding values widely used in evaluated data libraries such as ENDF, JEF and JENDL, in this work we have demonstrated the feasibility and principle of our experimental method. Furthermore, the value for the 243-americium capture cross-section is in very good agreement with the last two measurements done in 1975 and 1997. These facts allowed us to think of new experiments and their

  11. Application of a gamma spectroscopy system to the measurement of neutron cross sections necessary to the development of nuclear energy; Mise au point d'un systeme de spectroscopie pour mesurer des sections efficaces neutroniques applicables a un possible developpement du nucleaire comme source d'energie

    Deruelle, O

    2002-09-01

    This work concerns the development of nuclear energy and nuclear waste management in particular. Two parts of this study can be distinguished. In the first part (theoretical), a thorium-plutonium fuel based on MOX and dedicated for PWR was investigated in order to transmute plutonium in a potentially low waste fuel cycle. It was shown that this type of fuel is not regenerative but could be used for a transition to the industrial thorium fuel cycle without building new reactors. Thanks to moderated neutron spectra and high loaded actinide mass in the core, U-233 is quickly created ({approx}300 kg/y) for a loss of about {approx}1200 kg of fissile plutonium. In the second part (experimental), we have developed and built a new reaction chamber to measure neutron cross sections of actinides by alpha-gamma spectroscopy. This experimental device (in principle transportable) was commissioned in the high flux reactor of ILL Grenoble. Neutron flux was measured by gamma spectroscopy of irradiated Al and Co samples and was found to be of the order of 6,0. 10{sup 14} n.cm{sup -2}.s{sup -1} (4%). By the irradiation of 11{mu}g of Am-243 and Pu-242, corresponding capture cross sections were measured in the thermal neutron flux at 50 deg C. These are the results: {sup 243}Am(n,{gamma}) {sup 244fond.}Am = 4,72{+-}1,42b; {sup 243}Am(n,{gamma}) {sup 244total}Am = 74,8{+-}3,25b; {sup 242}Pu (n,{gamma}){sup 243}Pu = 22,7{+-}1,09b. Uncertainties of the measurements are mostly due to the determination of the neutron flux, efficiency of the electronics and ambiguities related to the definition of the area under {alpha}-{gamma} spectra. Although our measured cross sections deviate (by 10-30%) from the corresponding values widely used in evaluated data libraries such as ENDF, JEF and JENDL, in this work we have demonstrated the feasibility and principle of our experimental method. Furthermore, the value for the 243-americium capture cross-section is in very good agreement with the last two

  12. Quantitative imaging analysis and investigation of transmission loss in PbF2 crystals by laser ablation-inductively coupled plasma-mass spectrometry method.

    Zhang, Guoxia; Wang, Zheng; Li, Qing; Zhou, Hui; Zhu, Yan; Du, Yiping

    2016-07-01

    We developed a procedure for preparing matrix-matched calibration standards for the quantitative imaging of multiple trace elements in PbF2 crystals by laser ablation-inductively coupled plasma-mass spectrometry (LA-ICP-MS). In this facile approach, PbO powder was employed as the matrix with the addition of a series of standard solutions, followed by drying and tableting, for determining the concentrations of (24)Mg, (27)Al, (89)Y, (103)Rh, (133)Cs, (175)Lu and (209)Bi in transparent samples (with homogeneous element distribution). (206)Pb was chosen as the internal standard and the correlation coefficients of the calibration curves for all elements ranged from 0.9987 to 0.9999 after internal standard correction. The analysis showed good agreement with the results observed by established ICP-MS methods, following acid dissolution of the samples. Finally, the element distributions and transmission curves of a PbF2 sample with non-transparent and transparent sections were visualized. The distribution images, in conjunction with the transmission curves, suggested that the enrichment of Mg, Al, Rh, Cs, and Bi atoms in the non-transparent section of the sample could explain the loss in transmission observed for that section. PMID:27154704

  13. Intranuclear cascade model for 50-MeV-region (p, p'x) reactions over a wide target mass range

    In our previous study, the applicable range of the intranuclear cascade model was successfully extended to lower incident energy (p, p'x) reactions by introducing trajectory deflections and low-energy-loss process due to collective excitations. However, the model's validity was confirmed only for a 56Fe target. In the present work we widen the applicable range of masses of the target nucleus. First, we derive an expression for the response function, which gives the probability of collective excitation strengths, to fit the distorted-wave Born approximation results as a function of the target mass number and the beam energy. Second, the barrier transmission coefficient was investigated. An expression with a modified Gamow penetration factor was chosen from four phenomenological forms of one-dimensional barrier transmission coefficients. Calculations with the proposed model followed by a generalized evaporation model were carried out for double-differential cross sections of (p, p'x) reactions at 30–60 MeV. Although the response function and the transmission coefficient were only parameterized approximately, the proposed model showed good agreements with experimental observations for a variety of nuclear targets from 12C to 209Bi. (author)

  14. Investigation of the properties of the nuclei using on the new generation reactor technology systems

    The application fields of the fast neutron are Accelerator-Driven subcritical Systems (ADS) for fission energy production and hybrid reactor systems. The technical design hybrid reactor and ADS systems potentialities require the knowledge of a wide range of better data and much effort. Thorium (Th) and Uranium (U) are nuclear fuels in these reactor systems. Lead (Pb), Bismuth (Bi) and Tungsten (W) are the target nuclei in the ADS reactor systems. The Hartree-Fock (H-F) method with an effective interaction with Skyrme forces is widely used for studying the properties of nuclei such as binding energy, Root Mean Square (RMS) charge radii, mass radii, neutron density, proton density, electromagnetic multipole moments, etc. In this study, by using H-F method with interaction Skyrme RMS charge radii, RMS mass radii, neutron density and proton density were calculated for the 232Th, 238U, 207Pb, 209Bi and 184W isotopes used on the new generation reactor systems. The calculation results of charge radii have been compared with experimental data and obtained other results have been discussed for hybrid and ADS reactor systems

  15. Production cross sections of the superheavy nucleus 117 based on the dinuclear system model

    ZHAO Wei-Juan; ZHANG Yong-Qi; WANG Hua-Lei; SONG Li-Tao; LI Lu-Lu

    2010-01-01

    Within the framework of the dinuclear system model,the capture of two colliding nuclei,and the formation and de-excitation process of a compound nucleus are described by using an empirical coupled channel model,solving the master equation numerically and the statistical evaporation model,respectively.In the process of heavy-ion capture and fusion to synthesize superheavy nuclei,the barrier distribution func-tion is introduced and averaging collision orientations are considered.Based on this model,the production cross sections of the cold fusion system 76-82Se+209Bi and the hot fusion systems 55Mn+238U,51V-+244Pu,59 Co+232 Th,48 Ca+247-249 Bk and 45 Sc+246-248 Cm are calculated.The isotopic dependence of the largest production cross sections is analyzed briefly,and the optimal projectile-target combination and excitation energy of the ln-4n evaporation channels are proposed.It is shown that the hot fusion systems 48Ca+247 249Bk in the3n evaporation channels and 45Sc+248Cm in the 2n-4n channels are optimal for synthesizing the superheavy element 117.

  16. Excitation function for the production of 262Bh (Z = 107) in theodd-Z projectile reaction 208Pb(55Mn, n)

    Folden III, C.M.; Nelson, S.L.; Dullmann, Ch.E.; Schwantes, J.M.; Sudowe, R.; Zielinski, P.M.; Gregorich, K.E.; Nitsche, H.; Hoffman, D.C.

    2005-05-16

    The excitation function for production of 262Bh in the odd-Z-projectile reaction 208Pb(55Mn,n) has been measured at three projectile energies using the Berkeley Gas-filled Separator at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. In total, 33 decay chains originating from 262Bh and 2 decay chains originating from 261Bh were observed. The measured decay properties are in good agreement with previous reports. The maximum cross section of 540 +180 - 150 pb is observed at a lab-frame center-of-target energy of 264.0 MeV and is more than fives times larger than that expected based on previously reported results for production of 262Bh in the analogous even-Z-projectile reaction 209Bi(54Cr,n). Our results indicate that the optimum beam energy in one-neutron-out heavy-ion fusion reactions can be estimated simply using the ''Optimum Energy Rule'' proposed by Swiatecki, Siwek-Wilczynska, and Wilczynski.

  17. Dependence of Fission-Fragment Total Kinetic-Energy and Mass Distributions on the Excitation Energy and Angular-Momentum Distribution of the Fissioning Nuclide 210Po

    The fission of 210Po, produced by three different nuclear reactions (209Bi + p, 206Pb + α and 198Pt + 12C), has been studied in detail in order to establish the dependence of various scission-point properties on the excitation energy and angular-momentum distribution of the fissioning nucleus. Excitation energies of 31, 44 and 57 MeV were chosen so as to give reasonable fission cross-sections, while avoiding a large contribution from second chance fission. The experiments were conducted on a beam line of the Harwell Variable Energy Cyclotron. The mean-fragment total-kinetic-energy release was found to be dependent on the 210Po excitation energy and angular-momentum distribution. The variances of the total-kinetic energy and mass distributions were found to be a strongly dependent on excitation energy but not on angular momentum. The experimental results of this work were found to be in good agreement with the theoretical liquid-drop-model calculations of Nix and Swiatecki. (author)

  18. One nucleon transfer reactions induced by heavy ions: single particles states and collective modes

    In one nucleon transfer reactions induced by heavy ion beams, broad and very prominent structures are observed above 10 MeV excitation energy. The aim of this work is to try to understand these structures and to distinguish between interpretations in terms of the excitation of single particles states or collective modes such as giant resonances. We studied one nucleon transfer reactions on different targets 207Pb, 209Bi, 59Co, 63Cu, 58Ni, 120Sn) with beams of 20Ne at 48 MeV/A and of 36Ar at 42 MeV/A, detecting reaction products with a magnetic spectrometer, in order to verify the presence of those structures and to measure them in broad range of reactions. The different experimental results show that these bumps cannot be attributed to low multipolarity giant resonances (L=1 or 2). These results have been compared with two very different theoretical approaches. The first one uses a reaction model in order to evaluate the cross section of the different processes that can contribute to the transfer spectra. The second one is based on a microscopic description of the excited states in the random phase approximation (RPA), followed by a cross section calculation in the distorted wave Born approximation (DWBA). In the framework of these models, it appears that the observed structures are dominated by the excitation of high spin single particle states. Nevertheless, a small part of the cross section can be attributed to collective excitations of high multipolarity

  19. Summary report of global and the local optical model potentials parameters for some nuclei

    Measurements of reaction cross sections and differential cross sections of elastic scattering for deuteron missing from the EXFOR library were obtained from figures and tables in published papers of different journals. Measurement data of forty nuclei were given at different incident deuteron energies. A set of deuteron global optical model potential parameters for the target mass range from 12 to 209 and the deuteron energy range from threshold to 200 MeV have been obtained from experimental data of deuteron total reaction cross sections and elastic scattering angular distributions. The global optical model parameters obtained have been analyzed. Local deuteron optical model potential parameters for 6,7Li, 9Be, 12C and 40,42,44,46,48Ca have been obtained. Local optical model potentials parameters for some nuclei were obtained. The theoretical mode codes UNF and MEND are being used to calculate neutron and proton-induced reactions, and compared with the available experimental database for some nuclei ( n,p+54,56,57,58Fe, n+208Pb, 209Bi, 238U and p+58Ni). A set of alpha global optical model potential parameters for the target mass range from 12 to 208 and alpha energy range from threshold to 200 MeV have been obtained according to the experimental data of alpha total reaction cross sections and elastic scattering angular distributions

  20. Investigation of the properties of the nuclei used on the new generation reactor technology systems

    The main application fields of the fast neutrons are accelerator-driven subcritical systems (ADS) and fusion-fission (hybrid) reactor systems for fission energy production. Thorium (Th) and uranium (U) are nuclear fuels in these reactor systems. Lead (Pb), bismuth (Bi) and tungsten (W) are the target nuclei in the ADS reactor systems. The technical design of ADS and hybrid reactor systems require much effort and data. The Hartree-Fock (H-F) method with an effective interaction with Skyrme forces is widely used for studying the properties of nuclei such as binding energy, root mean square (RMS) charge radii, mass radii, neutron density, proton density, electromagnetic multipole moments, etc. In this study, by using H-F method with interaction Skyrme RMS charge radii, RMS mass radii, neutron density and proton density were calculated for the 232Th, 238U, 207Pb, 209Bi and 184W isotopes. The calculation results of charge radii were compared with experimental data. Obtained RMS mass radii, neutron density and proton density results were discussed for ADS and hybrid reactor systems

  1. Improved lead and bismuth (n,{gamma}) cross sections and their astrophysical impact

    Domingo-Pardo, C.; Abbondanno, U.; Aerts, G.; Alvarez, H.; Alvarez-Velarde, F.; Andriamonje, S.; Andrzejewski, J.; Assimakopoulos, P.; Audouin, L.; Badurek, G.; Baumann, P.; Becvar, F.; Berthoumieux, E.; Calvino, F.; Calviani, M.; Cano-Ott, D.; Capote, R.; Carrapico, C.; Cennini, P.; Chepel, V.; Chiaveri, E.; Colonna, N.; Cortes, G.; Couture, A.; Cox, J.; Dahlfors, M.; David, S.; Dillmann, I.; Dridi, W.; Duran, I.; Eleftheriadis, C.; Embid-Segura, M.; Ferrant, L.; Ferrari, A.; Ferreira-Marques, R.; Fujii, K.; Furman, W.; Goncalves, I.; Gonzalez-Romero, E.; Gramegna, F.; Guerrero, C.; Gunsing, F.; Haas, B.; Haight, R.; Heil, M.; Herrera-Martinez, A.; Igashira, M.; Jericha, E.; Kiappeler, F.; Kadi, Y.; Karadimos, D.; Karamanis, D.; Kerveno, M.; Koehler, P.; Kossionides, E.; Krticka, M.; Lampoudis, C.; Leeb, H.; Lindote, A.; Lopes, I.; Lozano, M.; Lukic, S.; Marganiec, J.; Marrone, S.; Martinez, T.; Massimi, C.; Mastinu, P.; Mengoni, A.; Milazzo, P.M.; Moreau, C.; Mosconi, M.; Neves, F.; Oberhummer, H.; O' Brien, S.; Pancin, J.; Papachristodoulou, C.; Papadopoulos, C.; Paradela, C.; Patronis, N.; Pavlik, A.; Pavlopoulos, P.; Perrot, L.; Pigni, M.T.; Plag, R.; Plompen, A.; Plukis, A.; Poch, A.; Praena, J.; Pretel, C.; Quesada, J.; Rauscher, T.; Reifarth, R.; Rubbia, C.; Rudolf, G.; Rullhusen, P.; Salgado, J.; Santos, C.; Sarchiapone, L.; Savvidis, I.; Stephan, C.; Tagliente, G.; Tain, J.L.; Tassan-Got, L.; Tavora, L.; Terlizzi, R.; Vannini, G.; Vaz, P.; Ventura, A.; Villamarin, D.; Vincente, M.C.; Vlachoudis, V.; Vlastou, R.; Voss, F.; Walter, S.; Wiescher, M.; Wisshak, K

    2008-07-01

    A series of (n,{gamma}) neutron capture measurements on the lead isotopes and bismuth have been carried out at the CERN n-TOF installation in the neutron energy range from 1 eV up to 1 MeV. At n-TOF, contaminations due to scattered neutrons were reduced down to a negligible level by using improved {gamma}-ray detectors with very low neutron sensitivity. The background level has been determined precisely from a complementary measurement. Other experimental effects related to the electronic threshold in the detectors and the angular distribution of the prompt {gamma}-rays were investigated via Monte Carlo simulations and could be taken into account in the analysis of the capture data. With this set of measurements the energy differential (n,{gamma}) cross sections of {sup 204,206,207}Pb and {sup 209}Bi have been determined with good accuracy. The information obtained in this work becomes of interest for constraining r-process calculations and in particular for the Th/U cosmo-chronometer. (authors)

  2. Improved lead and bismuth (n,γ) cross sections and their astrophysical impact

    A series of (n,γ) neutron capture measurements on the lead isotopes and bismuth have been carried out at the CERN n-TOF installation in the neutron energy range from 1 eV up to 1 MeV. At n-TOF, contaminations due to scattered neutrons were reduced down to a negligible level by using improved γ-ray detectors with very low neutron sensitivity. The background level has been determined precisely from a complementary measurement. Other experimental effects related to the electronic threshold in the detectors and the angular distribution of the prompt γ-rays were investigated via Monte Carlo simulations and could be taken into account in the analysis of the capture data. With this set of measurements the energy differential (n,γ) cross sections of 204,206,207Pb and 209Bi have been determined with good accuracy. The information obtained in this work becomes of interest for constraining r-process calculations and in particular for the Th/U cosmo-chronometer. (authors)

  3. Operation of Lanzhou all permanent electron cyclotron resonance ion source No. 2 on 320 kV platform with highly charged ions

    Lu, W., E-mail: luwang@impcas.ac.cn [Institute of Modern Physics, CAS, Lanzhou 730000 (China); University of Chinese Academy of Sciences, Beijing 100049 (China); Li, J. Y.; Kang, L.; Liu, H. P.; Li, H.; Li, J. D.; Sun, L. T.; Ma, X. W. [Institute of Modern Physics, CAS, Lanzhou 730000 (China)

    2014-02-15

    The 320 kV platform for multi-discipline research with highly charged ions is a heavy ion beam acceleration instrument developed by Institute of Modern Physics, which is dedicated to basic scientific researches such as plasma, atom, material physics, and astrophysics, etc. The platform has delivered ion beams of 400 species for 36 000 h. The average operation time is around 5000 h/year. With the beams provided by the platform, lots of outstanding progresses were made in various research fields. The ion source of the platform is an all-permanent magnet electron cyclotron resonance ion source, LAPECR2 (Lanzhou All Permanent ECR ion source No. 2). The maximum axial magnetic fields are 1.28 T at injection and 1.07 T at extraction, and the radial magnetic field is up to 1.21 T at the inner wall of the plasma chamber. The ion source is capable to produce low, medium, and high charge state gaseous and metallic ion beams, such as H{sup +}, {sup 40}Ar{sup 8+}, {sup 129}Xe{sup 30+}, {sup 209}Bi{sup 33+}, etc. This paper will present the latest result of LAPECR2 and the routine operation status for the high voltage platform.

  4. Optical measurement of the longitudinal ion distribution of bunched ion beams in the ESR

    Wen, W. Q.; Lochmann, M.; Ma, X.; Bussmann, M.; Winters, D. F. A.; Nörtershäuser, W.; Botermann, B.; Geppert, C.; Frömmgen, N.; Hammen, M.; Hannen, V.; Jöhren, R.; Kühl, Th.; Litvinov, Yu. A.; Sánchez, R.; Stöhlker, Th.; Vollbrecht, J.; Weinheimer, C.; Dimopoulou, C.; Nolden, F.; Steck, M.

    2013-05-01

    An optical technique to study the longitudinal distribution of ions in a bunched ion beam circulating in a storage ring is presented. It is based on the arrival-time analysis of photons emitted after collisional excitation of residual gas molecules. The beam-induced fluorescence was investigated in the ultraviolet regime with a channeltron and in the visible region using a photomultiplier tube. Both were applied to investigate the longitudinal shape of bunched and electron-cooled 209Bi80+ ion beams at about 400 MeV/u in the experimental storage ring (ESR) at GSI Helmholtzzentrum für Schwerionenforschung in Darmstadt, Germany. Bunch lengths were determined with an uncertainty of about 0.5 m using the UV-sensitive channeltron and with slightly lower accuracy from the photomultiplier data due to the slower transitions in the red region of the spectrum. The Gaussian shape of the longitudinal distribution of ions inside the bunch was confirmed. With the information of the transverse beam size that can be measured simultaneously by a newly installed ionization profile monitor (IPM) at the ESR, an accurate determination of the ion density in the bunched beam will be allowed.

  5. Search for the two-phonon octupole vibrational state in {sup 208}Pb

    Blumenthal, D.J.; Henning, W.; Janssens, R.V.F. [and others

    1995-08-01

    We performed an experiment to search for the two-phonon octupole vibrational state in {sup 208}Pb. Thick targets of {sup 208}Pb, {sup 209}Bi, {sup 58,64}Ni, and {sup 160}Gd were bombarded with 1305 MeV beams of were bombard {sup 208}Pb supplied by ATLAS. Gamma rays were detected using the Argonne-Notre Dame BGO gamma-ray facility, consisting of 12 Compton-suppressed germanium detectors surrounding an array of 50 BGO scintillators. We identified some 30 known gamma rays from {sup 208}Pb in the spectra gated by the 5{sup -} {yields} 3{sup -} and 3{sup -} {yields} 0{sup +} transitions in {sup 208}Pb. In addition, after unfolding these spectra for Compton response, we observed broad coincident structures in the energy region expected for the 2-phonon states. Furthermore, we confirmed the placement of a 2485 keV line observed previously in {sup 207}Pb and find no evidence consistent with the placement of this line in {sup 208}Pb. We are currently in the process of investigating the origin of the broadened lines observed in the spectra, extracting the excitation probability of states in {sup 208}Pb, and determining the relative probability of mutual excitation and neutron transfer in this reaction. An additional experiment is also being performed to collect much higher statistics germanium-germanium coincidence data for the thick {sup 208}Pb target.

  6. Investigations of nuclear structure and nuclear reactions induced by complex projectiles

    This is a progress report on activities of the Washington University group in nuclear reaction studies for the period Sept 1, 1992 to Aug 31, 1993. This group has a research program which touches five areas of nuclear physics: nuclear structure studies at high spin; studies at the interface between structure and reactions; production and study of hot nuclei; reaction mechanism studies; development and use of novel techniques and instrumentation in the above areas of research. Specific activities of the group include in part: superdeformation in 82Sr; structure of and identical bands in 182Hg and 178Pt; a highly deformed band in 136Pm; particle decay of the 164Yb compound nucleus; fusion reactions; proton evaporation; two-proton decay of 12O; modeling and theoretical studies; excited 16O disassembly into four alpha particles; 209Bi + 136Xe collisions at 28.2 MeV/amu; and development work on 4π solid angle gamma detectors, and x-ray detectors

  7. Optical measurement of the longitudinal ion distribution of bunched ion beams in the ESR

    An optical technique to study the longitudinal distribution of ions in a bunched ion beam circulating in a storage ring is presented. It is based on the arrival-time analysis of photons emitted after collisional excitation of residual gas molecules. The beam-induced fluorescence was investigated in the ultraviolet regime with a channeltron and in the visible region using a photomultiplier tube. Both were applied to investigate the longitudinal shape of bunched and electron-cooled 209Bi80+ ion beams at about 400 MeV/u in the experimental storage ring (ESR) at GSI Helmholtzzentrum für Schwerionenforschung in Darmstadt, Germany. Bunch lengths were determined with an uncertainty of about 0.5 m using the UV-sensitive channeltron and with slightly lower accuracy from the photomultiplier data due to the slower transitions in the red region of the spectrum. The Gaussian shape of the longitudinal distribution of ions inside the bunch was confirmed. With the information of the transverse beam size that can be measured simultaneously by a newly installed ionization profile monitor (IPM) at the ESR, an accurate determination of the ion density in the bunched beam will be allowed. -- Highlights: ► Optical methods to measure the bunch shape of ion beam at storage ring. ► High resolution of bunch length was obtained from the UV-sensitive channeltron. ► The Gaussian shape of longitudinal distribution of the ions in the bunch was confirmed

  8. Spectroscopy of hypernuclei

    Recent technological developments regarding secondary beams, magnetic spectrometers and detectors have made it possible to use electronic counter techniques to study hypernuclei. The in-flight strangeness exchange reaction K-+AZ → π-+sub(Λ)AZ is kinematically the most favorable. To undertake this experimental study, at Saclay we have built the large solid angle (20 msr), broad momentum acceptance (+-18%) and high resolution (dp/p=10-3) magnetic spectrometer SPES II. On its focal plane three large wire chambers allow us to measure the coordinates of the outgoing particle with a precision better than one millimeter. This whole system has been transported to CERN where, in conjunction with the secondary beam line K22, it has been used to investigate the spectroscopy of eleven hypernuclei: sub(Λ)6Li, sub(Λ)7Li, sub(Λ)9Be, sub(Λ)12C, sub(Λ)16O, sub(Λ)27Al, sub(Λ)32S, sub(Λ)40Ca, sub(Λ)51V, sub(Λ)89Y, and sub(Λ)209Bi. For the first time the precise and unambiguous identification of hypernuclear excited states has been possible. This has allowed us to determine the central and the spin-orbit of the Λ-nucleus interaction

  9. Study of $\\overline{p}$-Nucleus Interaction with a High Resolution Magnetic Spectrometer

    2002-01-01

    This experiment uses the high resolution, large solid angle and large momentum acceptance magnetic spectrometer SPES~II to study the interaction between @* and complex nuclei in the following experiments: \\\\ \\\\ \\item 1)~~~~A(@*, @*)A. Angular distribution of @* elastically scattered from |1|2C, |4|0Ca and |2|0|8Pb. \\item 2)~~~~A(@*, @*')A*. Excitation energy spectra and some angular distributions of @* inelastically scattered from |1|2C, |4|0Ca and |2|0|8Pb up to an excitation energy of &prop.~100~MeV. \\item 3)~~~~A(@*, p)A^z^-^1 (@*). Excitation energy spectra for knock out reaction on |6Li, |1|2C, |6|3Cu and |2|0|9Bi at several angles. \\end{enumerate}\\\\ \\\\ Any beam momentum between 300 MeV/c and 800 MeV/c will be suitable for this experiment. In order to vary the effect of strong absorption of @* by nuclei, elastic and inelastic scattering will be performed at two or three different @* momenta (depending on the way LEAR will be operated) down to 300~MeV/c.

  10. Development of the cyclotron radioisotope production technology

    Suh, Yong Sup; Chun, K.S.; Yang, S.D.; Lee, J.D.; Ahn, S.H.; Yun, Y.K.; Park, H.; Lee, J.S.; Chai, J.S.; Kim, U.S.; Hong, S.S.; Lee, M.Y.; Park, C.W.; Baik, S. K.; Kim, E. H.; Kim, T. K.; Kim, K. S.; Kim, J. H

    1999-04-01

    The purpose of this study is to contribute the advance of nuclear medicine and to the improvement of human health through the development of various accelerator radionuclides and mass production with automization of production. The results obtained from this study are following: 1) In order to introduce 30 MeV high current cyclotron, the specification of cyclotron has been made, the building site was selected and we drew the draw-up of cyclotron. The cyclotron installation contract was postponed until the financial resources could be secured. 2) For a development high purity 1-123 producing system, a Xe-124 target system, a temperature measurement system of the inner part of the target and a target window were fabricated. A Xe-124 gas target recovery system and a full production system of 1-123 was drew up. 3) For a development of a therapeutic nuclide At-211, a target for the production of At-211 via {sup 209}Bi(alpha, 2n) reaction was fabricated. Produced At-211 was separated by distillation method. 4) For development of beta-emitting nuclides, Ti-45, C-11, F{sub 2}-18, beam irradiation system suitable for each target were fabricated. 5) For automatic production of Ga-67, automated module and PLC program was made 6) For the quality control of radiopharmaceuticals, analytical method of thallium and copper by polarography was investigated and established.

  11. Production of high charge state ions with the Advanced Electron Cyclotron Resonance Ion Source at LBNL

    Production of high charge state ions with the Advanced Electron Cyclotron Resonance ion source (AECR) at Lawrence Berkeley National Laboratory (LBNL) has been significantly improved by application of various new techniques. Heating the plasma simultaneously with microwaves of two frequencies (10 and 14 GHz) has increased the production of very high charge state heavy ions. The two-frequency technique provides extra electron cyclotron resonance heating zone as compared to the single-frequency heating and improves the heating of the plasma electrons. Aluminum oxide on the plasma chamber surface improves the production of cold electrons at the chamber surfaces and increases the performance of the AECR. Fully stripped argon ions, ≥5 enA, were produced and directly identified by the source charge state analyzing system. High charge state ion beams of bismuth and uranium, such as 209Bi51+ and 238U53+, were produced by the source and accelerated by the 88-in. cyclotron to energies above 6 MeV/nucleon for the first time. copyright 1996 American Institute of Physics

  12. Investigations of nuclear structure and nuclear reactions induced by complex projectiles

    The research program described touches five areas of nuclear physics: nuclear structure studies at high spin (hyperdeformation in the mass A ≅ 182 region, structure of 182Hg and 182Au at high spin, a highly deformed band in 136Pm and the anomalous h11/2 proton crossing in the A∼135 superdeformed region), studies at the interface between structure and reactions (population of entry states in heavy-ion fusion reactions, nuclear structure effects in proton evaporation spectra, nuclear structure- dependent entry state population by total spectroscopy, entrance channel effects in fusion near the barrier, lifetimes of subbarrier α particles by the atomic clock method), production and study of hot nuclei (the statistical model evaporation code EVAP, statistical emission of deuterons and tritons from highly excited compound nuclei, heavy-fragment emission as a probe of the thermal properties of highly excited compound nuclei, use of incoming-wave boundary condition transmission coefficients in the statistical model: implications in the particle evaporation spectra, study of transparency in the optical model), reaction mechanism studies (binary character of highly dissipative 209Bi + 136Xe collisions at E/A=28.2 MeV), and development and use of novel techniques and instrumentation in these areas of research (including a 4π channel selection device, a novel x-ray detector, and a simple channel-selecting detector)

  13. Investigations of nuclear structure and nuclear reactions induced by complex projectiles. Progress report for the period September 1, 1992--August 31, 1993

    Sarantites, D.G.

    1993-09-06

    This is a progress report on activities of the Washington University group in nuclear reaction studies for the period Sept 1, 1992 to Aug 31, 1993. This group has a research program which touches five areas of nuclear physics: nuclear structure studies at high spin; studies at the interface between structure and reactions; production and study of hot nuclei; reaction mechanism studies; development and use of novel techniques and instrumentation in the above areas of research. Specific activities of the group include in part: superdeformation in {sup 82}Sr; structure of and identical bands in {sup 182}Hg and {sup 178}Pt; a highly deformed band in {sup 136}Pm; particle decay of the {sup 164}Yb compound nucleus; fusion reactions; proton evaporation; two-proton decay of {sup 12}O; modeling and theoretical studies; excited {sup 16}O disassembly into four alpha particles; {sup 209}Bi + {sup 136}Xe collisions at 28.2 MeV/amu; and development work on 4{pi} solid angle gamma detectors, and x-ray detectors.

  14. Communication of nuclear data progress: No.11 (1994)

    Communication of Nuclear Data Progress (CNDP) is set up by Chinese Nuclear Data Center. This is the eleventh issue. It includes the measurements of 64,67Zn(n,p), 199Ir(n,2n) and 151,153Eu (n, γ) activation cross sections, the level structure of 154Gd and 182W; photonuclear data calculation of 27Al, 54Fe and 209Bi, introduction to the codes SPEC and DDCS, the evaluations and calculations of reactions 54,56,NatFe(n,x)51Cr, 52,54Mn, 197Au(n,3n) and (n,4n), and open problem on photon production calculation, intermediate-high energy nuclear reaction kinetic simulation and QMD, systematics of H(n,n); the evaluation of neutron induced data on 56Fe, nuclear data sheets update for A = 52,54,195, level spin assignment of superdeformed bands; Chinese Evaluated Nuclear Parameter Library (CENPL) (III), an auxiliary plotting code of UNF code, management program system of Chinese evaluated nuclear decay database; a method for evaluation of uncertainties for DDX, the Spline fitting for multi-set of correlative data; and activities and cooperation on nuclear data in China during 1993

  15. Trace element analysis in CRM of plant origin by inductively coupled plasma mass spectrometry

    Three CRMs of plant origin (SRM 1515 Apple Leaves, SRM 1570a Trace Elements in Spinach Leaves, and SRM 1575 Pine Needles) were used for analytical quality assurance of Cr, Mn, Fe, Co, Ni, Cu, Zn, As, Mo, Cd, and Pb determination by ICP-MS. The samples were decomposed using microwave assisted pressurized digestion by HNO3 and HNO3 + H2O2 mixture and temperature programmed dry ashing. Concentrations of elements in samples were evaluated by external calibration. All samples, blanks, and standards were spiked to 100 μg/L concentration of In and Bi as internal standards. During the measurement, signals of 52Cr, 53Cr, 54Fe, 55Mn, 59Co, 60Ni, 62Ni, 63Cu, 65Cu, 66Zn, 95Mo, 111Cd, 112Cd, 115In, 206Pb, 207Pb, 208Pb and 209Bi were monitored. Results of Pb, Cd, Cu, Zn, Mo and Co determination were in good agreement with certified values. In order to obtain accurate results for As at low levels, it was necessary to mathematically correct the analytical signal. This correction effectively eliminates the influence of interfering ArCl+ ions. For Cr analysis it is advisable to use as powerful oxidizing conditions during sample decomposition as possible. (orig.)

  16. Approaching complete low-spin spectroscopy of 210Bi with a cold-neutron capture reaction

    Cieplicka-Oryńczak, N.; Fornal, B.; Leoni, S.; Bazzacco, D.; Blanc, A.; Bocchi, G.; Bottoni, S.; de France, G.; Jentschel, M.; Köster, U.; Mutti, P.; Simpson, G.; Soldner, T.; Szpak, B.; Ur, C.; Urban, W.

    2016-05-01

    The low-spin structure of the 210Bi nucleus was investigated in the neutron capture experiment 209Bi(n ,γ )210Bi performed at ILL Grenoble at the PF1B cold-neutron facility. By using the EXILL multidetector array, consisting of 46 high-purity germanium crystals, and γ γ -coincidence technique, 64 primary γ rays were observed (40 new) and a total number of 70 discrete states (33 new) were located below the neutron binding energy in 210Bi. The analysis of the angular correlations of γ rays provided information about transitions multipolarities, which made it possible to confirm most of the previously known spin-parity assignments and helped establish new ones. The obtained experimental results were compared to shell-model calculations involving one-valence-proton, one-valence-neutron excitations outside the 208Pb core. It has been found that while up to the energy of ˜2 MeV each state observed in 210Bi has its calculated counterpart; at higher excitation energies some levels cannot be described by the valence particle couplings. These states may arise from couplings of valence particles to the 3- octupole phonon of the doubly magic 208Pb core and may serve as a testing ground for models which describe single particle-phonon excitations.

  17. Activation of Tl, Pb and Bi by 10-160 MeV neutrons: possible application to the analysis of Bi

    Parekh, P.P.; Finston, H.L.

    1981-01-01

    The medium energy intense neutrons (MEIN) available at the Brookhaven Chemistry Linac Irradiation Facility have an energy distribution up to approx. 160 MeV and an effective neutron flux of approx. 1.3 x 10/sup 11/ cm/sup -2/ s/sup -1/. The present work explores the feasibility of using this facility for the analysis of Tl, Pb and Bi by activation with MEIN. The most sensitive reactions, from a practical standpoint, were found to be Tl (n, xn) /sup 200/Tl (x = 4, 6), Pb (n, xn) /sup 204//sup m/Pb (x = 0, 3, 4, 5) and /sup 209/Bi (n, 6n) /sup 204/Bi. The absolute sensitivities attainable with these reactions are 0.1, 0.05 and 0.08 ..mu..g of Tl, Pb and Bi respectively, for 1 h irradiation at 1.3 x 10/sup 11/ n cm/sup -2/ s/sup -1/ with samples counted 2 h after the end of irradiation. The advantages of the method over thermal neutron activation analysis are that all three elements can be assayed at the sub-microgram concentration levels by ..gamma..-spectrometry with the help of a simple radiochemical purificaton and the analytical results can be verified by cross checking via the multiple (n, xn) reaction products. However, interference from Bi in the determination of Pb and from Pb and Bi in the determination of Tl limits its usefulness to the analysis of Bi.

  18. Global Optocal Potential for 6He Interactions at Low Energies

    A set of global optical potential has been derived to describe the interactions of 6He nucleus at energies near the Coulomb barrier. The elastic scattering angular distribution data for many systems ranging from 12C to 209Bi have been considered within the framework of the optical model by using the derived potential set and very good agreement has been obtained between theoretical results and experimental data. In the same study, we have also attempted to understand the reason why the elastic scattering of the halo nucleus 6He from heavy targets at incident energies near the Coulomb barrier displays a deviation from the standard Fresnel-type diffraction behavior due to the strong Coulomb dipole breakup coupling produced by the Coulomb field of the heavy target. In order to address this problem, we have also performed Continuum Discretized Coupled Channels calculations for the elastic scattering of 6He on 12C, 68Ni, 120Sn, 144Sm and 184Ta targets in order to determine the range of ZT where these large breakup coupling effect begins to be dominant. In our calculations, we find that the strong Coulomb dipole breakup coupling effect starts to be seen at around ZT=60.(author)

  19. The theory of the Bohr-Weisskopf effect in the hyperfine structure

    Karpeshin, F. F.; Trzhaskovskaya, M. B.

    2015-09-01

    Description of the Bohr-Wesskopf effect in the hyperfine structure of few-electron heavy ions is a challenging problem, which can be used as a test of both QED and atomic calculations. However, for twenty years the research has actually been going in a wrong direction, aimed at fighting the Bohr-Weisskopf effect through its cancellation in specific differences. Alternatively, we propose the constructive model-independent way, which enables the nuclear radii and their momenta to be retrieved from the hyper-fine splitting (HFS). The way is based on analogy of HFS to internal conversion coefficients, and the Bohr-Weisskopf effect - to the anomalies in the internal conversion coefficients. It is shown that the parameters which can be extracted from the data are the even nuclear momenta of the magnetization distribution. The radii R2 and - for the first time - R4 are obtained in this way by analysis of the experimental HFS values for the H- and Li-like ions of 209Bi. The critical prediction concerning the HFS for the 2p1/2 state is made. The present analysis shows high sensitivity of the method to the QED effects, which offers a way of precision test of QED. Experimental recommendations are given, which are aimed at retrieving data on the HFS values for a set of a few-electron configurations of each atom.

  20. The theory of the Bohr-Weisskopf effect in the hyperfine structure

    Karpeshin, F F

    2015-01-01

    For twenty years research into the anomalies in the HF spectra was going in a wrong direction by fighting the related Bohr-Weisskopf effect. As a way out, the model-independent way is proposed of estimating the nuclear radii from the hyper-fine splitting. The way is based on analogy of HFS to internal conversion coefficients, and the Bohr-Weisskopf effect - to the anomalies in the internal conversion coefficients. This makes transparent It is shown that the parameters which can be extracted from the data are the even nuclear moments of the magnetization distribution. The radii $R_2$ and (for the first time) $R_4$ are thus obtained by analysis of the experimental HFS for the H- and Li-like ions of $^{209}$Bi. The critical prediction of the HFS for the $2p_{1/2}$ state is discussed. The moments may be determined in this way only if the higher QED effects are properly taken into account. Therefore, this set of the parameters form a basis of a strict QED test. Experimental prospects are discussed, aimed at retrie...

  1. Progress report 1982

    The channels around the Studsvik R2-reactor are equipped with spectrometers and diffractometers for experiments using neutron scattering as a tool. The programme comprises the study of molecular motion in liquid metals and salts, the determination of static and dynamic scattering factors, and the diffusion of hydrogen in alloys. Elementary excitations in liquid 3He and the nuclear spin ordering in solid 3He are studied. The study of crystal structures has continued both with single crystals and powders. The number flux of the Studsvik R2-0 reactor which is up to 4 x 1011 thermal n/cm2/s is used in the isotope-separator-on-line experiment OSIRIS. The decay properties, including the emission of delayed neutrons of short-lived fission products and thermal neutron induced fission of 235U have been studied. The Van de Graaff accelerator is used for various experiments in neutron physics including elastic scattering from Pb and 209Bi, inelastic scattering from 141Pr and other precision measurements. The laboratory has participated in international intercomparison work. The accelerator is also used for integral determination of the decay heat in nuclear fuel, for neutron diagnostical methods and for analytical determination using the PIXE technique. The radiation chemistry group has studied primary reactors in crystalline organic materials using pulse radiolysis and ESR spectroscopy techniques. Recently, cationic species of hydrocarbons have been studied. (G.B.)

  2. The JEFF-3.1 Nuclear Data Library - JEFF Report 21

    The Joint Evaluated Fission and Fusion (JEFF) Project is a collaborative effort among the member countries of the NEA Data Bank to develop a reference nuclear data library. The JEFF library contains sets of evaluated nuclear data, mainly for fission and fusion applications; it contains a number of different data types, including neutron and proton interaction data, radioactive decay data, fission yield data, thermal scattering law data and photo-atomic interaction data. The latest version of the JEFF library, JEFF-3.1, was released by the NEA in May 2005. JEFF-3.1 combines the efforts of the JEFF and EFF/EAF (European Fusion File/European Activation File) working groups who have contributed to this combined fission and fusion library. The neutron general purpose library contains incident neutron data for 381 materials from 1H to 255Fm. The activation library (based on the European Activation File, EAF-2003) contains 774 different targets from 1H to 257Fm. The radioactive decay data library contains data for 3 852 isotopes, of which 226 are stable. The proton special purpose library contains incident proton data for 26 materials from 40Ca to 209Bi. The thermal scattering law library covers 9 materials, and the fission yield library covers 19 isotopes of neutron induced fission yield from 232Th to 245Cm and 3 isotopes with spontaneous fission yields (242Cm, 244Cm and 252Cf)

  3. Classical simulations of heavy-ion fusion reactions and weakly-bound projectile breakup reactions

    S S Godre

    2014-05-01

    Heavy-ion collision simulations in various classical models are discussed. Heavy-ion reactions with spherical and deformed nuclei are simulated in a classical rigid-body dynamics (CRBD) model which takes into account the reorientation of the deformed projectile. It is found that the barrier parameters depend not only on the initial orientations of the deformed nucleus, but also on the collision energy and the moment of inertia of the deformed nucleus. Maximum reorientation effect occurs at near- and below-barrier energies for light deformed nuclei. Calculated fusion crosssections for 24Mg + 208Pb reaction are compared with a static-barrier-penetration model (SBPM) calculation to see the effect of reorientation. Heavy-ion reactions are also simulated in a 3-stage classical molecular dynamics (3S-CMD) model in which the rigid-body constraints are relaxed when the two nuclei are close to the barrier thus, taking into account all the rotational and vibrational degrees of freedom in the same calculation. This model is extended to simulate heavy-ion reactions such as 6Li + 209Bi involving the weakly-bound projectile considered as a weakly-bound cluster of deuteron and 4He nuclei, thus, simulating a 3-body system in 3S-CMD model. All the essential features of breakup reactions, such as complete fusion, incomplete fusion, no-capture breakup and scattering are demonstrated.

  4. Studies of the giant resonances in heavy nuclei

    Experimental measurements of the eletrodisintegration cross section in 181Ta, 208Pb and 209Bi nuclei are made in the Linear Accelerator of the IFUSP-Brazil. The cross section is obtained by the direct counting of the emitted neutrons, in an electron excitation energy range between 8 to 22 MeV. The experimental data are analysed throught the virtual photon method, with the aim of obtaining the isoscalar and isovectorial electric quadrupole giant resonance (E2GR) intensities, as well as the magnetic dipole intensity. For each studied nucleus the results obtained for the E2GR, isoscalar and isovectorial, are compared with the photodisintegration cross section measured by the Saclay and Livermore laboratories. From this comparison, it is observed that the photodisintegration cross sections are compatibles with the existence of an isovector E2GR, located between 120 to 130 A-1/3 Mev and which exhaust around 100% of the Energy-Weighted Sum rules (EWSR). (L.C.)

  5. Decay of the ground state and the 29/2+ isomer in 217Ac and G factor measurements by perturbed angular distribution of α-particles

    The nucleus 217Ac was studied using the 205Tl(16O, 4n), 206Pb (15N, 4n) and 209Bi (12C, 4n) reactions. The measurements included α-γ, γ-γ, α-ce and ce-ce coincidence experiments as well as γ-ray and α-particle perturbed angular distribution studies. Results are: g(217Acsup(gs))=+0.85 (1) and Tsub(1/2)(217Acsup(gs))=69(4) ns, the shortest known α-decay of a ground state. 217Agsup(m) decays mainly by a γ cascade, but also by α-emission to the single particles states πhsub(9/2), fsub(7/2), isub(13/2) of 213Fr. Spins and parities of levels to the 29/2+ isomer at 2013 keV with Tsub(1/2)=740(40)ns and g=+0.347(5) are determined. The level scheme of 217Ac and the α decay of N=128 isotones are discussed. (orig.)

  6. Measurement of cross-sections of fission reactions induced by neutrons on actinides from the thorium cycle at n-TOF facility

    In the frame of innovating energy source system studies, thorium fuel cycle reactors are considered. Neutron induced fission cross section on such cycle involved actinides play a role in scenario studies. To feed them, data bases are built with experimental results and nuclear models. For some nuclei, they are not complete or in disagreement. In order to complete these data bases, we have built an original set up, consisting in an alternation of PPACs (Parallel Plate Avalanche Chamber) and ultra - thin targets, which we installed on n-TOF facility. We describe detectors, set up, and the particular care brought to target making and characterization. Fission products in coincidence are detected with precise time measurement and localization with delay line read out method. We contributed, within the n-TOF collaboration, to the CERN brand new intense spallation neutron source characterization, based on time of flight measurement, and we describe its characteristics and performances. We were able to measure such actinide fission cross sections as 232Th, 234U, 233U, 237Np, 209Bi, and natPb relative to 235U et 238U standards, using an innovative acquisition system. We took advantage of the lame accessible energy field, from 0.7 eV to 1 GeV, combined with the excellent energy resolution in this field. Data treatment and analysis advancement are described to enlighten performance and limits of the obtained results. (author)

  7. Study of 207Tl126 Produced in Deep-Inelastic Reactions

    Wilson E.

    2014-03-01

    Full Text Available Deep-inelastic collisions of a 208Pb beam on a 208Pb target were performed using the ATLAS accelerator at Argonne National Laboratory. The Gammasphere detector array was used for the detection of prompt and delayed gamma-rays of the reaction products.207Tl is one proton away from the 208Pb doubly-magic nucleus. Its low-energy level structure is dominated by the single proton-hole states πs1/2−1, πd3/2−1 and πh11/2−1. The 11/2− state is isomeric with T1/2 = 1.33(11 s. The reaction partner of 207Tl is 209Bi, which has arelatively well established level scheme compared to 207Tl. Cross-coincidences between these two nuclei were used to confirm or establish levels above the 11/2− isomeric state in 207Tl. These states are obtained via breaking of the neutron core. Angular correlation analysis was performed on known transitions in 208Pb, proving the applicability of this method for multipolarity assignment.

  8. Domain structure and magnetic resonance studies of ferroelastic BiVO4 revisited

    Choh, Sung Ho; Jang, Min Su

    2016-04-01

    Bismuth vanadate (BiVO4) is a ferroelastic material undergoing a reversible second order phase transition at 528 K(T c) between the tetragonal and monoclinic structure. There have been experimental studies on the incommensurate domain wall (W‧) which reported different orientation angles. In order to clarify this we have tried to calculate it numerically in terms of lattice constants above and below T c by employing the theory of Sapriel, and obtained it to be either 35.9° or 54.1°. It also turns out that the shear strain (S 21) in the ferroelastic phase depends on the crystal growing condition. The remaining internal stress appears to be responsible for the formation of W‧ wall. The host atom nuclear magnetic resonance and the S-state impurity electron magnetic resonance are also reviewed. The nuclear electric quadrupole interaction of 51V and 209Bi in BiVO4 was evaluated in terms of the point charge model based on the crystal structure. The result of electric field gradient tensor turns out to be reasonable with experimental values. The zero-field splitting tensor of Mn2+, Fe3+ and Gd3+ are also compared, and the deduced local environment of these ions in the host are confirmed. Finally the second-order phase transition according to the Landau’s framework is found in this crystal from the temperature dependence of magnetic resonance parameters. Supported by The National Academy of Sciences, Republic of Korea (2014) through SHC.

  9. Operation of Lanzhou all permanent electron cyclotron resonance ion source No. 2 on 320 kV platform with highly charged ions

    Lu, W.; Li, J. Y.; Kang, L.; Liu, H. P.; Li, H.; Li, J. D.; Sun, L. T.; Ma, X. W.

    2014-02-01

    The 320 kV platform for multi-discipline research with highly charged ions is a heavy ion beam acceleration instrument developed by Institute of Modern Physics, which is dedicated to basic scientific researches such as plasma, atom, material physics, and astrophysics, etc. The platform has delivered ion beams of 400 species for 36 000 h. The average operation time is around 5000 h/year. With the beams provided by the platform, lots of outstanding progresses were made in various research fields. The ion source of the platform is an all-permanent magnet electron cyclotron resonance ion source, LAPECR2 (Lanzhou All Permanent ECR ion source No. 2). The maximum axial magnetic fields are 1.28 T at injection and 1.07 T at extraction, and the radial magnetic field is up to 1.21 T at the inner wall of the plasma chamber. The ion source is capable to produce low, medium, and high charge state gaseous and metallic ion beams, such as H+, 40Ar8+, 129Xe30+, 209Bi33+, etc. This paper will present the latest result of LAPECR2 and the routine operation status for the high voltage platform.

  10. Determination of total and isotopic uranium and total thorium in soils by inductively coupled plasma-mass spectrometry

    Inductively coupled plasma-mass spectrometry (ICP-MS), using standard sample introduction by peristaltic pumping, is presented as a method to determine total and isotopic uranium (234U, 235U, 236U, and 238U) and thorium (232Th) in soil samples. Initial sample preparation consists of oven drying to determine moisture content, and grinding and mixing the soil to make it homogeneous. This is followed by a nitric/hydrofluoric acid digestion to bring the uranium into solution. Bismuth (209Bi) is added prior to digestion to monitor for losses due to sample preparation and analysis. An addition digestion, using nitric/perchloric acid is performed if the total thorium concentration is required on the sample. The uranium and thorium content of this solution and the 235U/238U ratio are measured on an initial pass through the ICP-MS. The total uranium measurement is based on the 238U isotope measurement with correction for the presence of the U isotopes. To determine the concentration of the less abundant 234U and 236U isotopes, the digestate is further concentrated by using a solid phase extraction column (TRU.Spec by EiChrom Industries, Inc.) before a second pass through the ICP-MS

  11. Experimental studies of highly charged ions in a Penning trap for the measurement of electron magnetic moments by double-resonance spectroscopy

    A precise measurement of bound-electron g factors in highly charged ions provides stringent tests for state-of-the-art theoretical calculations, such as relativistic electron-correlation, bound-state QED, and higher-order Zeeman effects. We excite the fine-structure transition of boronlike argon (40Ar13+) with laser radiation and probe microwave transitions between Zeeman sub-levels in the magnetic field of a Penning trap. From this laser-microwave double-resonance technique the g factor can be determined on a ppb level of accuracy in our apparatus. We have built a novel 'half-open' Penning trap with high fluorescence-detection efficiency and an integrated electron-beam ion source for production of highly charged ions from gas, injected through a cryogenic valve. In the future, heavier ions shall be captured from the HITRAP facility at GSI and the method shall be applied to hyperfine-structure transitions of hydrogenlike bismuth (209Bi82+) in order to measure electronic and nuclear magnetic moments. This thesis presents experimental developments as well as production, cooling, transport, and long-term storage of highly charged argon ions.

  12. Operation of Lanzhou all permanent electron cyclotron resonance ion source No. 2 on 320 kV platform with highly charged ions

    The 320 kV platform for multi-discipline research with highly charged ions is a heavy ion beam acceleration instrument developed by Institute of Modern Physics, which is dedicated to basic scientific researches such as plasma, atom, material physics, and astrophysics, etc. The platform has delivered ion beams of 400 species for 36 000 h. The average operation time is around 5000 h/year. With the beams provided by the platform, lots of outstanding progresses were made in various research fields. The ion source of the platform is an all-permanent magnet electron cyclotron resonance ion source, LAPECR2 (Lanzhou All Permanent ECR ion source No. 2). The maximum axial magnetic fields are 1.28 T at injection and 1.07 T at extraction, and the radial magnetic field is up to 1.21 T at the inner wall of the plasma chamber. The ion source is capable to produce low, medium, and high charge state gaseous and metallic ion beams, such as H+, 40Ar8+, 129Xe30+, 209Bi33+, etc. This paper will present the latest result of LAPECR2 and the routine operation status for the high voltage platform

  13. Effects of the density of collision cascades: Separating contributions from dynamic annealing and energy spikes

    Titov, A.I.; Karaseov, P.A.; Azarov, A.Yu. [Department of Physical Electronics, St. Petersburg State Polytechnic University, St. Petersburg 195251 (Russian Federation); Kucheyev, S.O. [Lawrence Livermore National Laboratory, Livermore, CA 94551 (United States)], E-mail: kucheyev@llnl.gov

    2009-08-15

    We present a quantitative model for the efficiency of the molecular effect in damage buildup in semiconductors. Our model takes into account only one mechanism of the dependence of damage buildup efficiency on the density of collision cascades: nonlinear energy spikes. In our three-dimensional analysis, the volume of each individual collision cascade is divided into small cubic cells, and the number of cells that have an average density of displacements above some threshold value is calculated. We assume that such cells experience a catastrophic crystalline-to-amorphous phase transition, while defects in the cells with lower displacement densities have perfect annihilation. For the two limiting cases of heavy (500 keV/atom {sup 209}Bi) and light (40 keV/atom {sup 14}N) ion bombardment of Si, theory predictions are in good agreement with experimental data for a threshold displacement density of 4.5 at.%. For intermediate density cascades produced by small 2.1 keV/amu PF{sub n} clusters, we show that dynamic annealing processes entirely dominate cascade density effects for PF{sub 2} ions, while energy spikes begin contributing in the case of PF{sub 4} cluster bombardment.

  14. Effects of the density of collision cascades: Separating contributions from dynamic annealing and energy spikes

    We present a quantitative model for the efficiency of the molecular effect in damage buildup in semiconductors. Our model takes into account only one mechanism of the dependence of damage buildup efficiency on the density of collision cascades: nonlinear energy spikes. In our three-dimensional analysis, the volume of each individual collision cascade is divided into small cubic cells, and the number of cells that have an average density of displacements above some threshold value is calculated. We assume that such cells experience a catastrophic crystalline-to-amorphous phase transition, while defects in the cells with lower displacement densities have perfect annihilation. For the two limiting cases of heavy (500 keV/atom 209Bi) and light (40 keV/atom 14N) ion bombardment of Si, theory predictions are in good agreement with experimental data for a threshold displacement density of 4.5 at.%. For intermediate density cascades produced by small 2.1 keV/amu PFn clusters, we show that dynamic annealing processes entirely dominate cascade density effects for PF2 ions, while energy spikes begin contributing in the case of PF4 cluster bombardment.

  15. Operation of Lanzhou all permanent electron cyclotron resonance ion source No. 2 on 320 kV platform with highly charged ions.

    Lu, W; Li, J Y; Kang, L; Liu, H P; Li, H; Li, J D; Sun, L T; Ma, X W

    2014-02-01

    The 320 kV platform for multi-discipline research with highly charged ions is a heavy ion beam acceleration instrument developed by Institute of Modern Physics, which is dedicated to basic scientific researches such as plasma, atom, material physics, and astrophysics, etc. The platform has delivered ion beams of 400 species for 36,000 h. The average operation time is around 5000 h/year. With the beams provided by the platform, lots of outstanding progresses were made in various research fields. The ion source of the platform is an all-permanent magnet electron cyclotron resonance ion source, LAPECR2 (Lanzhou All Permanent ECR ion source No. 2). The maximum axial magnetic fields are 1.28 T at injection and 1.07 T at extraction, and the radial magnetic field is up to 1.21 T at the inner wall of the plasma chamber. The ion source is capable to produce low, medium, and high charge state gaseous and metallic ion beams, such as H(+), (40)Ar(8+), (129)Xe(30+), (209)Bi(33+), etc. This paper will present the latest result of LAPECR2 and the routine operation status for the high voltage platform. PMID:24593526

  16. 1n-decay cross-section of superheavy nuclei with ZCN =102-113 using hot and cold orientations

    The quest to synthesize new elements with Z ≥ 101 is materialized using the heavy ion- induced reaction dynamics. Within this interaction process, the superheavy elements lying in range Z=102-113 are synthesized within the cold fusion reactions, whereas the formation of Z ≥ 114 is carried out using the well-known hot fusion process. In cold fusion synthesis, usually 208Pb and 209Bi target nuclei are bombarded with neutron rich projectiles having masses in the range A2 =50-70. These reactions are characterized by low excitation energies accompanied via 1 or 2 neutron(s) emission. Hence high survival probability is expected for compound nucleus formed within the cold fusion process. On the other hand, this interaction process has limited scope of extension, because as ZCN increases, the production cross-sections of evaporation residues decrease sharply. The decrement in cross-section is due to the competing role of other processes like quasi-fission in the competition with complete fusion

  17. Study on target spallation reaction cross sections induced by high energy neutrons and heavy ions

    Nakamura, Takashi [Tohoku Univ., Sendai (Japan). Cyclotron and Radioisotope Center

    1996-03-01

    The target spallation reaction cross sections of neutrons and heavy ions which have not been observed are determined in this paper. The object of this work is to make clear the differences between the spallation reaction cross section of neutron and that of proton by comparing the obtained value of neutron with the known value of proton. To this end, the quasi monochromatic neutron field of 20{approx}50 MeV was developed in 4 cyclotrons, INS, CYRIC, TIARA and RIKEN. The nuclear spallation reaction cross sections of C, Al and Bi were measured in the above field and the distribution of nuclear spallation reaction products in Cu determined by C ion beam of HIMAC. {sup 12}C(n,2n){sup 11}C reaction cross section shows the maximum value of about 20 mb at near 40{approx}50 MeV and then the value gradually decreased to 10 mb. The cross sections of {sup 209}Bi(n,Xn) are shown. The distribution of {sup 61}Cu is lower at the entrance and higher in the depth. (S.Y.)

  18. Systematics of photopion reaction yields at intermediate energies

    Sakamoto, Hiroshi [Kanazawa Univ. (Japan). Faculty of Science

    1996-03-01

    Our development in radiochemical measurements of photopion yields from complex nuclei ranging from {sup 7}Li to {sup 209}Bi at intermediate energies is reviewed. It has been found from systematized yields with respect to photon-energies, types of photopion reaction and target masses that (1) photons responsible for the ({gamma}, {pi}{sup +}), ({gamma}, {pi}{sup -}) and ({gamma}, {pi}{sup -}xn) reactions upto x=9 are mostly of energies lower than 400 MeV but higher than 140 MeV (pion rest mass), (2) ({gamma}, {pi}{sup +}) and ({gamma}, {pi}{sup -}) yields are independent of target mass (A{sub t}) heavier than A{sub t}{approx}30, and the yield ratio of Y({gamma}, {pi}{sup -})/Y({gamma}, {pi}{sup +}) is 5-6 irrespective of photon energies concerned, and (3) the yield variations of ({gamma}, {pi}{sup -}xn) reactions are well expressed as functions of (N/Z) of targets and neutron multiplicity. These findings appear to imply requirements of new concepts on neutron density distributions and photonuclear processes in complex nuclei. (author)

  19. Astatine-211: production and availability.

    Zalutsky, Michael R; Pruszynski, Marek

    2011-07-01

    The 7.2-h half life radiohalogen (211)At offers many potential advantages for targeted α-particle therapy; however, its use for this purpose is constrained by its limited availability. Astatine-211 can be produced in reasonable yield from natural bismuth targets via the (209)Bi(α,2n)(211)At nuclear reaction utilizing straightforward methods. There is some debate as to the best incident α-particle energy for maximizing 211At production while minimizing production of (210)At, which is problematic because of its 138.4-day half life α-particle emitting daughter, (210)Po. The intrinsic cost for producing (211)At is reasonably modest and comparable to that of commercially available (123)I. The major impediment to (211)At availability is attributed to the need for a medium energy α-particle beam for its production. On the other hand, there are about 30 cyclotrons in the world that have the beam characteristics required for (211)At production. PMID:22201707

  20. Observation of electric quadrupole X-ray transitions in muonic thallium, lead and bismuth

    Schneuwly, H; Engfer, R; Jahnke, U; Kankeleit, E; Lindenberger, K H; Pearce, R M; Petitjean, C; Schellenberg, L; Schröder, W U; Walter, H K; Zehnder, A

    1972-01-01

    Electric quadrupole X-ray transitions (5g to 3d, 4f to 2p, and 3d to 1s) have been observed in muonic Tl, Pb and Bi. From the 3 to 1 transitions, energy splittings of the n=3 levels were deduced. From a comparison of the relative intensities of E1 and E2 transitions the population ratios 5g/5f, 4f/4d, and 3d/3p were deduced. These ratios are well reproduced by a cascade calculation assuming a statistical initial population at n=20, including K, L and M shell conversion. In the case of /sup 205/Tl discrepancies between the experimental and the calculated 3d-1s/3p-is intensity ratio can be explained by nuclear excitation. From the 3p/sub 3/2/ to 1s/sub 1/2/ intensity in /sup 209 /Bi one can deduce the ratio of the radiationless to the X-ray transition width and give limits for prompt neutron emission from the 3d level. (23 refs).

  1. Effects of the density of collision cascades: Separating contributions from dynamic annealing and energy spikes

    Titov, A I; Karaseov, P A; Azarov, A Y; Kucheyev, S O

    2008-08-13

    We present a quantitative model for the efficiency of the molecular effect in damage buildup in semiconductors. Our model takes into account only one mechanism of the cascade density dependence: nonlinear energy spikes. In our three-dimensional analysis, the volume of each individual collision cascade is divided into small cubic cells, and the number of cells that have an average density of displacements above some threshold value is calculated. We assume that such cells experience a catastrophic crystalline-to-amorphous phase transition, while defects in the cells with lower displacement densities have perfect annihilation. For the two limiting cases of heavy (500 keV/atom {sup 209}Bi) and light (40 keV/atom {sup 14}N) ion bombardment of Si, theory predictions are in good agreement with experimental data for a threshold displacement density of 4.5 at.%. For intermediate density cascades produced by small 2.1 keV/amu PF{sub n} clusters, we show that dynamic annealing processes entirely dominate cascade density effects for PF{sub 2} ions, while energy spikes begin contributing in the case of PF{sub 4} cluster bombardment.

  2. Nuclear reactions with radioactive and stable beams (Part I)

    At the present time there is a great interest at world level in experiments, with accelerated nuclei of short half life. The dispersion, fusion, transfer and break processes in the interaction of weakly light projectiles bounded with targets of Z great its have been object of intense recent investigation, at world level. Our group, in collaboration with the University of Notre Dame, it has measured and analyzed these processes for weakly bound systems as: 6He + 209Bi, 8Li + 208Pb, 10Be + 208Pb. On the other hand a research line that has wakened up great interest, it is that of studies of resonant reactions using the Inverse Kinematics technique with thick targets. The use of this technique allows to measure an entire excitation function with a single bombardment. Our group has carried out, in the ININ, preliminary bombardments for the system 12C + 4He. This allowed to establish the feasibility of implementing this technique in our Laboratory. The application of this and other techniques to different systems like 18O + 4He, 12C + 12C, 12C + 16O, 16O + 16O, it opens the possibility to measure the fusion of these systems at very low energy and to deepen in the knowledge of the nuclear structure and the nuclear astrophysics. In this technical report, the activities carried out by our group during 2004 are described.(Author)

  3. Excitation function for the production of 262Bh (Z=107) in the odd-Z-projectile reaction 208Pb(55Mn, n)

    The excitation function for production of 262Bh in the odd-Z-projectile reaction 208Pb(55Mn, n) has been measured at three projectile energies using the Berkeley Gas-filled Separator at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. In total, 33 decay chains originating from 262Bh and 2 decay chains originating from 261Bh were observed. The measured decay properties are in good agreement with previous reports. The maximum cross section of 540-150+180 pb is observed at a lab-frame center-of-target energy of 264.0 MeV and is more than five times larger than that expected based on previously reported results for production of 262Bh in the analogous even-Z-projectile reaction 209Bi(54Cr, n). Our results indicate that the optimum beam energy in one-neutron-out heavy-ion fusion reactions can be estimated simply using the optimum energy rule proposed by SwiaPtecki, Siwek-Wilczynska, and Wilczynski

  4. Alpha-decay properties of 261Bh

    The isotope 261Bh was produced in the reaction 209Bi(54Cr,2n)261Bh and its α decay has been remeasured. It was found that it populates by an unhindered transition of ∼ 10 MeV an excited level at E* >350 keV in the daughter nucleus 257Db. The latter decays by internal transitions either into the isomeric state or the ground state. A somewhat improved half-life value of T1/2=11.8+3.9-2.4 ms was obtained for 261Bh. The data support the previous assignment of the α activities 257Db (1) and 257Db (2) to the isomer and to the ground state, respectively. No evidence for an isomeric state in 261Bh decaying by α emission was found. Based on the experimental results and theoretical calculations a partial decay scheme of 261Bh including spin and parity assignments of the ground-state and excited levels in the daughter nucleus 257Db populated by the α decay and succeeding internal transitions have been suggested. 261Bh represents so far the heaviest nucleus for which such an attempt has been made. No spontaneous fission (SF) events that could be attributed to 261Bh were observed, resulting in an SF branching bSF*=22 MeV. (orig.)

  5. Measurement of cross-sections of fission reactions induced by neutrons on actinides from the thorium cycle at n-TOF facility; Mesures de sections efficaces de fission induite par neutrons sur des actinides du cycle du thorium a n-TOF

    Ferrant, L

    2005-09-01

    In the frame of innovating energy source system studies, thorium fuel cycle reactors are considered. Neutron induced fission cross section on such cycle involved actinides play a role in scenario studies. To feed them, data bases are built with experimental results and nuclear models. For some nuclei, they are not complete or in disagreement. In order to complete these data bases, we have built an original set up, consisting in an alternation of PPACs (Parallel Plate Avalanche Chamber) and ultra - thin targets, which we installed on n-TOF facility. We describe detectors, set up, and the particular care brought to target making and characterization. Fission products in coincidence are detected with precise time measurement and localization with delay line read out method. We contributed, within the n-TOF collaboration, to the CERN brand new intense spallation neutron source characterization, based on time of flight measurement, and we describe its characteristics and performances. We were able to measure such actinide fission cross sections as {sup 232}Th, {sup 234}U, {sup 233}U, {sup 237}Np, {sup 209}Bi, and {sup nat}Pb relative to {sup 235}U et {sup 238}U standards, using an innovative acquisition system. We took advantage of the lame accessible energy field, from 0.7 eV to 1 GeV, combined with the excellent energy resolution in this field. Data treatment and analysis advancement are described to enlighten performance and limits of the obtained results. (author)

  6. Experiments on Synthesis of the Heaviest Element at RIKEN

    At the Institute of Physical and Chemical Research (RIKEN) a series of experiments studying the productions and their decays of the heaviest elements have been performed by using a gas-filled recoil ion separator GARIS. Results on the isotope of the 112th element, 277112, and on that of the 113th element, 278113, are reviewed. Tow decay chains which are assigned to be ones originating from the isotope 277112 were observed in the 208Pb(70Zn, n) reaction. Both chains consisted of four consecutive alpha decays followed by a spontaneous fission. The results provide a confirmation of the production and decay of the isotope 277112 reported by a research group at Gesellschaft fuer Schwerionenforschung (GSI), Germany, produced via the same reaction by using a velocity filter. Tow decay chains, both consisted of four consecutive alpha decays followed by a spontaneous fission, were observed also in the reaction 209Bi(70Zn, n). Those are assigned to be the convincing candidate events of the decays of the isotope of the 113th element, 278113, and its daughter nuclei, 274Rg, 270Mt, 266Bh, and 262Db

  7. Experiments on searching for the heaviest elements

    At the Institute of Physical and Chemical Research (RIKEN) a series of experiments studying the productions and their decays of the heaviest elements have been performed by using a gas-filled recoil ion separator GARIS. Results on the isotope of the 112th element, 277112, and on that of the 113th element, 278113, are reviewed. Tow decay chains which are assigned to be ones originating from the isotope 277112 were observed in the 208Pb(70Zn, n) reaction. Both chains consisted of four consecutive alpha decays followed by a spontaneous fission. The results provide a confirmation of the production and decay of the isotope 277112 reported by a research group at Gesellschaft fuer Schwerionenforschung (GSI), Germany, produced via the same reaction by using a velocity filter. Tow decay chains, both consisted of four consecutive alpha decays followed by a spontaneous fission, were observed also in the reaction 209Bi(70Zn, n). Those are assigned to be the convincing candidate events of the decays of the isotope of the 113th element, 278113, and its daughter nuclei, 274Rg, 270Mt, 266Bh, and 262Db

  8. Status of heavy element research using GARIS at RIKEN

    Morita, K. E-mail: morita@rarfaxp.riken.jp; Morimoto, K.K.; Kaji, D.; Goto, S.; Haba, H.; Ideguchi, E.; Kanungo, R.; Katori, K.; Koura, H.; Kudo, H.; Ohnishi, T.; Ozawa, A.; Peter, J.C.; Suda, T.; Sueki, K.; Tanihata, I.; Tokanai, F.; Xu, H.; Yeremin, A.V.; Yoneda, A.; Yoshida, A.; Zhao, Y.-L.; Zheng, T

    2004-04-05

    A gas-filled recoil separator GARIS was installed at the RIKEN Linear Accelerator facility. Using the separator, two reactions, {sup 208}Pb({sup 64}Ni, 1n), and {sup 209}Bi({sup 64}Ni, 1n), were investigated. In the first reaction we observed fourteen {alpha}-decay chains which were assigned to be the decays starting from the isotope {sup 271}Ds(Z=110). The {alpha}-decay energies as well as the decay times coincided well with the values reported by GSI group. Existence of an isomeric state in {sup 271}Ds became clear from the present work. In the second reaction we have observed 14 {alpha}-decay chains that can be assigned to subsequent decays from {sup 272}111. The present result is the first clear confirmation for the discovery of {sup 272}111 and its {alpha}-decay products, {sup 264}Bh and {sup 268}Mt, reported previously by a GSI group. New information on their half-lives and decay energies is presented.

  9. Experiments on searching for the heaviest elements

    Morita, Kosuke [Superheavy Element Laboratory, RIKEN Nishina Center for Accelerator Based Science, RIKEN, Wako-shi, Saitama 351-0198 (Japan)

    2008-06-01

    At the Institute of Physical and Chemical Research (RIKEN) a series of experiments studying the productions and their decays of the heaviest elements have been performed by using a gas-filled recoil ion separator GARIS. Results on the isotope of the 112th element, {sup 277}112, and on that of the 113th element, {sup 278}113, are reviewed. Tow decay chains which are assigned to be ones originating from the isotope {sup 277}112 were observed in the {sup 208}Pb({sup 70}Zn, n) reaction. Both chains consisted of four consecutive alpha decays followed by a spontaneous fission. The results provide a confirmation of the production and decay of the isotope {sup 277}112 reported by a research group at Gesellschaft fuer Schwerionenforschung (GSI), Germany, produced via the same reaction by using a velocity filter. Tow decay chains, both consisted of four consecutive alpha decays followed by a spontaneous fission, were observed also in the reaction {sup 209}Bi({sup 70}Zn, n). Those are assigned to be the convincing candidate events of the decays of the isotope of the 113th element, {sup 278}113, and its daughter nuclei, {sup 274}Rg, {sup 270}Mt, {sup 266}Bh, and {sup 262}Db.

  10. Scattering of 11Be around the Coulomb barrier

    The 11Be is a halo nucleus composed of a 10Be core and a weakly bound neutron. Due to its loosely bound structure, the coupling of the ground and exited states to the continuum should strongly affect the elastic cross sections at energies around the Coulomb barrier [1, 2]. Another important issue is the role played by the highly deformed 10Be core on the scattering cross sections [3]. Accurate data on 11Be scattering are needed to study these effects. However, existing data for 11Be + 209Bi scattering [4, 5], suffer of large experimental uncertainties, and elastic and other reaction channels could not be studied separately. Aiming to improve the experimental situation we have recently performed measurements of 11Be scattered on 120Sn at 32 MeV (Lab) at the REX-ISOLDE facility at CERN (Geneva), covering a wide angular range. In this work, we present preliminary results of the experiment for the 11Be+120Sn quasi-elastic scattering as well as for the 11Be→ 10Be + n breakup. The accuracy and angular range of the presented results provide stronger constrains to the theoretical interpretation than existing published results. We compare the experimental results with CDCC and DWBA calculations performed as in references [6-8] for the 6He + 208Pb system. The role played by transfer and breakup channels in the elastic scattering is discussed.(author)

  11. Raman investigation of lattice defects and stress induced in InP and GaN films by swift heavy ion irradiation

    Hu, P. P.; Liu, J.; Zhang, S. X.; Maaz, K.; Zeng, J.; Guo, H.; Zhai, P. F.; Duan, J. L.; Sun, Y. M.; Hou, M. D.

    2016-04-01

    InP crystals and GaN films were irradiated by swift heavy ions 86Kr and 209Bi with kinetic energies of 25 and 9.5 MeV per nucleon and ion fluence in the range 5 × 1010 to 3.6 × 1012 ions/cm2. The characteristic optical bands were studied by Raman spectroscopy to reveal the disorder and defects induced in the samples during the irradiation process. The crystallinity of InP and GaN was found to be deteriorated after irradiation by the swift heavy ions and resulted in the amorphous nature of the samples along the ion tracks. The amorphous tracks observed by transmission electron microscopy (TEM) images confirmed the formation of lattice defects. In typical F2(LO) mode, in case of InP, the spectra shifted towards the lower wavenumbers with a maximum shift of 7.6 cm-1 induced by 1030 MeV Bi ion irradiation. While in case of GaN, the typical E2(high) mode shifted towards the higher wavenumbers, with maximum shift of 5.4 cm-1 induced by 760 MeV Bi ion irradiation at ion fluence of 1 × 1012 ions/cm2. The observed Raman shifts reveal the presence of lattice defects and disorder induced in the samples after irradiation by the swift heavy ions. This irradiation also generated lattice stress in the samples, which has been investigated and discussed in detail in this work.

  12. Study of 207Tl126 produced in deep-inelastic reactions

    Deep-inelastic collisions of a 208Pb beam on a 208Pb target were performed using the ATLAS accelerator at Argonne National Laboratory. The Gamma-sphere detector array was used for the detection of prompt and delayed gamma-rays of the reaction products. 207Tl is one proton away from the 208Pb doubly-magic nucleus. Its low-energy level structure is dominated by the single proton-hole states πs(1/2)-1, πd(3/2)-1 and πh(11/2)-1. The (11/2)- state is isomeric with T1/2= 1.33(11) s. The reaction partner of 207Tl is 209Bi, which has a relatively well established level scheme compared to 207Tl. Cross-coincidences between these two nuclei were used to confirm or establish levels above the (11/2)- isomeric state in 207Tl. These states are obtained via the breaking of the neutron core. Angular correlation analysis was performed on known transitions in 208Pb, proving the applicability of this method for multipolarity assignment. (authors)

  13. Importance of lifetime effects in breakup and suppression of complete fusion in reactions of weakly bound nuclei

    Cook, K J; Luong, D H; Kalkal, Sunil; Dasgupta, M; Hinde, D J

    2016-01-01

    Complete fusion cross sections in collisions of light, weakly bound nuclei and high Z targets show above-barrier suppression of complete fusion. This has been interpreted as resulting from breakup of the weakly bound nucleus prior to reaching the fusion barrier, reducing the probability of complete fusion. This paper investigates how these conclusions are affected by lifetimes of the resonant states that are populated prior to breakup. If the mean life of a populated resonance is much longer than the fusion timescale, then its breakup cannot suppress complete fusion. For short-lived resonances, the situation is more complex. This work includes the mean life of the short-lived 2+ resonance in 8Be in classical dynamical model calculations to determine its effect on energy and angular correlations of the breakup fragments and on predictions of fusion suppression. Coincidence measurements of breakup fragments produced in reactions of 9Be with 144Sm, 168Er, 186W, 196Pt, 208Pb and 209Bi at energies below the barrie...

  14. Techniques for the discovery of new elements

    Search for new elements is part of the broader field of investigations of nuclei at the limits of stability. In two series of experiments at SHIP, six new elements (Z=107-112) were synthesized via fusion reactions by 1n-deexcitation channels using lead or bismuth targets. The isotopes were unambiguously identified by means of αα correlations. Alpha decay, and not fission, is the dominant decay mode due to strong shell effects. Cross sections drop by two orders of magnitude from nielsbohrium (Z=107) to element 112, for which a cross section of 1 pb was measured. The development of intensive beam currents and sensitive detection methods is a necessity, aiming at production and identification of still heavier elements and new isotopes of already known elements, as well as small α-, β- and fission-branching ratios. An equally sensitive set-up is needed for measurement of excitation functions at low cross sections. Our results give hope that isotopes of element 114 close to the island of spherical superheavy elements could be produced by fusion reactions using 208Pb or 209Bi targets. Systematic studies of the reaction cross sections indicate that transfer of nucleons is the important process to initiate the fusion process. (orig.)

  15. Techniques for the discovery of new elements

    Hofmann, S.

    Search for new elements is part of the broader field of investigations of nuclei at the limits of stability. In two series of experiments at SHIP, six new elements ( Z = 107-112) were synthesized via fusion reactions by 1n-deexcitation channels using lead or bismuth targets. The isotopes were unambiguously identified by means of αα correlations. Alpha decay, and not fission, is the dominant decay mode due to strong shell effects. Cross sections drop by two orders of magnitude from nielsbohrium ( Z = 107) to element 112, for which a cross section of 1 pb was measured. The development of intensive beam currents and sensitive detection methods is a necessity, aiming at production and identification of still heavier elements and new isotopes of already known elements, as well as small α-, β- and fission-branching ratios. An equally sensitive set-up is needed for measurement of excitation functions at low cross sections. Our results give hope that isotopes of element 114 close to the island of spherical superheavy elements could be produced by fusion reactions using 208Pb or 209Bi targets. Systematic studies of the reaction cross sections indicate that transfer of nucleons is the important process to initiate the fusion process.

  16. Techniques for the discovery of new elements

    Hofmann, S. [Gesellschaft fuer Schwerionenforschung mbH, Darmstadt (Germany)

    1997-04-01

    Search for new elements is part of the broader field of investigations of nuclei at the limits of stability. In two series of experiments at SHIP, six new elements (Z=107-112) were synthesized via fusion reactions by 1n-deexcitation channels using lead or bismuth targets. The isotopes were unambiguously identified by means of {alpha}{alpha} correlations. Alpha decay, and not fission, is the dominant decay mode due to strong shell effects. Cross sections drop by two orders of magnitude from nielsbohrium (Z=107) to element 112, for which a cross section of 1 pb was measured. The development of intensive beam currents and sensitive detection methods is a necessity, aiming at production and identification of still heavier elements and new isotopes of already known elements, as well as small {alpha}-, {beta}- and fission-branching ratios. An equally sensitive set-up is needed for measurement of excitation functions at low cross sections. Our results give hope that isotopes of element 114 close to the island of spherical superheavy elements could be produced by fusion reactions using {sup 208}Pb or {sup 209}Bi targets. Systematic studies of the reaction cross sections indicate that transfer of nucleons is the important process to initiate the fusion process. (orig.). 37 refs.

  17. Nuclear reactions with radioactive and stable beams (Part I); Reacciones nucleares con haces radiactivos y estables (Parte I)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2004-12-15

    At the present time there is a great interest at world level in experiments, with accelerated nuclei of short half life. The dispersion, fusion, transfer and break processes in the interaction of weakly light projectiles bounded with targets of Z great its have been object of intense recent investigation, at world level. Our group, in collaboration with the University of Notre Dame, it has measured and analyzed these processes for weakly bound systems as: {sup 6}He + {sup 209}Bi, {sup 8}Li + {sup 208}Pb, {sup 10}Be + {sup 208}Pb. On the other hand a research line that has wakened up great interest, it is that of studies of resonant reactions using the Inverse Kinematics technique with thick targets. The use of this technique allows to measure an entire excitation function with a single bombardment. Our group has carried out, in the ININ, preliminary bombardments for the system {sup 12}C + {sup 4}He. This allowed to establish the feasibility of implementing this technique in our Laboratory. The application of this and other techniques to different systems like {sup 18}O + {sup 4}He, {sup 12}C + {sup 12}C, {sup 12}C + {sup 16}O, {sup 16}O + {sup 16}O, it opens the possibility to measure the fusion of these systems at very low energy and to deepen in the knowledge of the nuclear structure and the nuclear astrophysics. In this technical report, the activities carried out by our group during 2004 are described.(Author)

  18. The Karlsruhe Astrophysical Database of Nucleosynthesis in Stars Project – Status and Prospects

    The KADoNiS (Karlsruhe Astrophysical Database of Nucleosynthesis in Stars) project is an astrophysical online database for cross sections relevant for nucleosynthesis in the s process and the γ process. The s-process database ( (http://www.kadonis.org)) was started in 2005 and is presently facing its 4th update (KADoNiS v1.0). The γ-process database (KADoNiS-p, (http://www.kadonis.org/pprocess)) was recently revised and re-launched in March 2013. Both databases are compilations for experimental cross sections with relevance to heavy ion nucleosynthesis. For the s process recommended Maxwellian averaged cross sections for kT=5−100 keV are given for more than 360 isotopes between 1H and 210Bi. For the γ-process database all available experimental data from (p,γ),(p,n),(p,α),(α,γ),(α,n), and (α,p) reactions between 70Ge and 209Bi in or close to the respective Gamow window were collected and can be compared to theoretical predictions. The aim of both databases is a quick and user-friendly access to the available data in the astrophysically relevant energy regions

  19. Nuclear data for design analyses of the test blanket modules in ITER: Review and recommendations for EFF/JEFF evaluations

    This ppt-presentation gives an overview of ITER materials for nuclear analysis (Test Blanket Modules (TBM); Shield modules, vacuum vessel, plasma facing components; superconducting magnet, minor importance materials), a review of available nuclear data evaluations (EFF-3/JEFF-3.0 (EU); FENDL-2.0, JENDL-3.3, ENDF/B-VI; MF=6 data, co-variances, γ-production; benchmark analyses (data quality)) and recommendations for evaluations (priorities for EFF data evaluations in FP6; update/revision/completion of data evaluations according to needs for TBM design; extension for E > 20 MeV (IFMIF application)) for the isotopes 9Be, natPb, 204Pb, 206Pb, 208Pb, 6Li, 7Li, 28Si, 29Si, 30Si, 16O, 54Fe, 56Fe, 57Fe, 58Fe, 50Cr, 52Cr, 53Cr, 54Cr, natW, 182W, 183W, 184W, 186W, 181Ta, 63Cu, 65Cu, natTi, 46Ti, 47Ti, 48Ti, 49Ti, 12C, 23Na, 39K, 1H and many more

  20. Nuclear-decay studies of neutron-rich rare-earth nuclides

    Neutron-rich rare-earth nuclei were produced in multinucleon transfer reactions of 170Er and 176Yb projectiles on natW targets at the Lawrence Berkeley Laboratory SuperHILAC and their radioactive decays properties studied at the on-line mass separation facility OASIS. Two unknown isotopes, 169Dy (t 1/2 = 39 ± 8 s) and 174Er(t1/2 = 3.3 ± 0.2 m) were discovered and their decay characteristics determined. The decay schemes for two previously identified isotopes, 168Dy (t1/2 = 8.8 ± 0.3 m) and 171Ho (t1/2 = 55 ± 3 s), were characterized. Evidence for a new isomer of 3.0 m 168Hog, 168Hom (t1/2 = 132 ± 4 s) which decays by isomeric transition (IT) is presented. Beta particle endpoint energies were determined for the decay of 168Hog, 169Dy, 171Ho, and 174Er, the resulting Qβ-values are: 2.93 ± 0.03, 3.2 ± 0.3, 3.2 ± 0.6, and 1.8 ± 0.2 MeV, respectively. These values were compared with values calculated using recent atomic mass formulae. Comparisons of various target/ion source geometries used in the OASIS mass separator facility for these multinucleon transfer reactions were performed. 73 refs., 40 figs., 11 tabs

  1. Gamma and electron spectroscopy of transfermium isotopes at Dubna: Results and plans

    A Yeremin; O Malyshev; A Popeko; A Lopez-Martens; K Hauschild; O Dorvaux; S Saro; D Pantelica; S Mullin

    2010-07-01

    Detailed spectroscopic information of excited nuclear states in deformed transfermium nuclei is scarce. Most of the information available today has been obtained from investigations of fine-structure -decay. Although decay gives access to hindrance factors and lifetimes which are strongly correlated to shell/subshell closures and the presence of isomers, only the combined use of and conversion electron spectroscopy allows the precise determination of excitation energy, spin and parity of nuclear levels. In the years 2004–2009 using the GABRIELA set-up [Hauschild et al, Nucl. Instrum. Methods A560, 388 (2006)] at the focal plane of VASSILISSA separator [Malyshev et al, Nucl. Instrum. Methods A440, 86 (2000); A516, 529 (2004)] experiments with the aim of and electron spectroscopy of the isotopes from Fm to Lr, formed by complete fusion reactions with accelerated heavy ions were performed. In the following, the pre- liminary results of decay studies using - and - coincidences at the focal plane of the VASSILISSA recoil separator are presented. Accumulated experience allowed us to perform ion optical calculations and to design the new experimental set-up, which will collect the base and best parameters of the existing separators and complex detector systems used at the focal planes of these installations. In the near future it is planned to study neutron-rich isotopes of the Rf–Sg in the `hot’ fusion reactions with 22Ne incident projectiles and 242Pu, 243Am and 248Cm targets.

  2. Fast neutron capture in actinide isotopes: recent results from Karlsruhe

    Capture gamma-ray spectra of 241Am, 240Pu, 242Pu 238U and 197Au were calculated in the framework of the spherical optical model and the statistical model. These spectra were used to correct experimental data for the capture cross sections of 240242Pu and 241Am from relative measurements using a Moxon Rae-detector with graphite converter and 197Au as well as 238U as standards. This correction is required to take into account that the detector efficiency is not exactly proportional to gamma-ray energy. The resulting correction factors proved to be negligible for measurements relative to 238U, whereas they are approx. 3% if gold is used as a standard. The capture cross section of 243Am has been measured in the energy range 10 to 250 keV using kinematically collimated neutrons from the 7Li(p,n) and T(p,n) reaction. The samples are positioned at flight paths of 5 to 7 cm and gold was used as a standard. Capture events were detected by two Moxon-Rae detectors with graphite and bismuth-graphite converters shielded by 0.5 to 2 cm of lead. Fission events were detected by a NE213 liquid scintillator. The present status of the experiment and some preliminary results will be presented

  3. New isotope {sup 265}Bh

    Gan, Z.G.; Guo, J.S.; Wu, X.L.; Qin, Z.; Fan, H.M.; Lei, X.G.; Liu, H.Y.; Guo, B.; Xu, H.G.; Chen, R.F.; Dong, C.F.; Zhang, F.M.; Wang, H.L.; Xie, C.Y.; Feng, Z.Q.; Zhen, Y.; Song, L.T.; Luo, P.; Xu, H.S.; Zhou, X.H. [Institute of Modern Physics, Chinese Academy of Sciences, 730000, Lanzhou (China); Jin, G.M.; Ren, Zhongzhou

    2004-06-01

    A new isotope {sup 265}Bh was produced and identified at the Sector Focus Cyclotron of the Heavy Ion Research Facility in Lanzhou. This experiment was performed via the reaction of an {sup 243}Am target with 168 MeV {sup 26}Mg ions. Identification was made by observation of correlated {alpha} -particle decays between the new isotope {sup 265}Bh and its {sup 261}Db and {sup 257}Lr daughter nuclei using a set of rotating-wheels system. A total of 8 correlated decay events of {sup 265}Bh and 4 decay events of {sup 264}Bh were observed. {sup 265}Bh decays with a 0.94 {sub -0.31}{sup +} {sup 0.70} s half-life by emission of {alpha}-particles with an average energy of 9.24 {+-}0.05 MeV. The half-life and {alpha} decay energy of {sup 265}Bh from this experiment are in agreement with theoretical predictions. (orig.)

  4. Enumeration of Microbial Populations in Radioactive Environments by Epifluorescence Microscopy

    Epifluorescence microscopy was utilized to enumerate halophilic bacterial populations in two studies involving inoculated, actual radioactive waste/brine mixtures and pure brine solutions. The studies include an initial set of experiments designed to elucidate potential transformations of actinide-containing wastes under salt-repository conditions, including microbially mediated changes. The first study included periodic enumeration of bacterial populations of a mixed inoculum initially added to a collection of test containers. The contents of the test containers are the different types of actual radioactive waste that could potentially be stored in nuclear waste repositories in a salt environment. The transuranic waste was generated from materials used in actinide laboratory research. The results show that cell numbers decreased with time. Sorption of the bacteria to solid surfaces in the test system is discussed as a possible mechanism for the decrease in cell numbers. The second study was designed to determine radiological and/or chemical effects of 239Pu, 243Am, 237Np, 232Th and 238U on the growth of pure and mixed anaerobic, denitrifying bacterial cultures in brine media. Pu, Am, and Np isotopes at concentrations of -5M, -6M and -4M respectively, and Th and U isotopes -3M were tested in these media. The results indicate that high actinide concentration affected both the bacterial growth rate and morphology. However, relatively minor effects from Am were observed at all tested concentrations with the pure culture

  5. Characterization of strong 241Am sources

    Gamma ray spectra of strong 241Am sources may reveal information about the source composition as there may be other radioactive nuclides such as progeny and radioactive impurities present. In this work the possibility to use gamma spectrometry to identify inherent signatures in 241Am sources in order to differentiate sources from each other, is investigated. The studied signatures are age, i.e. time passed since last chemical separation, and presence of impurities. The spectra of some sources show a number of Doppler broadened peaks in the spectrum which indicate the presence of nuclear reactions on light elements within the sources. The results show that the investigated sources can be differentiated between by age and/or presence of impurities. These spectral features would be useful information in a national nuclear forensics library (NNFL) in cases when the visual information on the source, e.g. the source number, is unavailable. - Highlights: • Age and impurities can be used as a signature for 241Am sources. • Nuclear reactions take place in sources with low Z impurities. • Some sources contain 243Am as an impurity

  6. Measurement of fission cross-section of actinides at n_TOF for advanced nuclear reactors

    Calviani, Marco; Montagnoli, G; Mastinu, P

    2009-01-01

    The subject of this thesis is the determination of high accuracy neutron-induced fission cross-sections of various isotopes - all of which radioactive - of interest for emerging nuclear technologies. The measurements had been performed at the CERN neutron time-of-flight facility n TOF. In particular, in this work, fission cross-sections on 233U, the main fissile isotope of the Th/U fuel cycle, and on the minor actinides 241Am, 243Am and 245Cm have been analyzed. Data on these isotopes are requested for the feasibility study of innovative nuclear systems (ADS and Generation IV reactors) currently being considered for energy production and radioactive waste transmutation. The measurements have been performed with a high performance Fast Ionization Chamber (FIC), in conjunction with an innovative data acquisition system based on Flash-ADCs. The first step in the analysis has been the reconstruction of the digitized signals, in order to extract the information required for the discrimination between fission fragm...

  7. Identification of the new isotope 107265Bh by α correlated decay chains

    The experimental set-up, methods and results on the synthesis and identification of the new isotope 107265Bh are presented. The new isotope was produced by the complete fusion-evaporation reaction of 243Am with 135 MeV 26Mg bombardment at the Sector Focus Cyclotron of Heavy Ion Research Facility Lanzhou. The reaction products were transported and collected using helium-jet technique and a set of rotating wheel system. the identification of the new isotope was made by observing of correlated α-particle decays chain between the new isotope 265Bh and its 261Db and 257Lr daughters. A total of 8 correlated decay events of 265Bh and 4 decay events of 264Bh were observed. The new nuclide 265Bh has a half-life of 0.94-0.31+0.70s and decays by alpha-particle emission with decay energy of Eα=(9.24 ± 0.05) MeV. The half-life and α decay energy of 265Bh from this experiment are consistent with theoretical predictions. (authors)

  8. Review and Assessment of Neutron Cross Section and Nubar Covariances for Advanced Reactor Systems

    Maslov,V.M.; Oblozinsky, P.; Herman, M.

    2008-12-01

    In January 2007, the National Nuclear Data Center (NNDC) produced a set of preliminary neutron covariance data for the international project 'Nuclear Data Needs for Advanced Reactor Systems'. The project was sponsored by the OECD Nuclear Energy Agency (NEA), Paris, under the Subgroup 26 of the International Working Party on Evaluation Cooperation (WPEC). These preliminary covariances are described in two recent BNL reports. The NNDC used a simplified version of the method developed by BNL and LANL that combines the recent Atlas of Neutron Resonances, the nuclear reaction model code EMPIRE and the Bayesian code KALMAN with the experimental data used as guidance. There are numerous issues involved in these estimates of covariances and it was decided to perform an independent review and assessment of these results so that better covariances can be produced for the revised version in future. Reviewed and assessed are uncertainties for fission, capture, elastic scattering, inelastic scattering and (n,2n) cross sections as well as prompt nubars for 15 minor actinides ({sup 233,234,236}U, {sup 237}Np, {sup 238,240,241,242}Pu, {sup 241,242m,243}Am and {sup 242,243,244,245}Cm) and 4 major actinides ({sup 232}Th, {sup 235,238}U and {sup 239}Pu). We examined available evaluations, performed comparison with experimental data, taken into account uncertainties in model parameterization and made use state-of-the-art nuclear reaction theory to produce the uncertainty assessment.

  9. Results of the Excreta Bioassay Quality Control Program for April 1, 2009 through March 31, 2010

    Antonio, Cheryl L.

    2012-07-19

    A total of 58 urine samples and 10 fecal samples were submitted during the report period (April 1, 2009 through March 31, 2010) to General Engineering Laboratories, South Carolina by the Hanford Internal Dosimetry Program (IDP) to check the accuracy, precision, and detection levels of their analyses. Urine analyses for Sr, 238Pu, 239Pu, 241Am, 243Am 235U, 238U, elemental uranium and fecal analyses for 241Am, 238Pu and 239Pu were tested this year as well as four tissue samples for 238Pu, 239Pu, 241Am and 241Pu. The number of QC urine samples submitted during the report period represented 1.3% of the total samples submitted. In addition to the samples provided by IDP, GEL was also required to conduct their own QC program, and submit the results of analyses to IDP. About 33% of the analyses processed by GEL during the third year of this contract were quality control samples. GEL tested the performance of 21 radioisotopes, all of which met or exceeded the specifications in the Statement of Work within statistical uncertainty (Table 4).

  10. Results of The Excreta Bioassay Quality Control Program For April 1, 2010 Through March 31, 2011

    Antonio, Cheryl L.

    2012-07-19

    A total of 76 urine samples and 10 spiked fecal samples were submitted during the report period (April 1, 2010 through March 31, 2011) to GEL Laboratories, LLC in South Carolina by the Hanford Internal Dosimetry Program (IDP) to check the accuracy, precision, and detection levels of their analyses. Urine analyses for 14C, Sr, for 238Pu, 239Pu, 241Am, 243Am, 235U, 238U, 238U-mass and fecal analyses for 241Am, 238Pu and 239Pu were tested this year. The number of QC urine samples submitted during the report period represented 1.1% of the total samples submitted. In addition to the samples provided by IDP, GEL was also required to conduct their own QC program, and submit the results of analyses to IDP. About 31% of the analyses processed by GEL during the first year of contract 112512 were quality control samples. GEL tested the performance of 23 radioisotopes, all of which met or exceeded the specifications in the Statement of Work within statistical uncertainty except the slightly elevated relative bias for 243,244Cm (Table 4).

  11. Isotope ratio analysis of actinides, fission products, and geolocators by high-efficiency multi-collector thermal ionization mass spectrometry

    A ThermoFisher 'Triton' multi-collector thermal ionization mass spectrometer (MC-TIMS) was evaluated for trace and ultra-trace level isotoperatioanalysis of actinides (uranium, plutonium, and americium), fission products and geolocators (strontium, cesium, and neodymium). Total efficiencies (atoms loaded to ions detected) of up to 0.5-2% for U, Pu, and Am, and 1-30% for Sr, Cs, and Nd can be reported employing resin bead load techniques onto flat ribbon Re filaments or resin beads loaded into a millimeter-sized cavity drilled into a Re rod. This results in detection limits of 4 atoms to 105 atoms) for 239-242+244Pu, 233+236U, 241-243Am, 89,90Sr, and 134,135,137Cs, and (le) 1 pg for natural Nd isotopes (limited by the chemical processing blank) using a secondary electron multiplier (SEM) or multiple-ion counters (MICs). Relative standard deviations (RSD) as small as 0.1% and abundance sensitivities of 1 x 106 or better using a SEM are reported here. Precisions of RSD ∼ 0.01-0.001% using a multi-collector Faraday cup array can be achieved at sub-nanogram concentrations for strontium and neodymium and are suitable to gain crucial geolocation information. The analytical protocols reported herein are of particular value for nuclear forensic and nuclear safeguard applications.

  12. Behavior of actinides in the Integral Fast Reactor fuel cycle

    Courtney, J.C. [Louisiana State Univ., Baton Rouge, LA (United States). Nuclear Science Center; Lineberry, M.J. [Argonne National Lab., Idaho Falls, ID (United States). Technology Development Div.

    1994-06-01

    The Integral Fast Reactor (IFR) under development by Argonne National Laboratory uses metallic fuels instead of ceramics. This allows electrorefining of spent fuels and presents opportunities for recycling minor actinide elements. Four minor actinides ({sup 237}Np, {sup 240}Pu, {sup 241}Am, and {sup 243}Am) determine the waste storage requirements of spent fuel from all types of fission reactors. These nuclides behave the same as uranium and other plutonium isotopes in electrorefining, so they can be recycled back to the reactor without elaborate chemical processing. An experiment has been designed to demonstrate the effectiveness of the high-energy neutron spectra of the IFR in consuming these four nuclides and plutonium. Eighteen sets of seven actinide and five light metal targets have been selected for ten day exposure in the Experimental Breeder Reactor-2 which serves as a prototype of the IFR. Post-irradiation analyses of the exposed targets by gamma, alpha, and mass spectroscopy are used to determine nuclear reaction-rates and neutron spectra. These experimental data increase the authors` confidence in their ability to predict reaction rates in candidate IFR designs using a variety of neutron transport and diffusion programs.

  13. Investigation of the nuclear data on the neutron beam of the IBR-30 and IBR-2 reactors

    Methodical aspects and results of the measurements, conducted on reactors IBR-30 and IBR-2 are presented. Measurements of the multiplicity spectra of gamma-quanta from the neutron capture reaction on the isotopes 48Ti, 113,115In, 117Sn, 127J, 149Sm, 165Ho, 175Lu, 177Hf, 178Hf, 185Re, 187Re, and 232Th have been done. These spectra were used for determination of the capture cross-section and according resonance parameters in the fission of 235U, 239Pu. The measurements were performed of resonance spins of isotopes 113,115In, 117Sn, 185,187Re, and 235U by the low-lying level population method in the thermal neutron energy area. The transmission and self-indication functions of filter samples 232Th, 237Np, and 238U were measured with different temperatures for determination the neutron cross-sections in the neutron energy range from 1 eV to 100 keV. The fission cross-section measurements of the minor actinides 234U, 237Np, and 243Am by the neutrons with energy below the fission barrier were carried out. The measurements of total yields and decay curve of the delayed neutrons from fission of 233,235U, 237Np by thermal and cold neutrons were performed

  14. Results of The Excreta Bioassay Quality Control Program For April 1, 2008 through March 31, 2009

    Antonio, Cheryl L.

    2010-06-01

    A total of 62 urine samples and 6 spiked fecal samples were submitted during the report period (April 1, 2008 through March 31, 2009) to General Engineering Laboratories, South Carolina by the Hanford Internal Dosimetry Program (IDP) to check the accuracy, precision, and detection levels of their analyses. Urine analyses for Sr, 238Pu, 239Pu, 241Am, 243Am 235U, 238U, elemental uranium and fecal analyses for 241Am, 238Pu and 239Pu were tested this year. The number of QC urine samples submitted during the report period represented 1.3% of the total samples submitted. In addition to the samples provided by IDP, GEL was also required to conduct their own QC program, and submit the results of analyses to IDP. About 34% of the analyses processed by GEL during the third year of this contract were quality control samples. GEL tested the performance of 21 radioisotopes, all of which met or exceeded the specifications in the Statement of Work within statistical uncertainty. IDP concluded that GEL was performing well for all analyses tested, and concerns identified earlier were satisfactorily resolved (see section on Follow-up on Concerns During the Fourth Contract Year).

  15. EMP Attachment 1 DOE-SC PNNL Site Sampling and Analysis Plan

    Meier, Kirsten M.

    2011-11-10

    This Sampling and Analysis Plan (SAP) is written for the radiological environmental air surveillance program for the DOE-SC PNNL Site, Richland Washington. It provides the requirements for planning sampling events, and the requirements imposed on the analytical laboratory analyzing the air samples. The actual air sampling process is in procedure EPRP-AIR-029. The rationale for analyte selection, media, and sampling site location has been vetted through the data quality objectives (DQO) process (Barnett et al. 2010). The results from the DQO process have been reviewed and approved by the Washington State Department of Health. The DQO process (Barnett et al. 2010) identified seven specific radionuclides for analysis along with the need for gross alpha and gross beta radiological analyses. The analytes are {sup 241}Am, {sup 243}Am, {sup 244}Cm, {sup 60}Co, {sup 238}Pu, {sup 239}Pu, and {sup 233}U. The report also determined that air samples for particulates are the only sample matrix required for the monitoring program. These samples are collected on 47-mm glass-fiber filters.

  16. Safety procedures for the electron spectroscopy of actinides at the ALS

    This is an addendum to the ALS Experimental Safety Form Renewal for the continuation of actinide microspot experiments on beamlines 7.0. There are several modifications to the previously approved. procedures. There is an increase in the amount of allowable material of the low activity isotopes 238U, 237Np, 242Pu, and 248Cm. There is also the addition of 99Tc and the activity isotopes 232Th and 243Am to the list of permissible sample materials. All of the materials are alpha-emitters with negligible gamma fields with the exception of 99Tc which is a beta-emitter. There is a series of new experiments that requires the use of a crystal cleaver in the preparation chamber of the ultraESCA end station. The beamline 7.0 ultraESCA endstation has been suitably modified to permit the safe cleave of YUPd alloy rectangular ingots. AR of the sample materials are solids. The exact nature and composition of the samples are delineated in the sample preparation section that follows. A corresponding Radiological Work Authorization (RWA) must be issued for this work at ALS since the material amounts exceed those in the Low Activity Source (LAS) guidelines in Table I and those in the Values for Exemption of Sealed Source Inventory in Table II. The preliminary date for the next run of these sample materials has been tentatively scheduled in early February 1996 and this will be with the uranium cleave alloys, not the transuranic materials

  17. Behavior of actinides in the Integral Fast Reactor fuel cycle

    The Integral Fast Reactor (IFR) under development by Argonne National Laboratory uses metallic fuels instead of ceramics. This allows electrorefining of spent fuels and presents opportunities for recycling minor actinide elements. Four minor actinides (237Np, 240Pu, 241Am, and 243Am) determine the waste storage requirements of spent fuel from all types of fission reactors. These nuclides behave the same as uranium and other plutonium isotopes in electrorefining, so they can be recycled back to the reactor without elaborate chemical processing. An experiment has been designed to demonstrate the effectiveness of the high-energy neutron spectra of the IFR in consuming these four nuclides and plutonium. Eighteen sets of seven actinide and five light metal targets have been selected for ten day exposure in the Experimental Breeder Reactor-2 which serves as a prototype of the IFR. Post-irradiation analyses of the exposed targets by gamma, alpha, and mass spectroscopy are used to determine nuclear reaction-rates and neutron spectra. These experimental data increase the authors' confidence in their ability to predict reaction rates in candidate IFR designs using a variety of neutron transport and diffusion programs

  18. VERTICAL MIGRATION OF RADIONUCLIDES IN THE VICINITY OF THE CHERNOBYL CONFINEMENT SHELTER

    Farfan, E.; Jannik, T.; Marra, J.

    2011-10-01

    Studies on vertical migration of Chernobyl-origin radionuclides in the 5-km zone of the Chernobyl Nuclear Power Plant (ChNPP) in the area of the Red Forest experimental site were completed. Measurements were made by gamma spectrometric methods using high purity germanium (HPGe) detectors with beryllium windows. Alpha-emitting isotopes of plutonium were determined by the measurement of the x-rays from their uranium progeny. The presence of {sup 60}Co, {sup 134,137}Cs, {sup 154,155}Eu, and {sup 241}Am in all soil layers down to a depth of 30 cm was observed. The presence of {sup 137}Cs and {sup 241}Am were noted in the area containing automorphous soils to a depth of 60 cm. In addition, the upper soil layers at the test site were found to contain {sup 243}Am and {sup 243}Cm. Over the past ten years, the {sup 241}Am/{sup 137}Cs ratio in soil at the experimental site has increased by a factor of 3.4, nearly twice as much as would be predicted based solely on radioactive decay. This may be due to 'fresh' fallout emanating from the ChNPP Confinement Shelter.

  19. Analysis of high burnup spent nuclear fuel by ICP-MS

    Inductively coupled plasma mass spectrometry (ICP-MS) as the primary tool for determining concentrations of a suite of nuclides in samples excised from high-burnup spent nuclear fuel rods taken from light water nuclear reactors. The complete analysis included the determination of 95Mo, 99Tc, 101Ru, 103Rh, 109Ag, 137Cs, 143Nd, 145Nd, 148Nd, 147Sm, 149Sm, 150Sm, 151Sm, 152Sm, 151Eu, 153Eu, 155Eu, 155Gd, 237Np, 234U, 235U, 236U, 238U, 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, 241Am, 242mAm, and 243Am. The isotopic composition of fissiogenic lanthanide elements was determined using high-performance liquid chromatography (HPLC) with ICP-MS detection. These analytical results allow the determination of fuel burn-up based on 148Nd, Pu, and U content, as well as provide input for storage and disposal criticality calculations. Results show that ICP-MS along with HPLC-ICP-MS are suitable of performing routine determinations of most of these nuclides, with an uncertainty of ±10% at the 95% confidence level. (author)

  20. Elemental groups separation for high-level waste partitioning using a novel silica-based CMPO extraction-resin

    To facilitate the management of high-level liquid waste (HLLW) and minimize its long-term radiological risk in geologic disposal, we have proposed an advanced partitioning process by extraction chromatography using a minimal organic solvent and compact equipment to separate long-lived minor actinides (MA) and specific fission products (FP) such as Zr and Mo from nitrate acidic HLLW solution. The process consists of two separation columns packed with CMPO (octyl(phenyl)-N, N-diisobutylcarbamoylmethylphosphine oxide) extraction-resin for elemental groups separation and R-BTP (2,6-bis-(5,6-dialkyl-1,2,4-triazine-3-yl)-pyridine) extraction-resin for the isolation of MA from lanthanides (Ln), respectively. Several novel silica-based extraction resins have been prepared by impregnating CMPO or R-BTP into a macroreticular styrene- divinylbenzene copolymer which is immobilized in porous silica particles with a diameter of 50 μm (SiO2-P). In this work, adsorption and elution behavior of typical FP elements from nitric acid solution onto the CMPO extraction-resin was investigated. Separation experiments for simulated HLLW solutions containing a trace amount of 243Am(III) and macro amounts of typical FP elements were carried out by column chromatography. It was found that the elements in the simulated HLLW were successfully separated to the following there groups: Cs-Sr-Rh-Ru, Pd-Ln-Am and Zr-Mo. (author)

  1. Group neutron fission and radiative-capture cross-sections for transactinides

    A comparison is made between evaluations of radiative-capture and fission cross-sections for the isotopes 236U, 237Np, 238Pu, 241Am, 243Am, 242Cm and 244Cm, and group cross-sections for use in fast-reactor calculations are recommended. Group cross-sections obtained from the HEDL graphical data (evaluation for ENDF/B-V) are shown for 234U, 236Pu, 237Pu, 242Pu, 244Pu, sup(242m)Am, 241Cm, 243Cm and 248Cm. Group cross-sections for 32 isotopes from the ENDL-76 library files are also given. In choosing recommended cross-sections, account was taken of the extent of agreement with experimental data where these are available, the extent to which the cross-sections are documented and the extent to which they have been calculated from a theoretical model. The reliability of evaluations is discussed. An attempt is made to evaluate the error in single-group cross-sections averaged over a typical fast-reactor spectrum. Conclusions are drawn from a study of the literature on the current status of experimental and theoretical research on transactinide cross-sections, and from the spread of the different evaluation data. Finally, the situation with respect to the integral experiments which can be used for correcting transactinide cross-sections is discussed. (author)

  2. ANSI/ANS-8.15-1981(R87): Nuclear criticality control of special actinide elements

    The American National Standard, open-quotes Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactotorsclose quotes American National Standards Institute/American Nuclear Society (ANSI/ANS)-8.1-1983(R88) provides guidance for the nuclides 233U, 235U, and 239Pu. These three nuclides are of primary interest in out-of-reactor criticality safety since they are the most commonly encountered in the vast majority of operations. However, some operations can involve nuclides other than 233U, 235U, and 239Pu in sufficient quantities that their effect on criticality safety could be of concern. ANSI/ANS-8.15-1981(R87) open-quotes Nuclear Criticality Control of Special Actinide Elements,close quotes provides guidance for 15 such nuclides. The standard was approved for use on November 9, 1981. When it received its first 5-yr review, no changes were made, and it was reaffirmed effective October 30, 1987. The standard was again reviewed and reaffirmed without changes in December 1995. The next 5-yr review of the standard is due in December 2000. The affected nuclides are 237Np, 238Pu, 240Pu, 242Pu, 241Am, 243Am, 244Cm, 239Pu, 241Pu, 242mAm, 243Cm, 245Cm, 247Cm, 249Cf, and 251Cf

  3. Annual progress report on nuclear data 1989. Central Bureau for nuclear measurements

    In 1989 the efforts for the improvement of the set of standard neutron cross sections and other quantities selected within the INDC/NEANDC Standards File continued. In particular a detailed study of the nuclear mass and charge distribution of the cold and near cold fission of 252Cf yielded understanding of cold mass rearrangements in nuclei. Accuracy of alpha-particle emission probabilities for major transitions in the decay of 236Pu, 239Pu and 243Am was improved to better than 0.5%. In the field of nuclear data for fission technology work was concentrated on European requests in the NEA High Priority Request List. The number of neutrons emitted per neutron absorbed, was obtained for 235U between 2 and 100 meV neutron energy. Using the weighting function determined at CBNM for neutron capture detectors, a new value was obtained for the neutron width of the 1.15 keV resonance in 56FeΓn = (62.9 ± 2.1) meV. In the field of nuclear data for fusion technology, measurements continued aiming at an improvement of relevant data for neutron transport calculations in the blanket and for prediction of gas production. The radionuclide metrology subproject follows three lines: determination of decay-scheme data, preparation of special standards and the improvement of measurement techniques including international comparisons

  4. Determination of Self - absorption Corrections Factor for Radioactivity Measurement of Seawater and Plankton Samples by Gross α/β Counter

    In environmental survey, gross alpha/beta activity is one of the parameters to be determined and used to decide whether further radiological analyses are necessary. To obtain correct results, samples shall be counted under the same conditions (geometric setup, chemical composition, density). If not possible, the self absorption corrections factor was necessary. In this study, sea water and plankton samples were prepared by coprecipitation and filtration, respectively. The standards used to determine the self-absorption corrections factor were prepared by adding 243Am and 90Sr, respectively for standard gross alpha and gross beta, to distilled water and varying the amount of carriers to increase the weight of final precipitates and filtrates. The range of weight obtained was 20 to 75 mg. The self-absorption corrections factor was calculated using the following equation. Fa = Ex/E0 where Fa is the absorption corrections factor, Ex is the mean efficiency of the different points of the curve and E0 is the mean efficiency of the first point of the curve. The mass thickness of studied range have effect on the counting of gross alpha/beta in plankton samples and gross alpha in seawater samples and caused no effect of gross beta counting in seawater samples.

  5. Radiation instrumentation: radiological chemistry

    Program efforts were concentrated in the following areas: development of low-level radiochemical laboratory techniques, in situ monitoring techniques, and activation analysis technology. Four different techniques were evaluated for borehole analysis of uranium and thorium ores. These involved the detection of fission product photons after 252Cf activation, the detection of low-energy gamma rays, the direct measurement of the 1001 keV photon from /sup 242m/Pa, a 238U daughter, and isotopic excitation x-ray fluorescence spectroscopy. X-ray fluorescence spectroscopy and detection of uranium daughter photons allowed 0.01% uranium to be detected. X-ray spectrometry of rare earth elements following activation analysis also allowed better elemental detection sensitivities to be obtained than did the detection of high-energy photons identified with a Ge(Li) detector in typical instrumental neutron activation analysis. An activation analysis facility is under development utilizing 252Cf in a 235U-fueled subcritical assembly. This assembly will be used to develop cyclic activation analysis techniques for some 65 elements in environmental matrices with sensitivities varying from parts per million to parts per billion. A study was initiated to identify instrumentation required for the measurement of transuranium elements associated with power reactor fuels. Transuranium isotopes, 237Pu, 238Pu, 239Pu, 241Am, 243Am, and 244Cm can be identified through low energy photons or x-rays emitted following alpha emission with planar intrinsic Ge detectors

  6. Sequential isotopic determination of plutonium, thorium, americium and uranium in the air filter and drinking water samples around the WIPP site

    The simultaneous determination of actinides in air filter and water samples around the WIPP site have been demonstrated. The analytical method is based on the selective separation and purification by anion exchange and Eichrome-TEVA, TRU and DGA-resin followed by determination of actinides by alpha spectrometry. Counting sources for alpha spectrometric measurements were prepared by microcoprecipitation on neodymium fluoride (NdF3). Radiochemical yields were determined using 242Pu, 229Th, 243Am and 232U as tracers. The validation of the method is performed through the analysis of reference materials or participating in laboratory intercomparison programs. The plutonium concentrations in aerosols varied seasonally, being highest in spring and summer due to the spring-time enhanced wind-storm transportation of radioactive aerosols from the stratosphere to the troposphere. The 238Pu/239+240Pu activity ratio in the aerosol samples is typically close to that of global fallout from historic above-ground nuclear weapons testing. The results presented here indicate that the source of plutonium in the WIPP environment results mainly from global nuclear fallout and there is no evidence of increases in radiological contaminants in the region that could be attributed to releases from the WIPP. (author)

  7. Characterization of actinide physics specimens for the US/UK joint experiment in the Dounreay Prototype Fast Reactor

    The United States and the United Kingdom are engaged in a joint research program in which samples of the higher actinides are irradiated in the Dounreay Prototype Fast Reactor in Scotland. The purpose of the porogram is (1) to study the materials behavior of selected higher actinide fuels and (2) to determine the integral cross sections of a wide variety of the higher actinide isotopes. Samples of the actinides are incorporated in fuel pins inserted in the core. For the fuel study, the actinides selected are 241Am and 244Cm in the form of Am2O3, Cm2O3, and Am6Cm(RE)7O21, where (RE) represents a mixture of lanthanides. For the cross-section determinations, the samples are milligram quantities of actinide oxides of 248Cm, 246Cm, 244Cm, 243Cm, 243Am, 241Am, 244Pu, 242Pu, 241Pu, 240Pu, 239Pu, 238Pu, 237Np, 238U, 236U, 235U, 234U, 233U, 232Th, 230Th, and 231Pa encapsulated in vanadium. Coincident with the irradiations, neutron flux and energy spectral measurements are made with vanadium-encapsulated dosimeter materials located within the same fuel pins

  8. Post irradiation examination of irradiated americium oxide and uranium dioxide in magnesium aluminate spinel

    To study MgAl2O4 spinel as inert matrix material for the transmutation of minor actinides, two capsules were irradiated at the high flux reactor in Petten, containing 12.5 wt% micro-dispersed 241AmOx in spinel and 25 wt% micro-dispersed enriched UO2 in spinel. During irradiation, the initially present 241Am was converted for 99.8% to fission products (50%), plutonium (30%), curium (16%) and 243Am (4%). The UO2 spinel target experienced a burn-up of 32% fission per initial metal atom. The post irradiation examination of the AmOx inert matrix target showed swelling of 27 vol.%, and a gas release of 48% for He and 16% for Xe and Kr. The UO2 inert matrix target also showed a large volumetric swelling of 11%, directed mainly radially. Ceramography on the UO2 inert matrix target revealed a complete restructuring of the spinel grains upon irradiation and the absence of porosity, suggesting that amorphisation is the main cause of the swelling

  9. Post irradiation examination of irradiated americium oxide and uranium dioxide in magnesium aluminate spinel

    Klaassen, F. C.; Bakker, K.; Schram, R. P. C.; Klein Meulekamp, R.; Conrad, R.; Somers, J.; Konings, R. J. M.

    2003-06-01

    To study MgAl 2O 4 spinel as inert matrix material for the transmutation of minor actinides, two capsules were irradiated at the high flux reactor in Petten, containing 12.5 wt% micro-dispersed 241AmO x in spinel and 25 wt% micro-dispersed enriched UO 2 in spinel. During irradiation, the initially present 241Am was converted for 99.8% to fission products (50%), plutonium (30%), curium (16%) and 243Am (4%). The UO 2 spinel target experienced a burn-up of 32% fission per initial metal atom. The post irradiation examination of the AmO x inert matrix target showed swelling of 27 vol.%, and a gas release of 48% for He and 16% for Xe and Kr. The UO 2 inert matrix target also showed a large volumetric swelling of 11%, directed mainly radially. Ceramography on the UO 2 inert matrix target revealed a complete restructuring of the spinel grains upon irradiation and the absence of porosity, suggesting that amorphisation is the main cause of the swelling.

  10. Post irradiation examination of irradiated americium oxide and uranium dioxide in magnesium aluminate spinel

    Klaassen, F.C. E-mail: klaassen@nrg-nl.com; Bakker, K.; Schram, R.P.C.; Klein Meulekamp, R.; Conrad, R.; Somers, J.; Konings, R.J.M

    2003-06-01

    To study MgAl{sub 2}O{sub 4} spinel as inert matrix material for the transmutation of minor actinides, two capsules were irradiated at the high flux reactor in Petten, containing 12.5 wt% micro-dispersed {sup 241}AmO{sub x} in spinel and 25 wt% micro-dispersed enriched UO{sub 2} in spinel. During irradiation, the initially present {sup 241}Am was converted for 99.8% to fission products (50%), plutonium (30%), curium (16%) and {sup 243}Am (4%). The UO{sub 2} spinel target experienced a burn-up of 32% fission per initial metal atom. The post irradiation examination of the AmO{sub x} inert matrix target showed swelling of 27 vol.%, and a gas release of 48% for He and 16% for Xe and Kr. The UO{sub 2} inert matrix target also showed a large volumetric swelling of 11%, directed mainly radially. Ceramography on the UO{sub 2} inert matrix target revealed a complete restructuring of the spinel grains upon irradiation and the absence of porosity, suggesting that amorphisation is the main cause of the swelling.

  11. Maximization of burning and/or transmutation (B/T) capacity in coupled spectrum reactor (CSR) by fuel and core adjustment

    A conceptual design of burning and/or transmutation (B/T) reactor, based on a modified conventional 1150 MWe-PWR system, consisted of two core regions for thermal and fast neutrons, respectively, was proposed herein for the treatments of minor actinides (MA). In the outer region 237Np, 241Am, and 243Am burned by thermal neutrons, while in the inner region 244Cm was burned mainly by fast neutrons. The geometry of B/T fuel in the outer region was left the same with that of PWR, while in the inner region the B/T fuel was arranged in a tight-lattice geometry that allowed a higher fuel to coolant volume ratio. The maximization of B/T capacity in CSR were done by, first, increasing the radius of the inner region. Second, reducing the coolant to fuel volume ratio, and third, choosing a suitable B/T fuel type. The result of the calculations showed that the equilibrium of main isotopes in CSR can be achieved after about 5 recycle stages. This study also showed that the CSR can burn and transmute up to 808 kg of MA in a single reactor core effectively and safely. (author)

  12. Synthesis of Heaviest Elements (results and Prospects)

    Oganessian, Yuri

    The formation and decay properties of the heaviest nuclei with Z = 112 - 116 and 118 were studied in the reactions 238U, 242,244Pu, 243Am, 245,248Cm and 249Cf+48Ca. The new nuclides mainly undergo sequential α-decay, which ends with spontaneous fission. The total time of decays ranges from 0.5 ms to about 1 day, depending on the proton and neutron numbers in the synthesized nuclei. The atomic number of the new elements 115 and 113 was confirmed also by an independent radiochemical experiment based on the identification of the neutron-rich isotope 268Db (TSF ≈ 30 h), the final product in the chain of α-decays of the odd-odd parent nucleus 288115. The comparison of the decay properties of 29 new nuclides with Z = 104 - 118 and N = 162 - 177 gives evidence for the decisive influence of the structure of superheavy nuclei on their stability with respect to different modes of radioactive decay. The investigations connected with the search for superheavy elements in Nature (cosmic rays) and prospects of superheavy element research are also presented.

  13. Synthesis of Superheavy Nuclei in 48CA-INDUCED Reactions

    Oganessian, Yu. Ts.; Utyonkov, V. K.; Lobanov, Yu. V.; Abdullin, F. Sh.; Polyakov, A. N.; Sagaidak, R. N.; Shirokovsky, I. V.; Tsyganov, Yu. S.; Voinov, A. A.; Gulbekian, G. G.; Bogomolov, S. L.; Gikal, B. N.; Mezentsev, A. N.; Iliev, S.; Subbotin, V. G.; Sukhov, A. M.; Subotic, K.; Zagrebaev, V. I.; Vostokin, G. K.; Itkis, M. G.; Moody, K. J.; Patin, J. B.; Shaughnessy, D. A.; Stoyer, M. A.; Stoyer, N. J.; Wilk, P. A.; Kenneally, J. M.; Landrum, J. H.; Wild, J. F.; Lougheed, R. W.

    2008-11-01

    Thirty-four new nuclides with Z = 104-116, 118 and N = 161-177 have been synthesized in the complete-fusion reactions of 238U, 237Np, 242,244Pu, 243Am, 245,248Cm, and 249Cf targets with 48Ca beams. The masses of evaporation residues were identified through measurements of the excitation functions of the xn-evaporation channels and from cross bombardments. The decay properties of the new nuclei agree with those of previously known heavy nuclei and with predictions from different theoretical models. A discussion of self-consistent interpretations of all observed decay chains originating from the parent isotopes 282,283112, 282113, 286-289114, 287,288115, 290-293116, and 294118 is presented. Decay energies and lifetimes of the neutron-rich superheavy nuclei as well as their production cross sections indicate a considerable increase in the stability of nuclei with an increasing number of neutrons, which agrees with the predictions of theoretical models concerning the decisive dependence of the structure and radioactive properties of superheavy elements on their proximity to the nuclear shells with N = 184 and Z = 114.

  14. Synthesis, Decay Properties, and Identification of Superheavy Nuclei Produced in 48CA-INDUCED Reactions

    Oganessian, Yu. Ts.; Utyonkov, V. K.; Lobanov, Yu. V.; Abdullin, F. Sh.; Polyakov, A. N.; Sagaidak, R. N.; Shirokovsky, I. V.; Tsyganov, Yu. S.; Voinov, A. A.; Iliev, S.; Subbotin, V. G.; Sukhov, A. M.; Gulbekian, G. G.; Bogomolov, S. L.; Gikal, B. N.; Mezentsev, A. N.; Subotic, K.; Zagrebaev, V. I.; Itkis, M. G.; Moody, K. J.; Henderson, R. A.; Patin, J. B.; Shaughnessy, D. A.; Stoyer, M. A.; Stoyer, N. J.; Wilk, P. A.; Kenneally, J. M.; Landrum, J. H.; Wild, J. F.; Lougheed, R. W.

    2008-04-01

    Thirty-four new nuclides with Z = 104-116, 118 and N = 161-177 have been synthesized in the complete-fusion reactions of 238U, 237Np, 242,244Pu, 243Am, 245,248Cm, and 249Cf targets with 48Ca beams. The masses of evaporation residues were identified through measurements of the excitation functions of the xn-evaporation channels and from cross bombardments. The decay properties of the new nuclei agree with those of previously known heavy nuclei and with predictions from different theoretical models. A discussion of self-consistent interpretations of all observed decay chains originating from the parent isotopes 282,283112, 282113, 286-289114, 287,288115, 290-293116, and 294118 is presented. Decay energies and lifetimes of the neutron-rich superheavy nuclei as well as their production cross sections indicate a considerable increase in the stability of nuclei with the approach to the theoretically predicted nuclear shells with N = 184 and Z = 114.

  15. Nuclear Reactions Used For Superheavy Element Research

    Stoyer, Mark A.

    2008-04-01

    Some of the most fascinating questions about the limits of nuclear stability are confronted in the heaviest nuclei. How many more new elements can be synthesized? What are the nuclear and chemical properties of these exotic nuclei? Does the "Island of Stability" exist and can we ever explore the isotopes inhabiting that nuclear region? This paper will focus on the current experimental research on the synthesis and characterization of superheavy nuclei with Z>112 from the Dubna/Livermore collaboration. Reactions using 48Ca projectiles from the U400 cyclotron and actinide targets (233,238U, 237Np, 242,244Pu, 243Am, 245,248Cm, 249Cf) have been investigated using the Dubna Gas Filled Recoil Separator in Dubna over the last 8 years. In addition, several experiments have been performed to investigate the chemical properties of some of the observed longer-lived isotopes produced in these reactions. Some comments will be made on nuclear reactions used for the production of the heaviest elements. A summary of the current status of the upper end of the chart of nuclides will be presented.

  16. Synthesis and decay properties of the heaviest nuclei

    Oganessian, Yuri

    2006-07-01

    The formation and decay properties of the heaviest nuclei with Z=112-116 and 118 were studied in the reactions 238U, 242,244Pu, 243Am, 245,248Cm and 249Cf + 48Ca. The new nuclides mainly undergo sequential α-decay, which ends with spontaneous fission. The total time of decay ranges from 0.5 ms to ~1 day, depending on the proton and neutron numbers in the synthesized nuclei. The atomic number of the new elements 115 and 113 was confirmed also by an independent radiochemical experiment based on the identification of the neutron-rich isotope 268Db (TSF~30 h), the final product in the chain of α-decays of the odd-odd parent nucleus 288115. The comparison of the decay properties of 29 new nuclides with Z=104-118 and N=162-177 gives evidence of the decisive influence of the structure of superheavy elements on their stability with respect to different modes of radioactive decay. The investigations connected with the search for superheavy elements in Nature and prospects of superheavy element research are also presented. The experiments were carried out at the Flerov Laboratory of Nuclear Reactions (JINR, Dubna) in collaboration with the Analytical and Nuclear Chemistry Division of the Lawrence Livermore National Laboratory (USA).

  17. Analytical performance of radiochemical method for americium determination in urine

    This paper presents an analytical method developed and adapted for separation and analysis of Plutonium (Pu) isotopes and Americium (Am) in urine samples. The proposed method will attend the demand of internal exposure monitoring program for workers involved mainly with dismantling rods and radioactive smoke detectors. In this experimental procedure four steps are involved as preparation of samples, sequential radiochemical separation, preparation of the source for electroplating and quantification by alpha spectrometry. In the first stage of radiochemical separation, plutonium is conventionally isolated employing the anion exchange technique. Americium isolation is achieved sequentially by chromatographic extraction (Tru.spec column) from the load and rinse solutions coming from the anion exchange column. The 243Am tracer is added into the sample as chemical yield monitors and to correct the results improving the precision and accuracy. The mean recovery obtained is 60%, and the detection limit for 24h urine sample is 1.0 mBq L-1 in accordance with the literature. Based in the preliminary results, the method is appropriate to be used in monitoring programme of workers with a potential risk of internal contamination. (author)

  18. Separation and determination of 241Am in urine samples from radiation workers using PC88-A and alpha spectrometry

    Bioassay technique is used for the estimation of actinides present in the body based on their excretion rate through body fluids. For occupational radiation workers urine assay is the preferred method for monitoring of chronic internal exposure. Determination of low concentrations of actinides such as plutonium, americium and uranium at low level of mBq in urine by alpha spectrometry requires pre-concentration of large volumes of urine. This article deals with standardization of analytical method for the determination of 241Am isotope in urine samples using Extraction Chromatography (EC) and 243Am tracer for radiochemical recovery. The method involves oxidation of urine followed by co-precipitation of americium along with calcium phosphate. This precipitate after treatment is further subjected to calcium oxalate co-precipitation. Separation of Am was carried out by EC column prepared by PC88-A (2-ethyl hexyl phosphonic acid 2-ethyl hexyl monoester) adsorbed on microporous resin XAD-7 (PC88A-XAD7). Am-fraction was electro-deposited and activity estimated using tracer recovery by alpha spectrometer. Ten routine urine samples of radiation workers were analyzed and consistent radiochemical recovery was obtained in the range 44-60% with a mean and standard deviation of 51 and 4.7% respectively. (author)

  19. Interaction of radionuclides with geomedia associated with the Waste Isolation Pilot Plant (WIPP) site in New Mexico

    A survey of the potential of geological media from the vicinity of the Waste Isolation Pilot Plant site in Southeastern New Mexico for retardation of radionuclide migration in an aqueous carrier was conducted. The survey included the measurement of sorption coefficients (Kd) for twelve radionuclides between three natural water simulants and ten samples from various geological strata. The nuclides included 137Cs, 85Sr, 131I, 99Tc, 125Sb, 144Ce, 152Eu, 153Gd, 106Ru, 243Am, 244Cm, and 238Pu. The compositions of the simulant solutions were those expected of water in contact with potash minerals or halite deposits in the area and in a typical groundwater found in the Delaware Basin. The geological samples were obtained from potential aquifers above and below the proposed repository horizons and from bedded salt deposits in the repository horizons. In brine solutions, Tc and I were not significantly adsorbed by any of the minerals and Cs and Sr showed minimal adsorption (Kd's 103 and Ru and Sb Kd's varied in the range of 25 to > 103. In the groundwater simulant, Tc and I showed the same behavior, but the Kd's of the other nuclides were generally higher. Some initial parametric studies involving pH, trace organic constituents in the simulant solutions, and radionuclide concentrations were carried out. Significant differences in the observed Kd's can result from varying one or more of these solution parameters

  20. Preparation of actinide specimens for the US/UK joint experiment in the Dounreay Prototype Fast Reactor

    A joint research program involving the United States and the United Kingdom was initiated about four years ago for the purpose of studying the fuel behavior of higher actinides using in-core irradiation in the fast reactor at Dounreay, Scotland. Simultaneously, determination of integral cross sections of a wide variety of higher actinide isotopes (physics specimens) was proposed. Coincidental neutron flux and energy spectral measurements were to be made using vanadium encapsulated dosimetry materials in the immediate region of the fuel pellets and physics samples. The higher actinide samples chosen for the fuel study were 241Am and 244Cm in the forms of Am2O3, Cm2O3, and Am6Cm(RE)7O21, where (RE) represents a mixture of lanthanides. Milligram quantities of actinide oxides of 248Cm, 246Cm, 244Cm, 243Cm, 243Am, 241Am, 244Pu, 242Pu, 241Pu, 240Pu, 239Pu, 238Pu, 237Np, 238U, 236U, 235U, 234U, 233U, 232Th, 230Th, and 231Pa were encapsulated to obtain nuclear cross section and reaction rate data for these materials

  1. Experiments to produce isotopes of superheavy elements with atomic numbers 114-116 in 48Ca ion reactions

    Experiments have been conducted to synthesize isotopes of elements 114-116 in fusion reactions between 48Ca ions and sup(246,248)Cm, sup(243)Am and sup(242)Pu isotopes. Irradiations by 48Ca ions at 267 MeV have been carried out using an internal beam of the cyclotron U-300 with the average current of 48Ca ions 1012 fr/s. As in conformity with the theoretical predictions, the superheavy elements with Z=112-116 must possess higher volatility and the elements with Z=108-111 must be analogs of heavy metals with Z=76-79, upon irradiation from the target by chemical methods fractions of volatile elements, heavy noble gases, sulphides of heavy metals as well as Cf-Fm fraction have been isolated. The obtained samples (80%) have been put in contact with phosphate glasses for detecting spontaneous fission of superheavy elements with the period Tsub(sf) from 2 h. to a year. At the same time a part of the samples (20%) has been placed in an alpha-spectrometer. No unknown spontaneously fissioning and alpha-active radiations have been observed. Upper limits of the production cross sections for superheavy elements in the studied reactions: for spontaneously-fissioning activity sigma35 cm2, for alpha-active isotopes with the period 2h(-34 cm2

  2. Actinide behavior in the Integral Fast Reactor. Final project report

    The Integral Fast Reactor (IFR) under development by Argonne National Laboratory uses metallic fuels instead of ceramics. This allows electrorefining of spent fuels and presents opportunities for recycling minor actinide elements. Four minor actinides (237Np, 240Pu, 241Am, and 243Am) determine the waste storage requirements of spent fuel from all types of fission reactors. These nuclides behave the same as uranium and other plutonium isotopes in electrorefining, so they can be recycled back to the reactor without elaborate chemical processing. An experiment has been designed to demonstrate the effectiveness of the high-energy neutron spectra of the IFR in consuming these four nuclides and weapons grade plutonium. Eighteen sets of seven actinide and five light metal targets have been selected for seven day exposure in the Experimental Breeder Reactor-II which serves as a prototype of the IFR. Post-irradiation analyses of the exposed targets by gamma, alpha, and mass spectroscopy are used to determine nuclear reaction rates and neutron spectra. These experimental data increase the authors confidence in their ability to predict reaction rates in candidate IFR designs using a variety of neutron transport and diffusion programs

  3. Neutron capture and neutron-induced fission experiments on americium isotopes with DANCE

    Neutron capture cross section data on Am isotopes were measured using the Detector for Advanced Neutron Capture Experiments (DANCE) at Los Alamos National Laboratory. The neutron capture cross section was determined for 241Am for neutron energies between thermal and 320 keV. Preliminary results were also obtained for 243Am for neutron energies between 35 eV and 200 keV. The results on concurrent neutron-induced fission and neutron-capture measurements on 242mAm will be presented, where the fission events were actively triggered during the experiments. In these experiments, the Parallel-Plate Avalanche Counter (PPAC) detector that surrounds the target located in the center of the DANCE array was used as a fission-tagging detector to separate (n,γ) from (n,f) events. The first evidence of neutron capture on 242mAm in the resonance region in between 2 and 9 eV of the neutron energy was obtained.

  4. Preparation of novel silica-based R-BTP extraction-resins and their application to trivalent actinides and lanthanides separation

    To separate long-lived minor actinides and specific fission products such as Zr and Mo from nitrate acidic high-level liquid waste, we have been studying an advanced partitioning process by extraction chromatography using a minimal organic solvent and compact equipment. In this work, we have synthesized several new type of nitrogen donor ligands, 2,6-bis-(5,6-dialkyl-1,2,4-triazine-3-yl)-pyridine with different alkyl groups and prepared the novel silica-based extraction-resins by impregnating these ligands into the SiO2-P support with a diameter of 50 μm. The adsorption performance of 243Am(III) and typical fission product Ln(III) from nitrate solution on these extraction-resins was investigated. It was found that the adsorption behavior depends strongly on the alkyl group in R-BTP. nBu-BTP/SiO2-P and nHex-BTP/SiO2-P showed significantly higher adsorbablility and selectivity for Am(III) over Ln(III). The separation factor is about 104 for Am/Ce and near 102 for Am/Eu-Gd, respectively. It is expected that Am(III) can be effectively separated from Ln(III) by extraction chromatography using these novel R-BTP/SiO2-P extraction-resins. (author)

  5. Sensitivity analysis for actinide production and depletion in fast reactors

    In sensitivity analysis of the actinide production and depletion in fast reactors, a mathematical method of calculating sensitivity coefficients is improved and simplified by combining the time-dependent generalized perturbation technique with the eigenvalue method. Numerical calculations show that the eigenvalue method is well applicable in solving the nuclide chain equation and its adjoint equation and the cylic chains in the decay scheme of the actinides can be interpreted by means of complex eigenvalues. The sensitivity coefficients of actinide production and depletion in a 1000 MWe fast reactor are strongly dependent on the type of Pu fuel used, i.e. Pu fuel from BWR or Pu fuel from the blanket of FBR. The sensitivity coefficients due to variations of capture cross sections, σsub(n,2n) of 238U, lambda sub(β) of 241Pu and lambda sub(α) of 242Cm are especially large. Sensitivity analyses for the 1000 MWe fast reactors show that higher priorily should be given to decay constants of 241Pu and 242Cm, capture cross sections of 237Np, 241Am, 243Am and 242Pu, and fission cross sections of 237Np, 242Pu, 241Am and sup(242m)Am. (author)

  6. Plutonium build-up credits for a material test research reactor and influence of cross-section differences on actinide production

    Burnup calculations with SARC system were carried out to analyse the effects of plutonium build-up on criticality of MTR type research reactor PARR-1 using several WIMSD libraries based on evaluated nuclear data files ENDFB-VI.8, JEF-2.2, JEFF-3.1 and JENDL-3.2. For equilibrium core of the reactor, it was found that a net reactivity of more than 3.5 mk is induced due to build-up of plutonium isotopes during depletion. The plutonium credit amounts to 3% of the length of equilibrium cycle. From the analysis of actinide production in the core during burnup, it was observed that in most of the cases, the amounts of actinides obtained using various cross section libraries agree fairly with each other, however, significant differences were observed for 238Pu, 241Pu, 242mAm, 243Am, 242Cm and 244Cm for some libraries. The actinide chain analysis was conducted to investigate the reasons for the observed differences

  7. Plutonium build-up credits for a material test research reactor and influence of cross-section differences on actinide production

    Ahmad, Siraj Islam [Pakistan Institute of Engineering and Applied Sciences, Islamabad-45650 (Pakistan)]. E-mail: sirajisl@yahoo.co.uk; Ahmad, Nasir [Pakistan Institute of Engineering and Applied Sciences, Islamabad-45650 (Pakistan)

    2006-12-15

    Burnup calculations with SARC system were carried out to analyse the effects of plutonium build-up on criticality of MTR type research reactor PARR-1 using several WIMSD libraries based on evaluated nuclear data files ENDFB-VI.8, JEF-2.2, JEFF-3.1 and JENDL-3.2. For equilibrium core of the reactor, it was found that a net reactivity of more than 3.5 mk is induced due to build-up of plutonium isotopes during depletion. The plutonium credit amounts to 3% of the length of equilibrium cycle. From the analysis of actinide production in the core during burnup, it was observed that in most of the cases, the amounts of actinides obtained using various cross section libraries agree fairly with each other, however, significant differences were observed for {sup 238}Pu, {sup 241}Pu, {sup 242m}Am, {sup 243}Am, {sup 242}Cm and {sup 244}Cm for some libraries. The actinide chain analysis was conducted to investigate the reasons for the observed differences.

  8. The urgent requirement for new radioanalytical certified reference materials for nuclear safeguards, forensics, and consequence management

    A multi-agency workshop was held from 25 to 27 August 2009, at the National Institute of Standards and Technology (NIST), to identify and prioritize the development of radioanalytical Certified Reference Materials (CRMs, generally provided by National Metrology Institutes; Standard Reference Materials, a CRM issued by NIST) for field and laboratory nuclear measurement methods to be used to assess the consequences of a domestic or international nuclear event. Without these CRMs, policy makers concerned with detecting proliferation and trafficking of nuclear materials, attribution and retribution following a nuclear event, and public health consequences of a nuclear event would have difficulty making decisions based on analytical data that would stand up to scientific, public, and judicial scrutiny. The workshop concentrated on three areas: post-incident Improvised Nuclear Device (IND) nuclear forensics, safeguard materials characterization, and consequence management for an IND or a Radiological Dispersion Device detonation scenario. The workshop identified specific CRM requirements to fulfill the needs for these three measurement communities. Of highest priority are: (1) isotope dilution mass spectrometry standards, specifically 233U, 236gNp, 244Pu, and 243Am, used for quantitative analysis of the respective elements that are in critically short supply and in urgent need of replenishment and certification; (2) CRMs that are urgently needed for post-detonation debris analysis of actinides and fission fragments, and (3) CRMs used for destructive and nondestructive analyses for safeguards measurements, and radioisotopes of interest in environmental matrices. (author)

  9. Synthesis of heaviest elements (results and prospects)

    The formation and decay properties of the heaviest nuclei with Z = 112 - 116 and 118 were studied in the reactions 238U, 242,244Pu, 243Am, 245,248Cm and 249Cf + 48Ca. The new nuclides mainly undergo sequential α-decay, which ends with spontaneous fission. The total time of decays ranges from 0.5 ms to about 1 day, depending on the proton and neutron numbers in the synthesized nuclei. The atomic number of the new elements 115 and 113 was confirmed also by an independent radiochemical experiment based on the identification of the neutron-rich isotope 268Db (TSF ≈ 30 h), the final product in the chain of α-decays of the odd–odd parent nucleus 288115. The comparison of the decay properties of 29 new nuclides with Z = 104 - 118 and N = 162 - 177 gives evidence for the decisive influence of the structure of superheavy nuclei on their stability with respect to different modes of radioactive decay. The investigations connected with the search for superheavy elements in Nature (cosmic rays) and prospects of superheavy element research are also presented. (author)

  10. Calculations of neutron and proton induced reaction cross sections for actinides in the energy region from 10MeV to 1GeV

    Several nuclear model codes were applied to calculations of nuclear data in the energy region from 10MeV to 1GeV. At energies up to 100MeV the nuclear theory code GNASH was used for nuclear data calculation for neutrons incident for on 238U, 233-236U, 238-242Pu, 237Np, 232Th, 241-243Am and 242-247Cm. At energies from 100MeV to 1GeV the intranuclear cascade exciton model including the fission process was applied to calculations of protons and neutrons with 233U, 235U, 238U, 232Th, 232Pa, 237Np, 238Np, 239Pu, 241Am, 242Am and 242-248Cm. Determination of parameter systematics was a major effort in the present work that was aimed at improving the predictive capability of the models used. An emphasis was placed upon a simultaneous analysis of data for a variety of reaction channels for the nuclei considered, as well as of data that are available for nearby nuclei or for other incident particles. Comparisons with experimental data available on multiple reaction cross sections, isotope yields, fission cross sections, particle multiplicities, secondary particle spectra, and double differential cross sections indicate that the calculations reproduce the trends, and often the details, of the measurements data. (author) 82 refs

  11. Measurement of the fast neutron capture cross section of /sup 238/U relative to /sup 235/U(n,f)

    Fawcett, L.R. Jr.; Poenitz, W.P.; Smith, D.L.

    1979-01-01

    The capture cross section of /sup 238/U was measured using the activation technique and /sup 235/U(n,f) as a reference cross section. Capture events were measured by detection of two prominent ..gamma..-transitions in the decay of the /sup 239/U daughter nuclide, /sup 239/Np, employing a high resolution Ge(Li) detector. The system was calibrated with samples activated in a thermal neutron flux relative to the capture cross section of gold, and with an absolutely calibrated ..cap alpha..-emitter, /sup 243/Am, which decays to /sup 239/Np. Cross section measurements were carried out in the neutron energy range from 30 keV to 3 MeV. Emphasis was on absolute values between 150 keV and 1 MeV where the /sup 238/U(n,..gamma..) cross section and its cross section is small. Background from fission products was found to restrict the accuracy of the measured data at energies > 1.5 MeV.

  12. Neutron capture and neutron-induced fission experiments on americium isotopes with DANCE

    Jandel, Marian [Los Alamos National Laboratory

    2008-01-01

    Neutron capture cross section data on Am isotopes were measured using the Detector for Advanced Neutron Capture Experiments (DANCE) at Los Alamos National Laboratory. The neutron capture cross section was determined for {sup 241}Am for neutron energies between thermal and 320 keV. Preliminary results were also obtained for {sup 243}Am for neutron energies between 35 eV and 200 keV. The results on concurrent neutron-induced fission and neutron-capture measurements on {sup 242m}Am will be presented, where the fission events were actively triggered during the experiments. In these experiments, the Parallel-Plate Avalanche Counter (PPAC) detector that surrounds the target located in the center of the DANCE array was used as a fission-tagging detector to separate (n,{gamma}) from (n,f) events. The first evidence of neutron capture on {sup 242m}Am in the resonance region in between 2 and 9 eV of the neutron energy was obtained.

  13. Determination of the transfer coefficients between oyster's mushrooms and their cultivation media by using of isotopes 239Pu and 241Am

    Mushrooms are unicellular or poly-cellular organisms, which are feed lateral or saprophytic. Mainly their cells have developed cellular sheet and definite form. Poly-cellular mushrooms generate the fibers, called hypes, which make twine, called mycelium, which side as feeding tissue. From mycelium grow fertile body, which have reproductive function. These fertile bodies with their speed and period of grow, as possible bio-indicators of contamination biosphere by heavy metals, present applicable matrix for analysis. In this work we try to find a way of using fungus to clean up soil contaminated with radioactive waste, especially plutonium and americium. The completely natural method, called myco-remediation or fungal remediation, which was successfully used for clean up soil contaminated with petroleum hydrocarbons and other toxic or hazardous waste, is expected to be faster and more cost-effective than other bioremediation techniques. The analyzed radionuclides were determined using by followed algorithm - the Pu was separated by liquid extraction with Aliquat-336 and for the determination of Am was used liquid extraction with TOPO. For the determination of chemical recovery was used tracer 242Pu with activity 5,0.10-2 Bq, respectively 243Am with activity 1.28.10-1 Bq. The samples after separation were precipitated, micro-filtrated and follow measured by α-spectrometer Ortec. (author)

  14. Biological pathways and chemical behavior of plutonium and other actinides in the environment

    The principal long-lived actinide elements that may enter the environment from either U or Pu fuel cycles are Pu, Am, Cm, and Np. Approximately 25% of the alpha activity estimated to be released to the atmosphere from the LMFBR fuel cycle will be contributed by 241Am, 242Cm, and 244Cm. The balance of the alpha activity will come from Pu isotopes. Activities of 242Cm, 244Cm, 241Am, 243Am, and 237Np in waste may exceed concentrations of Pu isotopes in waste after various periods of decay. Thorium and uranium isotopes may also be released by operations of the thorium fuel cycle. Environmental actinides are discussed under the following headings: sources of man-made actinide elements; pathways of exposure; environmental chemistry of actinides; uptake of actinides by plants; distribution of actinides in components of White Oak Lake; entry of actinides into terrestrial food chains; relationship between chemical behavior and uptake of actinides by organisms; and behavior of Pu in freshwater and marine food chains

  15. Interim salt disposition program macrobatch 6 tank 21H qualification monosodium titanate and cesium mass transfer tests

    Savannah River National Laboratory (SRNL) performed experiments on qualification material for use in the Interim Salt Disposition Program (ISDP) Batch 6 processing. This qualification material was a set of six samples from Tank 21H in October 2012. This sample was used as a real waste demonstration of the Actinide Removal Process (ARP) and the Extraction-Scrub-Strip (ESS) tests process. The Tank 21H sample was contacted with a reduced amount (0.2 g/L) of MST and characterized for strontium and actinide removal at 0 and 8 hour time intervals in this salt batch. 237Np and 243Am were both observed to be below detection limits in the source material, and so these results are not reported in this report. The plutonium and uranium samples had decontamination factor (DF) values that were on par or slightly better than we expected from Batch 5. The strontium DF values are slightly lower than expected but still in an acceptable range. The Extraction, Scrub, and Strip (ESS) testing demonstrated cesium removal, stripping and scrubbing within the acceptable range. Overall, the testing indicated that cesium removal is comparable to prior batches at MCU

  16. Measured solubilities and speciations of neptunium, plutonium, and americium in a typical groundwater (J-13) from the Yucca Mountain region

    Solubility and speciation data are important in understanding aqueous radionuclide transport through the geosphere. They define the source term for transport retardation processes such as sorption and colloid formation. Solubility and speciation data are useful in verifying the validity of geochemical codes that are part of predictive transport models. Results are presented from solubility and speciation experiments of 237NpO2+, 239Pu4+, 241Am3+/Nd3+, and 243Am3+ in J-13 groundwater (from the Yucca Mountain region, Nevada, which is being investigated as a potential high-level nuclear waste disposal site) at three different temperatures (25 degree, 60 degree, and 90 degree C) and pH values (5.9, 7.0, and 8.5). The solubility-controlling steady-state solids were identified and the speciation and/or oxidation states present in the supernatant solutions were determined. The neptunium solubility decreased with increasing temperature and pH. Plutonium concentrations decreased with increasing temperature and showed no trend with pH. The americium solutions showed no clear solubility trend with increasing temperature and increasing pH

  17. Experimental and theoretical studies of the yields of residual product nuclei produced in thin Pb and Bi targets irradiated by 40 - 2600 MeV protons

    The Project is aimed at experimental determining and computer-aided theoretical simulating the independent and cumulative yields of residual radioactive product nuclei in high-energy protonirradiated thin targets made of high-isotopic and natural lead (206Pb, 207Pb, 208PB, natPb) and bismuth (209Bi) that are the most probable choice to be the target materials in the acceleratordriven (hybrid) systems (ADS) coupled to a high-current proton accelerator. The yields of residual product nuclei are of great importance when estimating such basic radiation-technology characteristics of the hybrid facility targets as the total target activity, the target 'poisoning', the buildup of long-lived nuclides, the α-activity, the content of low-pressure evaporated nuclides (Hg), the content of the chemically-active nuclides that drastically spoil the corrosion resistance of the facility structure materials, etc. In view of the above, the radioactive product nuclide yields from targets materials were experimentally determined using the ITEP U-10 proton accelerator in 55 measurement runs using the monoisotopic and natural lead (206Pb, 207Pb, 208PB, natPb) and bismuth (209Bi) targets within the proton energy range fractionated minutely, namely at 0.04, 0.07, 0.10, 0.8, 1.2, 1.4, 1.6, and 2.6 GeV to cover the entire range of the internuclear hadron cascading. As a result, 5972 cumulative and independent yields of residual radioactive product nuclei, whose lifetimes range from 8 minutes to 32 years, have been measured. Besides, the cross sections for the 27Al(p,x)24Na and 27Al(p,x)7Be monitor reactions have been measured at the same proton energies together with the 27Al(n,p)27Mg reaction rate that characterizes the neutron background contributions in each experiment. The experimental nuclide yields are determined by the direct γ-spectrometry method. The γ-spectrometer resolution is 1.8 keV in the 1332 keV 60Co γ-line. The experimental γ-spectra are processed by the GENIE2000 code

  18. Influence of complex impurity centres on radiation damage in wide-gap metal oxides

    Lushchik, A.; Lushchik, Ch.; Popov, A. I.; Schwartz, K.; Shablonin, E.; Vasil'chenko, E.

    2016-05-01

    Different mechanisms of radiation damage of wide-gap metal oxides as well as a dual influence of impurity ions on the efficiency of radiation damage have been considered on the example of binary ionic MgO and complex ionic-covalent Lu3Al5O12 single crystals. Particular emphasis has been placed on irradiation with ∼2 GeV heavy ions (197Au, 209Bi, 238U, fluence of 1012 ions/cm2) providing extremely high density of electronic excitations within ion tracks. Besides knock-out mechanism for Frenkel pair formation, the additional mechanism through the collapse of mobile discrete breathers at certain lattice places (e.g., complex impurity centres) leads to the creation of complex defects that involve a large number of host atoms. The experimental manifestations of the radiation creation of intrinsic and impurity antisite defects (Lu|Al or Ce|Al - a heavy ion in a wrong cation site) have been detected in LuAG and LuAG:Ce3+ single crystals. Light doping of LuAG causes a small enhancement of radiation resistance, while pair impurity centres (for instance, Ce|Lu-Ce|Al or Cr3+-Cr3+ in MgO) are formed with a rise of impurity concentration. These complex impurity centres as well as radiation-induced intrinsic antisite defects (Lu|Al strongly interacting with Lu in a regular site) tentatively serve as the places for breathers collapse, thus decreasing the material resistance against dense irradiation.

  19. Production of high charge state ions with the Advanced Electron Cyclotron Resonance ion source at LBNL

    Production of high charge state ions with the Advanced Electron Cyclotron Resonance ion source (AECR) at Lawrence Berkeley National Laboratory (LBNL) has been significantly improved by application of various new techniques. Heating the plasma simultaneously with microwaves of two frequencies (10 and 14 GHz) has increased the production of very high charge state heavy ions. The two-frequency technique provides extra electron cyclotron resonance heating zone as compared to the single-frequency heating and improves the heating of the plasma electrons. Aluminum oxide on the plasma chamber surface improves the production of cold electrons at the chamber surfaces and increases the performance of the AECR. Fully stripped argon ions, > 5 enA, were produced and directly identified by the source charge state analyzing system. High charge state ion beams of bismuth and uranium, such as 209Bi51+ and 238U53+, were produced by the source and accelerated by the 88-Inch Cyclotron to energies above 6 MeV/nucleon for the first time. To further increase the production of high charge state ions to support the nuclear science research programs at the 88-Inch Cyclotron, an upgrade is taking place to increase the AECR magnetic field strengths and mirror ratios to improve the plasma confinement. Conceptual design is underway for a 3rd Generation ECR that uses superconducting magnets to reach higher magnetic field strengths and higher mirror ratios, high secondary emission chamber walls to increase the yield of cold electrons at the chamber surfaces and microwaves of multiple frequencies to improve plasma heating

  20. Astatine-211 Pathway from Radiochemistry to Clinical Investigation

    Particularly in clinical settings where tumour burden is low and cancers are located in close proximity to essential normal tissue structures, α-particle emitting radionuclides can offer significant advantages for targeted radionuclide therapy. One of the first alpha emitters to be evaluated for this purpose is the 7.2-h half-life radiohalogen Astatine-211 (211At). From a commercialization-potential perspective 211At, is less appealing than the longer half-life alpha particle emitters Radium-223, Actinium-225 and Thorium-227, which have become the focus of many laboratories. However, if methods for providing a better supply of 211At could be developed, this alpha emitter would be the radionuclide of choice for many potential therapeutic applications. With regard to the production of 211At, this can be readily be accomplished by bombarding natural bismuth targets with 28−29.5 MeV alpha particles via the 209Bi(α,2n)211At reaction. The goal is to utilize an alpha particle beam energy that provides the required balance for maximizing 211At production while minimizing creation of 210At, which is problematic because of its 138.4-day half life alpha-particle emitting daughter, 210Po. For most intended clinical applications, alpha particle beam energy of about 29 MeV offers the best compromise between maximizing yield and providing 211At with sufficient radionuclidic purity for clinical use. Clinically relevant levels of 211At have been produced at several institutions using both internal and external cyclotron targets

  1. Communication of nuclear data progress: No.16 (1996)

    'Communication of Nuclear Data Progress' (CNDP) in English is set up by Chinese Nuclear Data Center. This is the 16th issue. The nuclear data achievements and progress in China during the last year are presented. It includes the measurements of neutron activation cross section for 193Ir(n,2n)192m2Ir reaction at 14.7 MeV and fragment angular distributions in the fission of 197Au, 207Pb and 209Bi induced by alpha particles up to 70 MeV; discrete level effect on spectrum calculations of secondary particles, calculations of n + 235U (En = 5 MeV) scattering angle distribution by ECIS95 and various cross sections for n + 169Tm and 103Rh reactions up to 100 MeV and 25 MeV respectively, and p + 52Cr reactions up to 30 MeV; evaluations of H total neutron cross section from 20 MeV to 2 GeV and 169Tm(n,xn)168,167,166,165Tm reactions from threshold to 100 MeV, evaluation and calculation of production cross sections for 11C, 13N and 15O medical radioisotopes from 11B, 13C, 15N(p,n) and 16O(p,x)13N reactions up to 80 MeV; an approach of systematic description of gamma-ray spectra from (n,xγ) reactions induced by fast neutron; data files of optical model parameter and level density sub-libraries

  2. Study of fission cross sections induced by nucleons and pions using the cascade-exciton model CEM95

    Nucleon and pion-induced fission cross sections at intermediate and at higher energies are important in current nuclear applications, such as accelerator driven-systems (ADS), in medicine, for effects on electronics etc. In the present work, microscopic fission cross sections induced by nucleons and pions are calculated using the cascade-exciton model code CEM95 for different projectile-target combinations; at various energies and the computed cross sections are compared with the experimental data found in literature. A new approach is used to compute the fission cross sections in which a change of the ratio of the level density parameter in fission to neutron emission channels was taken into account with the change in the incident energy of the projectile. We are unable to describe well the fission cross sections without using this new approach. Proton induced fission cross sections are calculated for targets 197Au, 208Pb, 209Bi, 238U and 239Pu in the energy range from 20 MeV to 2000 MeV. Neutron induced fission cross sections are computed for 238U and 239Pu in the energy range from 20 MeV to 200 MeV. Negative pion induced cross sections for fission are calculated for targets 197Au and 208Pb from 50 MeV to 2500 MeV energy range. The calculated cross sections are essential to build a data library file for accelerator driven systems just like was built for conventional nuclear reactors. The computed values exhibited reasonable agreement with the experimental values found in the literature across a wide range of beam energies

  3. Neutron fluences and dose equivalents measured with passive detectors on LDEF

    Frank, A. L.; Benton, E. V.; Armstrong, T. W.; Colborn, B. L.

    1996-01-01

    Neutron fluences were measured on LDEF in the low energy ( 1 MeV) ranges. The low energy detectors used the 6Li(n,alpha)T reaction with Gd foil absorbers to separate thermal (neutron response. High energy detectors contained sets of fission foils (181Ta, 209Bi, 232Th, 238U) with different neutron energy thresholds. The measured neutron fluences together with predicted spectral shapes were used to estimate neutron dose equivalents. The detectors were located in the A0015 and P0006 experiments at the west and Earth sides of LDEF under shielding varying from 1 to 19 g/cm2. Dose equivalent rates varied from 0.8 to 3.3 microSv/d for the low energy neutrons and from 160 to 390 microSv/d for the high energy neutrons. This compares with TLD measured absorbed dose rates in the range of 1000-3000 microGy/d near these locations and demonstrates that high energy neutrons contribute a significant fraction of the total dose equivalent in LEO. Comparisons between measurements and calculations were made for high energy neutrons based on fission fragment tracks generated by fission foils at different shielding depths. A simple 1-D slab geometry was used in the calculations. Agreement between measurements and calculations depended on both shielding depth and threshold energy of the fission foils. Differences increased as both shielding and threshold energy increased. The modeled proton/neutron spectra appeared deficient at high energies. A 3-D model of the experiments is needed to help resolve the differences.

  4. Progress Report 1981

    The facilities at the Studsvik Research Centre serve as a basis for fundamental research. The neutron diffraction work aiming at determining crystal structures has continued both with single crystals and powders in collaboration with university groups from Lund, Stockholm, Goeteborg and Uppsala. Results are reported for a number of compounds. The neutron scattering studies deal with liquid metals and elementary excitations in liquid 3He. Another project is to equip a reactor channel with a Sc filter to produce nearly mehoenergetic neutron beams. The R2-0 reactor is used in the isotope-separator-on-line experiment OSIRIS. The main research activity has been connected to studies of the properties of short-lived neutron-rich isotopes of zinc, gallium, germanium, bromine, cadmium, indium and iodine. Thermal neutron induced fission of 235U at OSIRIS and heavy-ion induced regetions are studied as a collaboration project with a group at Lawrence Barkeley Laboratory. The Van de Graaff-accelerator is used for experiments in elastic scattering from radiogenic Pb and 209Bi, inelastic scattering from 80 Y and 141Pr. The accelerator is also used for analytical determinations using the PIXE technique. The radiation chemistry group has continued the studies of primary reactions in crystalline organic materials using pulse radiolysis and ESR spectroscopy techniques. The kinetics of the decay of the ions is determined after irradiations with a pulsed 800 kV electron accelerator of type Febetron. The laboratory has been financially supported by the Natural Science Research Council and the Board of Technical Development. A description of research programs is given and list of publication is presented. (G.B.)

  5. Communication of nuclear data progress: No.14 (1995)

    Communication of Nuclear Data Progress (CNDP) in English is set up by Chinese Nuclear Data Center. This is the fourteenth issue, in which the achievements in nuclear data field for the last year in P.R. China are published. It includes the measurements of neutron activation cross sections for 64Zn(n,γ)65Zn, 23Na(n,2n)22Na, 92Mo(n,p)92mNb, 94Mo(n,2n)93mMo, 98Mo(n,p)98mNb, Ba(n,x)134Cs, 134Ba(n,2n)133Ba, 137Ba(n,p)137Cs, 140Ce(n,2n)139Ce, 142Ce(n,2n)141Ce, 179Hf(n,2n)178m2Hf and 209Bi(n,2n)208Bi reactions; calculation of neutron induced reactions on nuclides 175,176,NatLu and 89Y (emphatically on γ-production data); a γ-production data intercomparison system and intercomparison of Fe, Cr, Ni γ-production data; evaluations of n + 56Fe, 58,60,61,62,64,NatNi(n,α), 93Nb(n,2n), (n,n') and 58Ni, 87Rb, 89Y, 90Zr, 140Ce, 169Tm(n,2n) reaction cross sections; sensitivity of logft on ε branching to ground state of 197Au in decay of 197Hg; evaluated particle reflection data base, physical sputtering simulated calculation; progress on parameter and program libraries

  6. Ambiguities in the elastic scattering of 8 MeV neutrons from adjacent nuclei

    Ratios of the cross sections for elastic scattering of 8 MeV neutrons from adjacent nuclei are measured over the angular range ∼20 degree - 160 degree for the target pairs 51V/Cr, 59Co/58Ni, Cu/Zn, 89Y/93Nb, 89Y/Zr, 93Nb/Zr, In/Cd and 209Bi/Pb. The observed ratios vary from unity by as much as a factor of ∼2 at some angles for the lighter target pairs. Approximately half the measured ratios are reasonably explained by a simple spherical optical model, including size and isospin contributions. In all cases, the geometry of the real optical--model potential is essentially the same for neighboring nuclei, and the real--potential strengths are consistent with the Lane model. In contrast, it is found that the imaginary potential may be quite different for adjacent nuclei, and the nature of this difference is examined. It is shown that the spin--spin interaction has a negligible effect on the calculation of the elastic--scattering ratios, but that channel coupling, leading to a large reorientation of the target ground state, can be a consideration, particularly in the 59Co/58Ni case. In the A ∼ 50--60 region the calculated ratios are sensitive to spin--orbit effects, but the exact nature of this interaction must await more definitive polarization measurements. The measured and calculated results suggest that the concept of a conventional ''global'' or even ''regional'' optical potential provides no more than a qualitative representation of the physical reality for a number of cases. 48 refs., 14 figs., 3 tabs

  7. Effect of implanted species on thermal evolution of ion-induced defects in ZnO

    Implanted atoms can affect the evolution of ion-induced defects in radiation hard materials exhibiting a high dynamic annealing and these processes are poorly understood. Here, we study the thermal evolution of structural defects in wurtzite ZnO samples implanted at room temperature with a wide range of ion species (from 11B to 209Bi) to ion doses up to 2 × 1016 cm−2. The structural disorder was characterized by a combination of Rutherford backscattering spectrometry, nuclear reaction analysis, and transmission electron microscopy, while secondary ion mass spectrometry was used to monitor the behavior of both the implanted elements and residual impurities, such as Li. The results show that the damage formation and its thermal evolution strongly depend on the ion species. In particular, for F implanted samples, a strong out-diffusion of the implanted ions results in an efficient crystal recovery already at 600 °C, while co-implantation with B (via BF2) ions suppresses both the F out-diffusion and the lattice recovery at such low temperatures. The damage produced by heavy ions (such as Cd, Au, and Bi) exhibits a two-stage annealing behavior where efficient removal of point defects and small defect clusters occurs at temperatures ∼500 °C, while the second stage is characterized by a gradual and partial annealing of extended defects. These defects can persist even after treatment at 900 °C. In contrast, the defects produced by light and medium mass ions (O, B, and Zn) exhibit a more gradual annealing with increasing temperature without distinct stages. In addition, effects of the implanted species may lead to a nontrivial defect evolution during the annealing, with N, Ag, and Er as prime examples. In general, the obtained results are interpreted in terms of formation of different dopant-defect complexes and their thermal stability

  8. Resonant Raman spectroscopy study of swift heavy ion irradiated MoS2

    Guo, Hang; Sun, Youmei; Zhai, Pengfei; Zeng, Jian; Zhang, Shengxia; Hu, Peipei; Yao, Huijun; Duan, Jinglai; Hou, Mingdong; Liu, Jie

    2016-08-01

    Molybdenum disulphide (MoS2) crystal samples were irradiated by swift heavy ions (209Bi and 56Fe). Hillock-like latent tracks were observed on the surface of irradiated MoS2 by atomic force microscopy. The modifications of properties of irradiated MoS2 were investigated by resonant Raman spectroscopy and ultraviolet-visible spectroscopy (UV-Vis). A new peak (E1u2, ∼385.7 cm-1) occurs near the in-plane E2g1 peak (∼383.7 cm-1) after irradiation. The two peaks shift towards lower frequency and broaden due to structural defects and stress with increasing fluence. When irradiated with high fluence, two other new peaks appear at ∼ 190 and ∼ 230 cm-1. The peak at ∼230 cm-1 is disorder-induced LA(M) mode. The presence of this mode indicates defects induced by irradiation. The feature at ∼460 cm-1 is composed of 2LA(M) (∼458 cm-1) and A2u (∼466 cm-1) mode. With increasing fluence, the integrated intensity ratio between 2LA(M) and A2u increases. The relative enhancement of 2LA(M) mode is in agreement with the appearance of LA(M) mode, which both demonstrate structural disorder in irradiated MoS2. The ∼423-cm-1 peak shifts toward lower frequency due to the decrease in exciton energy of MoS2, and this was demonstrated by the results of UV-Vis spectra. The decrease in exciton energy could be due to introduction of defect levels into band gap.

  9. Studies of heavy ion reactions and transuranic nuclei. Progress report, August 1, 1983-August 31, 1984

    The status of the current understanding of the microscopic mechanisms operating in damped nuclear reactions is reviewed. Several experimental and conceptual problems of attempts to determine the nuclear interaction potential for distances inside the fusion barrier are discussed. An explanation of the unexpectedly large angular anisotropies of fragments from fission of heavy systems produced at large spins has been found in terms of the statistical scission model. In this model, the phase space available to the final deformed fission fragments governs the fission probability. Processes associated with incomplete linear-momentum transfer have been studied for 292-MeV 20Ne-induced fission with targets of 165Ho, 181Ta, 197Au, 209Bi, and 238U. Preequilibrium neutron emission has been studied in central and peripheral 165Ho + 20Ne and 165Ho + 12C collisions at bombarding energies between 11 and 25 MeV/nucleon. In preparation of kinematically complete coincidence experiments, a fast, position-sensitive avalanche detector with a large active area has been developed. The theoretical framework of the statistical scission model for fission has been reconsidered. Exclusive measurements were made of alpha particles emitted in the damped reaction 165Ho + 56Fe at E/sub Lab/ = 465 MeV. The data were interpreted with the aid of rather detailed Monte Carlo evaporation simulations. As part of an extensive coincidence study of equilibration mechanisms in damped reactions, inclusive measurements of projectile-like and fusion-fission-like fragments have been performed for the 197Au + 51V system at E/sub Lab/ = 447 MeV. The damped reaction features have been interpreted in terms of phenomenological reaction models

  10. Influence of projectile neutron number on cross section in cold fusion reactions

    Elements 107-112 [1,2] have been discovered in reactions between 208Pb or 209Bi targets and projectiles ranging from 54Cr through 70Zn. In such reactions, the compound nucleus can be formed at excitation energies as low as ∼12 MeV, thus this type of reaction has been referred to as 'cold fusion'. The study of cold fusion reactions is an indispensable approach to gaining a better understanding of heavy element formation and decay. A theoretical model that successfully predicts not only the magnitudes of cold fusion cross sections, but also the shapes of excitation functions and the cross section ratios between various reaction pairs was recently developed by Swiatecki, Siwek-Wilczynska, and Wilczynski [3,4]. This theoretical model, also referred to as Fusion by Diffusion, has been the guide in all of our cold fusion studies. One particularly interesting aspect of this model is the large predicted difference in cross sections between projectiles differing by two neutrons. The projectile pair where this difference is predicted to be largest is 48Ti and 50Ti. To test and extend this model, 208Pb(48Ti,n)255Rf and 208Pb(50Ti,n)257Rf excitation functions were recently measured at the Lawrence Berkeley National Laboratory's (LBNL) 88-Inch Cyclotron utilizing the Berkeley Gas-filled Separator (BGS). The 50Ti reaction was carried out with thin lead targets (∼100 (micro)g/cm2), and the 48Ti reaction with both thin and thick targets (∼470 (micro)g/cm2). In addition to this reaction pair, reactions with projectile pairs 52Cr and 54Cr [5], 56Fe and 58Fe [6], and 62Ni [7] and 64Ni [8] will be discussed and compared to the Fusion by Diffusion predictions. The model predictions show a very good agreement with the data

  11. Alpha-decay properties of {sup 261}Bh

    Hessberger, F.P.; Ackermann, D.; Heinz, S.; Khuyagbaatar, J.; Kindler, B.; Kojouharov, I.; Lommel, B.; Mann, R. [Helmholtzzentrum fuer Schwerionenforschung GmbH, GSI, Darmstadt (Germany); Antalic, S. [Comenius University Bratislava, Department of Nuclear Physics and Biophysics, Bratislava (Slovakia); Hofmann, S. [Helmholtzzentrum fuer Schwerionenforschung GmbH, GSI, Darmstadt (Germany); Goethe-Universitaet Frankfurt, Institut fuer Physik, Frankfurt (Germany)

    2010-02-15

    The isotope {sup 261}Bh was produced in the reaction {sup 209}Bi({sup 54}Cr,2n){sup 261}Bh and its {alpha} decay has been remeasured. It was found that it populates by an unhindered transition of {approx} 10 MeV an excited level at E{sup *} >350 keV in the daughter nucleus {sup 257}Db. The latter decays by internal transitions either into the isomeric state or the ground state. A somewhat improved half-life value of T{sub 1/2}=11.8{sup +3.9} {sub -2.4} ms was obtained for {sup 261}Bh. The data support the previous assignment of the {alpha} activities {sup 257}Db (1) and {sup 257}Db (2) to the isomer and to the ground state, respectively. No evidence for an isomeric state in {sup 261}Bh decaying by {alpha} emission was found. Based on the experimental results and theoretical calculations a partial decay scheme of {sup 261}Bh including spin and parity assignments of the ground-state and excited levels in the daughter nucleus {sup 257}Db populated by the {alpha} decay and succeeding internal transitions have been suggested. {sup 261}Bh represents so far the heaviest nucleus for which such an attempt has been made. No spontaneous fission (SF) events that could be attributed to {sup 261}Bh were observed, resulting in an SF branching b{sub SF}< 0.05. The measured production cross-section is (64{+-}15) pb at E{sup *}=22 MeV. (orig.)

  12. Investigation of neutron spectra and transmutation of 129I, 237Np and other nuclides with 1.5 GeV protons from the Dubna Nuclotron using the electronuclear setup 'Energy plus Transmutation'

    Experiments which are part of the scientific program 'Investigations of physical aspects of electronuclear method of energy production and transmutation for radioactive waste of atomic energetics using relativistic beams from the JINR Synchrophasotron/Nuclotron' (project 'Energy plus Transmutation') are described. A large lead target surrounded by a four-section uranium blanket with a total weight of 206.4 kg natural uranium was irradiated with 1.5 GeV protons from the new cryogenic accelerator Nuclotron. Radiochemical sensors were exposed to the secondary particle fluences inside and on top of the target assembly. Two long-lived radioactive waste of atomic energetics sensors 129I and 237Np (approximately 1 g weight each) and stable nuclides 27Al, 59Co, 127I, 139La, 197Au and 209Bi as well as natural and enriched uranium were used. In addition, various solid state nuclear track detectors and nuclear emulsions were exposed simultaneously. The experimental results confirm the theoretical estimations that the neutron spectra around the U/Pb-assembly are dominated by medium- and high-energy neutrons as shown by the observation of (n, xn)-reaction products in Co, Au and Bi sensors. The yield of thermal neutrons on the surface of the U-blanket is strongly reduced as compared to the surface of a smaller Pb target surrounded with paraffin. The latter data were determined with (n, γ) reactions in stable La sensors. In this experiment the technique of nuclear emulsions has been applied for the first time to measurements of neutron spectra in an accelerator driven system

  13. Nucleon-induced fission cross sections of heavy nuclei in the intermediate energy region

    Fission is the most important nuclear reaction for society at large today due to its use in energy production. However, this has raised the problem of how to treat the long-lived radioactive waste from nuclear reactors. A radical solution would be to change the composition of the waste into stable or short-lived nuclides, which could be done through nuclear transmutation. Such a concept requires accelerator-driven systems to be designed, where those for transmutation are reactor hybrids. This thesis is a contribution to the knowledge base for developing transmutation systems, specifically with respect to the computational modeling of the underlying nuclear reactions, induced by the incident and secondary particles. Intermediate energy fission cross sections are one important type of such data. Moreover, they are essential for understanding the fission process itself and related nuclear interactions. The experimental part of this work was performed at the neutron beam facility of the The Svedberg Laboratory in Uppsala. Fission cross sections of 238U, 209Bi, Pb, 208Pb, 197Au, W, and 181Ta were measured for neutrons in the range En, = 30-160 MeV using thin-film breakdown counters for the fission fragment detection. A model was developed for the determination of the efficiency of such detectors. A compilation of existing data on proton-induced fission cross sections for nuclei from 165Ho to 239Pu was performed. The results, which constitute the main body of information in this field, were added to the worldwide EXFOR database. The dependences of the cross sections on incident energy and target nucleus were studied, which resulted in systematics that make it possible to give estimates for unmeasured nuclides. Nucleon-induced fission cross sections were calculated using an extended version of the cascade exciton model. A comparison with the systematics and the experimental data obtained in the present work revealed significant discrepancies. A modification of the model

  14. Nuclear-decay studies of neutron-rich rare-earth nuclides

    Chasteler, R.M. (California Univ., Berkeley, CA (USA). Dept. of Chemistry Lawrence Berkeley Lab., CA (USA))

    1990-04-26

    Neutron-rich rare-earth nuclei were produced in multinucleon transfer reactions of {sup 170}Er and {sup 176}Yb projectiles on {sup nat}W targets at the Lawrence Berkeley Laboratory SuperHILAC and their radioactive decays properties studied at the on-line mass separation facility OASIS. Two unknown isotopes, {sup 169}Dy (t {sub 1/2} {equals} 39 {plus minus} 8 s) and {sup 174}Er(t{sub 1/2} {equals} 3.3 {plus minus} 0.2 m) were discovered and their decay characteristics determined. The decay schemes for two previously identified isotopes, {sup 168}Dy (t{sub 1/2} {equals} 8.8 {plus minus} 0.3 m) and {sup 171}Ho (t{sub 1/2} {equals} 55 {plus minus} 3 s), were characterized. Evidence for a new isomer of 3.0 m {sup 168}Ho{sup g}, {sup 168}Ho{sup m} (t{sub 1/2} {equals} 132 {plus minus} 4 s) which decays by isomeric transition (IT) is presented. Beta particle endpoint energies were determined for the decay of {sup 168}Ho{sup g}, {sup 169}Dy, {sup 171}Ho, and {sup 174}Er, the resulting Q{beta}-values are: 2.93 {plus minus} 0.03, 3.2 {plus minus} 0.3, 3.2 {plus minus} 0.6, and 1.8 {plus minus} 0.2 MeV, respectively. These values were compared with values calculated using recent atomic mass formulae. Comparisons of various target/ion source geometries used in the OASIS mass separator facility for these multinucleon transfer reactions were performed. 73 refs., 40 figs., 11 tabs.

  15. Production metallic 26Mg from 26MgO and the synthesis new isotope of 265Bh

    The metallicion beam is of importance for production of heavy elements by heavy-ion fusion evaporation reactions. In order to try to synthese a new superheavy nuclide 265Bh (Z=107), a reaction of 243Am target with 26Mg ion beam is selected to produce new isotope 265Bh. The preparation and production of this rare and extremely expensive isotope 26Mg used for ion beam substance will be the key problem in synthesizing experiment of 265Bh. The available chemical form of isotope 26Mg in commercial product usually is oxide or other compound, which are not required in our experiment. They need to be transformed to metal form as a proper working substance in ion source. There is a lot of technique to prepare metallic 26Mg from its oxide. Pidgeon method of them is the most common technique. Its basic principle is that the metallic 26Mg could be reduced from 26MgO with FeSi (Ferro-Silicon): 226MgO + 2CaO + FeSi→226Mg + Ca2SiO4 + Fe The set-up for producing 26Mg consists of a tubal electric oven, a sealed stainless steel tube connected with a vacuum pump, and a tantalum foil put in inner wall of the tube and used to collect 26Mg sample. The bottom of the tube is filled with the mixture of 26MgO, CaO and FeSi powder. It is heated at 1200 degree C for the reduction. The top part of the tube is cooled by circular water. In this case, temperature grads are formed along the tube. So the magnesium vapour produced from the reaction will be condensed to crystal on the surface of tantalum collection foil where the temperature is suitable for the condensation of 26Mg vapour (∼400-600 degree C). In the experiment, several conditions such as temperature, reduction. time, proportion of the mixture component etc are investigated, and-the optimal conditions are obtained. At 1200 degree C, the production rate of metallic 26Mg is ∼0.5 g/h. The reduction efficiency is larger than 90% and the chemistry purity of magnesium is 99.9%. In conclusion, 26Mg with a good quality has been obtained

  16. Radionuclide desorption kinetics on synthetic Zn/Ni-labeled montmorillonite nanoparticles

    Huber, F. M.; Heck, S.; Truche, L.; Bouby, M.; Brendlé, J.; Hoess, P.; Schäfer, T.

    2015-01-01

    Sorption/desorption kinetics for selected radionuclides (99Tc(VII), 232Th(IV), 233U(VI), 237Np(V), 242Pu and 243Am(III)) under Grimsel (Switzerland) ground water conditions (pH 9.7 and ionic strength of ∼1 mM) in the presence of synthetic Zn or Ni containing montmorillonite nanoparticles and granodiorite fracture filling material (FFM) from Grimsel were examined in batch studies. The structurally bound Zn or Ni in the octahedral sheet of the synthetic colloids rendered them suitable as colloid markers. Only a weak interaction of the montmorillonite colloids with the fracture filling material occurs over the experimental duration of 10,000 h (∼13 months). The tri- and tetravalent radionuclides are initially strongly associated with nanoparticles in contrast to 99Tc(VII), 233U(VI) and 237Np(V) which showed no sorption to the montmorillonite colloids. Radionuclide desorption of the nanoparticles followed by sorption to the fracture filling material is observed for 232Th(IV), 242Pu and 243Am(III). Based on the conceptual model that the driving force for the kinetically controlled radionuclide desorption from nanoparticles and subsequent association to the FFM is the excess in surface area offered by the FFM, the observed desorption kinetics are related to the colloid/FFM surface area ratio. The observed decrease in concentration of the redox sensitive elements 99Tc(VII), 233U(VI) and 237Np(V) may be explained by reduction to lower oxidation states in line with Eh-pH conditions prevailing in the experiments and thermodynamic considerations leading to (i) precipitation of a sparingly soluble phase, (ii) sorption to the fracture filling material, (iii) possible formation of eigencolloids and/or (iv) sorption to the montmorillonite colloids. Subsequent to the sorption/desorption kinetics study, an additional experiment was conducted investigating the potential remobilization of radionuclides/colloids attached to the FFM used in the sorption/desorption kinetic

  17. Enumeration of microbial populations in radioactive environments by epifluorescence microscopy

    Epifluorescence microscopy was utilized to enumerate halophilic bacterial populations in two studies involving inoculated, actual waste/brine mixtures and pure brine solutions. The studies include an initial set of experiments designed to elucidate potential transformations of actinide-containing wastes under salt-repository conditions, including microbially mediated changes. The first study included periodic enumeration of bacterial populations of a mixed inoculum initially added to a collection of test containers. The contents of the test containers are the different types of actual radioactive waste that could potentially be stored in nuclear waste repositories in a salt environment. The transuranic waste was generated from materials used in actinide laboratory research. The results show that cell numbers decreased with time. Sorption of the bacteria to solid surfaces in the test system is discussed as a possible mechanism for the decrease in cell numbers. The second study was designed to determine radiological and/or chemical effects of 239Pu, 243Am, 237Np, 232Th and 238U on the growth of pure and mixed anaerobic, denitrifying bacterial cultures in brine media. Pu, Am, and Np isotopes at concentrations of ≤1x10-6 M , ≤5x10-6 M and ≤5x10-4M respectively, and Th and U isotopes ≤4x10-3M were tested in these media. The results indicate that high concentrations of certain actinides affected both the bacterial growth rate and morphology. However, relatively minor effects from Am were observed at all tested concentrations with the pure culture

  18. Managing Inventories of Heavy Actinides

    The Department of Energy (DOE) has stored a limited inventory of heavy actinides contained in irradiated targets, some partially processed, at the Savannah River Site (SRS) and Oak Ridge National Laboratory (ORNL). The 'heavy actinides' of interest include plutonium, americium, and curium isotopes; specifically 242Pu and 244Pu, 243Am, and 244/246/248Cm. No alternate supplies of these heavy actinides and no other capabilities for producing them are currently available. Some of these heavy actinide materials are important for use as feedstock for producing heavy isotopes and elements needed for research and commercial application. The rare isotope 244Pu is valuable for research, environmental safeguards, and nuclear forensics. Because the production of these heavy actinides was made possible only by the enormous investment of time and money associated with defense production efforts, the remaining inventories of these rare nuclear materials are an important part of the legacy of the Nuclear Weapons Program. Significant unique heavy actinide inventories reside in irradiated Mark-18A and Mark-42 targets at SRS and ORNL, with no plans to separate and store the isotopes for future use. Although the costs of preserving these heavy actinide materials would be considerable, for all practical purposes they are irreplaceable. The effort required to reproduce these heavy actinides today would likely cost billions of dollars and encompass a series of irradiation and chemical separation cycles for at least 50 years; thus, reproduction is virtually impossible. DOE has a limited window of opportunity to recover and preserve these heavy actinides before they are disposed of as waste. A path forward is presented to recover and manage these irreplaceable National Asset materials for future use in research, nuclear forensics, and other potential applications.

  19. Fabrication and characterization of MCC approved testing material: ATM-9 glass

    The Materials Characterization Center ATM-9 glass is designed to be representative of glass to be produced by the Defense Waste Processing Facility at the Savannah River Plant, Aiken, South Carolina. ATM-9 glass contains all of the major components of the DWPF glass and corresponds to a waste loading of 29 wt %. The feedstock material for this glass was supplied by Savannah River Laboratory, Aiken, SC, as SRL-165 Black Frit to which was added Ba, Cs, Md, Nd, Zr, as well as 99Tc, depleted U, 237Np, 239+240Pu, and 243Am. The glass was produced under reducing conditions by the addition of 0.7 wt % graphite during the final melting process. Three kilograms of the glass were produced from April to May of 1984. On final melting, the glass was formed into stress-annealed rectangular bars of two sizes: 1.9 x 1.9 x 10 cm and 1.3 x 1.3 x 10 cm. Seventeen bars of each size were made. The analyzed composition of ATM-9 glass is listed. Examination by optical microscopy of a single transverse section from one bar showed random porosity estimated at 0.36 vol % with nominal pore diameters ranging from approx. 5 μm to 200 μm. Only one distinct second phase was observed and it was at a low concentraction level in the glass matrix. The phase appeared as spherical metallic particles. X-ray diffraction analysis of this same sample did not show any diffraction peaks from crystalline components, indicating that the glass contained less than 5 wt % of crystalline devitrification products. The even shading on the radiograph exposure indicated a generally uniform distribution of radioactivity throughout the glass matrix, with no distinct high-concentration regions

  20. New radiochemical methods for determination of 237Np a 241Pu using extraction chromatography (Presentation)

    Thesis was focused on the development of a new methodology for the separation of anthropogenic transuranium radionuclides 237Np a 241Pu from different kinds of matrices. The analytical methods used in this study were based on extraction chromatography and were optimized according to the sample type. The proposed radiochemical procedure is a combination of two algorithms, which represent the separation of radionuclides by using extraction chromatographic sorbents TEVA resin and TRU resin supplied by Eichrom Technologies LLC. 239Np a 237Np were selectively captured on sorbent TEVA resin in oxidation state 4+. TRU resin was used for purification of plutonium fraction from interfering americium radionuclide. 242Pu and 239Np radionuclides as tracers have been used to monitor the radiochemical yields of separation. Before every radiochemical separation tracer radionuclide 239Np was obtained by separation from the parent radionuclide 243Am, which is in radioactive equilibrium to 239Np. The average yield of chemical separation was 69,3% for 239Np at 277 keV energy line and 65,9% at 228 keV energy line. The NPL AH-B08069 (2008) samples which consist of the mixture of alpha-radionuclides were used for the modification and optimization of separation method used for separation of Np and Pu in model samples. This method provided high radiochemical yields of 239,240Pu (95,0 ± 3,5)% and 237Np (87,9 ± 3,0)%.. Reliability of the method was verified by applying our modified separation procedures on reference materials IAEA-375 and IAEA-414 supplied by International Atomic Energy Agency. A good agreement between the results is obtained by this procedure and the certified values were found. Samples of contaminated soils from the area of Nuclear power plant A-1 Jaslovske Bohunice which is stored temporarily before disposal were analyzed using developed separation procedure. Specific activity of investigated radionuclides was determined in these samples. (author)

  1. New radiochemical methods for determination of 237Np a 241Pu using extraction chromatography

    Thesis was focused on the development of a new methodology for the separation of anthropogenic transuranium radionuclides 237Np a 241Pu from different kinds of matrices. The analytical methods used in this study were based on extraction chromatography and were optimized according to the sample type. The proposed radiochemical procedure is a combination of two algorithms, which represent the separation of radionuclides by using extraction chromatographic sorbents TEVA resin and TRU resin supplied by Eichrom Technologies LLC. 239Np a 237Np were selectively captured on sorbent TEVA resin in oxidation state 4+. TRU resin was used for purification of plutonium fraction from interfering americium radionuclide. 242Pu and 239Np radionuclides as tracers have been used to monitor the radiochemical yields of separation. Before every radiochemical separation tracer radionuclide 239Np was obtained by separation from the parent radionuclide 243Am, which is in radioactive equilibrium to 239Np. The average yield of chemical separation was 69,3% for 239Np at 277 keV energy line and 65,9% at 228 keV energy line. The NPL AH-B08069 (2008) samples which consist of the mixture of alpha-radionuclides were used for the modification and optimization of separation method used for separation of Np and Pu in model samples. This method provided high radiochemical yields of 239,240Pu (95,0 ± 3,5)% and 237Np (87,9 ± 3,0)%.. Reliability of the method was verified by applying our modified separation procedures on reference materials IAEA-375 and IAEA-414 supplied by International Atomic Energy Agency. A good agreement between the results is obtained by this procedure and the certified values were found. Samples of contaminated soils from the area of Nuclear power plant A-1 Jaslovske Bohunice which is stored temporarily before disposal were analyzed using developed separation procedure. Specific activity of investigated radionuclides was determined in these samples. (author)

  2. OSMOSE program : statistical review of oscillation measurements in the MINERVE reactor R1-UO2 configuration.

    Stoven, G.; Klann, R.; Zhong, Z.; Nuclear Engineering Division

    2007-08-28

    The OSMOSE program is a collaboration on reactor physics experiments between the United States Department of Energy and the France Commissariat Energie Atomique. At the working level, it is a collaborative effort between the Argonne National Laboratory and the CEA Cadarache Research Center. The objective of this program is to measure very accurate integral reaction rates in representative spectra for the actinides important to future nuclear system designs, and to provide the experimental data for improving the basic nuclear data files. The main outcome of the OSMOSE measurement program will be an experimental database of reactivity-worth measurements in different neutron spectra for the heavy nuclides. This database can then be used as a benchmark to verify and validate reactor analysis codes. The OSMOSE program (Oscillation in Minerve of isotopes in Eupraxic Spectra) aims at improving neutronic predictions of advanced nuclear fuels through oscillation measurements in the MINERVE facility on samples containing the following separated actinides: {sup 232}Th, {sup 233}U, {sup 234}U, {sup 235}U, {sup 236}U, {sup 238}U, {sup 237}Np, {sup 238}Pu, {sup 239}Pu, {sup 240}Pu, {sup 241}Pu, {sup 242}Pu, {sup 241}Am, {sup 243}Am, {sup 244}Cm, and {sup 245}Cm. The first part of this report provides an overview of the experimental protocol and the typical processing of a series of experimental results which is currently performed at CEA-Cadarache. In the second part of the report, improvements to this technique are presented, as well as the program that was created to process oscillation measurement results from the MINERVE facility in the future.

  3. Safe handling of kilogram amounts of fuel-grade plutonium and of gram amounts of plutonium-238, americium-241 and curium-244

    During the past 10 years about 600 glove-boxes have been installed at the Institute for Transuranium Elements at Karlsruhe. About 80% of these glove-boxes have been designed and equipped for handling 100-g to 1-kg amounts of 239Pu containing 8-12% 240Pu (low-exposure plutonium). A small proportion of the glove-boxes is equipped with additional shielding in the form of lead sheet or lead glass for work with recycled plutonium. In these glove-boxes gram-amounts of 241Am have also been handled for preparation of Al-Am targets using tongs and additional shielding inside the glove-boxes themselves. Water- and lead-shielded glove-boxes equipped with telemanipulators have been installed for routine work with gram-amounts of 241Am, 243Am and 244Cm. A prediction of the expected radiation dose for the personnel is difficult and only valid for a preparation procedure with well-defined preparation steps, owing to the fact that gamma dose-rates depend strongly upon proximity and source seize. Gamma radiation dose measurements during non-routine work for 241Am target preparation showed that handling of gram amounts leads to a rather high irradiation dose for the personnel, despite lead or steel glove-box shielding and shielding within the glove-boxes. A direct glove-hand to americium contact must be avoided. For all glove-handling of materials with gamma radiation an irradiation control of the forearms of the personnel by, for example, thermoluminescence dosimeters is necessary. Routine handling of americium and curium should be executed with master-slave equipment behind neutron and gamma shielding. (author)

  4. Simultaneous photon and neutron interrogation using an electron accelerator in order to quantify actinides in encapsulated radioactive wastes

    Measuring out alpha emitters, such as (234,235,236,238U 238,239,240,242,244Pu, 237Np 241,243Am...), in solid radioactive waste, allows us to quantify the alpha activity in a drum and then to classify it. The SIMPHONIE (SIMultaneous PHOton and Neutron Interrogation Experiment) method, developed in this Ph.D. work, combines both the Active Neutron Interrogation and the Induced Photofission Interrogation techniques simultaneously. Its purpose is to quantify in only one measurement, fissile (235U, 239,241Pu...) and fertile (236,238U, 238,240Pu...) elements separately. In the first chapter of this Ph.D. report, we present the principle of the Radioactive Waste Management in France. The second chapter deals with the physical properties of neutron fission and of photofission. These two nuclear reactions are the basis of the SIMPHONIE method. Moreover, one of our purposes was to develop the ELEPHANT (ELEctron PHoton And Neutron Transport) code in view to simulate the electron, photon and neutron transport, including the (γ, n), (γ, 2n) and (γ, f) photonuclear reactions that are not taken into account in the MCNP4 (Monte Carlo N-Particle) code. The simulation codes developed and used in this work are detailed in the third chapter. Finally, the fourth chapter gives the experimental results of SIMPHONIE obtained by using the DGA/ETCA electron linear accelerators located at Arcueil, France. Fissile (235U, 239Pu) and fertile (238U) samples were studied. Furthermore, comparisons between experimental results and calculated data of photoneutron production in tungsten, copper, praseodymium and beryllium by using an electron LINear Accelerator (LINAC) are given. This allows us to evaluate the validity degree of the ELEPHANT code, and finally the feasibility of the SIMPHONIE method. (author)

  5. The disposal of Canada's nuclear fuel waste: a study of postclosure safety of in-room emplacement of used CANDU fuel in copper containers in permeable plutonic rock. Volume 4: biosphere model

    AECL (Atomic Energy of Canada Limited) has developed a disposal concept for Canada's nuclear fuel waste, which calls for a vault deep in plutonic rock of the Canadian Shield. The concept has been fully, documented in an environmental impact statement (EIS) for review by a panel under the Canadian Environmental Assessment Agency. The EIS includes the results of the EIS postclosure assessment case study to address the long term safety of the disposal concept. To more fully demonstrate the flexibility of the disposal concept and our assessment methodology, we are now carrying out another postclosure assessment study, which involves different assumptions and engineering options than those used in the EIS. In response to these changes, we have updated the BIOTRAC (BIOsphere Transport and Assessment Code) model developed for the EIS postclosure assessment case study. The main changes made to the BIOTRAC model are the inclusion of 36Cl, 137Cs, 239Np and 243Am; animals inhalation pathway; International Commission on Radiological Protection 60/61 human internal dose conversion factors; all the postclosure assessment nuclides in the dose calculations for non-human biota; and groundwater dose limits for 14C, 16C1 and 129I for non-human biota to parallel these limits for humans. We have also reviewed and changed several parameter values, including evasion rates of gaseous nuclides from soil and release fractions of various nuclides from domestic water, and indicated changes that affect the geosphere/biosphere interface model. These changes make the BIOTRAC model more flexible. As a result of all of these changes, the BIOTRAC model has been significantly expanded and improved, although the changes do not greatly affect model predictions. The modified model for the present study is called BIOTRAC2 (BIOTRAC - Version 2). The full documentation of the BIOTRAC2 model includes the report by Davis et al. (1993a) and this report. (author). 105 refs., 13 tabs., 8 figs

  6. Transmutation of high level wastes in a fusion-driven transmuter (FDT)

    This study presents the transmutations of both the minor actinides (MAs: 237Np, 241Am, 243Am and 244Cm) and the long-lived fission products (LLFPs: 99Tc, 129I and 135Cs), discharged from high burn-up PWR-MOX spent fuel, in a fusion-driven transmuter (FDT) and the effects of the MA and LLFP volume fractions on their transmutations. The blanket configuration of the FDT is improved by analyzing various sample blanket design combinations with different radial thicknesses. Two different transmutation zones (TZMA and TZFP which contain the MA and LLFP nuclides, respectively) are located separately from each other. The volume fraction of the MA is raised from 10 to 20% stepped by 2%. The MAs are cladded with the graphite (10%) and cooled with the high-pressured helium gas for nuclear heat transfer. The volume fraction of helium is reduced from 80 to 70% depending on that of MA. Furthermore, the volume fraction of graphite is raised from 10 to 80% stepped by 5% to slow down the energy of neutrons entering into the TZFP while the volume fraction of LLFP is reduced from 80 to 10% depending on the graphite volume fraction. The calculations are performed for an operation period (OP) of up to 10 years by 75% plant factor (η) under a neutron wall load (P) of 5 MW/m2 to estimate neutronic parameters and transmutation characteristics per D-T fusion neutron. The transmutation rates of the LLFP nuclides increase linearly with the increase of volume fractions of the MA, and the 99Tc nuclide among them has the highest transmutation rate

  7. Development of a MCNP–ORIGEN burn-up calculation code system and its accuracy assessment

    Highlights: • MCNP and ORIGEN are coupled to perform nuclides depletion and decay calculation. • Coupled system MCORE uses “modified predictor corrector” approach. • MCORE can use different depletion schemes and simulate fuel shuffling. • MCORE is assessed by a “VVER-1000 LEU Assembly Computational Benchmark”. • MCORE is also assessed by a fast reactor benchmark problem. - Abstract: An MCNP–ORIGEN burn-up calculation code system, named MCORE (MCNP and ORIGEN burn-up Evaluation code), is developed in this work. MCORE makes use of the Monte Carlo neutron and photon transport code MCNP4C and nuclides depletion and decay calculation code ORIGEN2.1. MCNP and ORIGEN are coupled by data processing and linking subroutines. In MCORE, a so called “modified predictor corrector” approach is used. MCORE provides the capability of using different depletion calculation schemes and simulating fuel shuffling. Total nuclide density changes in active cells are considered in MCORE. The validity and applicability of the developed code are tested by investigating and predicting the neutronic and isotopic behavior of a “VVER-1000 LEU Assembly Computational Benchmark” at lattice level and a “Physics of Plutonium Recycling” fast reactor at core level (OECD-NEA). The comparison results show that the MCORE code predicts the nuclide composition within 5% accuracy and k∞ within 800 pcm at the end of the burn-up for LEU assembly (40 MWD/kg HM). For a fast reactor, the results obtained by MCORE are in the range of reported results except for 243Am. In general, MCORE results show a good agreement with the benchmark values

  8. Simultaneous photon and neutron interrogation using an electron accelerator in order to quantify actinides in encapsulated radioactive wastes; Double interrogation simultanee neutrons et photons utilisant un accelerateur d'electrons pour la caracterisation separee des actinides dans les dechets radioactifs enrobes

    Jallu, F

    1999-09-24

    Measuring out alpha emitters, such as ({sup 234,235,236,238}U {sup 238,239,240,242,}2{sup 44P}u, {sup 237}Np {sup 241,243}Am...), in solid radioactive waste, allows us to quantify the alpha activity in a drum and then to classify it. The SIMPHONIE (SIMultaneous PHOton and Neutron Interrogation Experiment) method, developed in this Ph.D. work, combines both the Active Neutron Interrogation and the Induced Photofission Interrogation techniques simultaneously. Its purpose is to quantify in only one measurement, fissile ({sup 235}U, {sup 239,241}Pu...) and fertile ({sup 236,238}U, {sup 238,240}Pu...) elements separately. In the first chapter of this Ph.D. report, we present the principle of the Radioactive Waste Management in France. The second chapter deals with the physical properties of neutron fission and of photofission. These two nuclear reactions are the basis of the SIMPHONIE method. Moreover, one of our purposes was to develop the ELEPHANT (ELEctron PHoton And Neutron Transport) code in view to simulate the electron, photon and neutron transport, including the ({gamma}, n), ({gamma}, 2n) and ({gamma}, f) photonuclear reactions that are not taken into account in the MCNP4 (Monte Carlo N-Particle) code. The simulation codes developed and used in this work are detailed in the third chapter. Finally, the fourth chapter gives the experimental results of SIMPHONIE obtained by using the DGA/ETCA electron linear accelerators located at Arcueil, France. Fissile ({sup 235}U, {sup 239}Pu) and fertile ({sup 238}U) samples were studied. Furthermore, comparisons between experimental results and calculated data of photoneutron production in tungsten, copper, praseodymium and beryllium by using an electron LINear Accelerator (LINAC) are given. This allows us to evaluate the validity degree of the ELEPHANT code, and finally the feasibility of the SIMPHONIE method. (author)

  9. Development of odd-Z-projectile reactions for transactinide element synthesis

    Folden III, Charles Marvin

    2004-11-04

    The development of new odd-Z-projectile reactions leading to the production of transactinide elements is described. The cross section of the even-Z-projectile 208Pb(64Ni, n)271Ds reaction was measured at two new energies using the Berkeley Gas-filled Separator at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. In total, seven decay chains attributable to 271Ds were observed. These data, combined with previous results, establish an excitation function for the production of 271Ds. The maximum cross section was 20 +15 -11 pb at a center-of-target energy of 311.5 MeV in the laboratory frame.The data from the 271Ds experiments were used to estimate the optimum beam energy for the new odd-Z-projectile 208Pb(65Cu, n)272-111 reaction using the Fusion by Diffusion theory proposed by Swiatecki, Siwek-Wilczynska, and Wilczynski. A cross section for this reaction was measured for the first time, at a center-of-target energy of 321.1 MeV in the laboratory frame. The excitation energy f or compound nuclei formed at the target center was 13.2 MeV. One decay chain was observed, resulting in a measured cross section of 1.7 +3.9 -1.4 pb. This decay chain is in good agreement with previously published data on the decay of 272-111.The new odd-Z-projectile 208Pb(55Mn, n)262Bh reaction was studied at three different projectile energies, and 33 decay chains of 262Bh were observed. The existence of a previously reported alpha-decaying isomeric state in this nuclide was confirmed. Production of the ground state was preferred at all three beam energies. The maximum cross section was 540 +180 -150 pb at a projectile center-of-target energy of 264.0 MeV. This cross section is much larger than that previously reported for the even-Z-projectile 209Bi(54Cr, n)262Bh reaction, which may be because the 54Cr projectile energies in the latter reaction were too high for optimum production of the 1n product. At the highest projectile energy of 268.0 MeV in the target center, two decay

  10. Influence of projectile neutron number on cross section in cold fusion reactions

    Dragojevic, Irena; Dragojevic, I.; Gregorich, K.E.; Dullmann, Ch.E.; Folden III, C.M.; Garcia, M.A.; Gates, J.M.; Nelson, S.L.; Sudowe, R.; Nitsche, H.

    2007-09-01

    Elements 107-112 [1,2] have been discovered in reactions between {sup 208}Pb or {sup 209}Bi targets and projectiles ranging from {sup 54}Cr through {sup 70}Zn. In such reactions, the compound nucleus can be formed at excitation energies as low as {approx}12 MeV, thus this type of reaction has been referred to as 'cold fusion'. The study of cold fusion reactions is an indispensable approach to gaining a better understanding of heavy element formation and decay. A theoretical model that successfully predicts not only the magnitudes of cold fusion cross sections, but also the shapes of excitation functions and the cross section ratios between various reaction pairs was recently developed by Swiatecki, Siwek-Wilczynska, and Wilczynski [3,4]. This theoretical model, also referred to as Fusion by Diffusion, has been the guide in all of our cold fusion studies. One particularly interesting aspect of this model is the large predicted difference in cross sections between projectiles differing by two neutrons. The projectile pair where this difference is predicted to be largest is {sup 48}Ti and {sup 50}Ti. To test and extend this model, {sup 208}Pb({sup 48}Ti,n){sup 255}Rf and {sup 208}Pb({sup 50}Ti,n){sup 257}Rf excitation functions were recently measured at the Lawrence Berkeley National Laboratory's (LBNL) 88-Inch Cyclotron utilizing the Berkeley Gas-filled Separator (BGS). The {sup 50}Ti reaction was carried out with thin lead targets ({approx}100 {micro}g/cm{sup 2}), and the {sup 48}Ti reaction with both thin and thick targets ({approx}470 {micro}g/cm{sup 2}). In addition to this reaction pair, reactions with projectile pairs {sup 52}Cr and {sup 54}Cr [5], {sup 56}Fe and {sup 58}Fe [6], and {sup 62}Ni [7] and {sup 64}Ni [8] will be discussed and compared to the Fusion by Diffusion predictions. The model predictions show a very good agreement with the data.

  11. 两种海胆矿质元素的ICP-MS法测定分析%Determination of mineral elements in two kinds of sea urchin by ICP-MS method

    刘小芳; 薛长湖; 王玉明; 薛勇; 王超

    2012-01-01

    利用电感耦合等离子体质谱法(ICP-MS)测定马粪海胆和紫海胆中K、Ca、Mg、Fe、V、Cr、Mn、Al、Co、Ni、Cu、Zn、As、Se、Mo、Cd、Hg、Pb共18种元素,并以内标元素补偿基体效应,选择适当的待测元素同位素克服质谱干扰,优化实验条件。用HNO3+HClO4(4:1)混酸作为消化液处理样品,各元素在实验范围内线性良好,相关系数均大于0.9984,加标回收率93.11%~116.91%,相对标准偏差(RSD)小于5%。结果表明:马粪海胆和紫海胆中K、Mg、Ca含量较高,且均含有Zn、Fe、Cu、V、Mn、Se等对人体非常有益的微量元素,为海胆的科学合理利用提供理论依据。%Eighteen kinds of mineral elements in sea urchin,Hemicentrotus pulcherrimus and Anthocidaris crassispina,were detected and analyzed by inductively coupled plasma mass spectrometry(ICP-MS).6Li,45Sc,72Ge,89Y,115In,159Tb,209Bi were selected as the internal standard elements.The matrix effect was compensated and the MS interference was corrected by selecting the suitable isotope of the elements.The experimental conditions were optimized.The samples were digested with HNO3+HClO4(4:1).All the detected elements showed a good linear relationship within the working curves,the correlation coefficients were all above 0.9984.The precisions and recoveries were good,the range of recoveries(n=3) was 93.11%~116.91% and the RSDs were all lower than 5%.The results indicated that there were abundant nutritional elements for people in the two kinds of sea urichin.They were all rich in the elements K,Mg,Ca and some trace elements which are beneficial to humans such as Zn,Fe,Cu,V,Mn,Se.This study will provide some useful evidence for the effective exploitation of sea urichin.

  12. ICP-MS Determination of Copper, Arsenic, Molybdenum, Cadmium, Thallium and Lead in Cigarette Paper%电感耦合等离子体质谱法测定卷烟用纸中铜、砷、钼、镉、铊和铅

    李力; 黄馨; 胡清源; 李东亮; 曾建; 戴亚

    2011-01-01

    Six metal elements, i.e, Cu, As, Mo, Cd, T1 and Pb present as impurities in cigarette paper were determined by ICP-MS.The sample was digested with HNO3, H2O2 and HF in Multiwave 3000 Microwave Digestor.Boric acid solution was added to the digested sample solution to complex with excess of HF.Mixed standard solution containing 20 μg · L-1 each of the isotopes of 115 In and 209 Bi was added as internal standard.Linear relationships in definite ranges were obtained and the detection limits (3S/N) found for the 6 elements were in the range from 0.002 to 0.16μg · L-1.Recovery was tested by standard addition method, results obtained were in the range of 95.3% to 113.0%.Repeatability of the method was tested, giving values of RSD's (n=5) ranged from 0.9% to 4.6%.%采用电感耦合等离子体质谱法测定了卷烟纸中铜、砷、钼、镉、铊和铅等6种杂质金属元素.试样用硝酸、过氧化氢及氢氟酸在Multiwave 3000型微波消解仪中消解处理,在所得消解后的溶液中加入硼酸溶液络合过量的氢氟酸.加入含115In及209Bi各20 μg·L-1的混合溶液作为内标.上述6种元素在一定浓度范围内与各相应的分析信号值之间呈线性关系,其检出限(3S/N)在0.002~0.16 μg·L-1之间.按标准加入法测得方法的回收率在95.3%~113.0 %之间.试验了方法的重复性,其相对标准偏差(n=5)在0.9%~4.6%之间.

  13. Measurement of cross sections for the scattering of neutrons in the energy range from 2 MeV to 4 MeV with the {sup 15}N(p,n) reaction as neutron source; Messung von Wirkungsquerschnitten fuer die Streuung von Neutronen im Energiebereich von 2 MeV bis 4 MeV mit der {sup 15}N(p,n)-Reaktion als Neutronenquelle

    Poenitz, Erik

    2010-04-26

    In future nuclear facilities, the materials lead and bismuth can play a more important role than in today's nuclear reactors. Reliable cross section data are required for the design of those facilities. In particular the neutron transport in the lead spallation target of an Accelerator-Driven Subcritical Reactor strongly depends on the inelastic neutron scattering cross sections in the energy region from 0.5 MeV to 6 MeV. In the recent 20 years, elastic and inelastic neutron scattering cross sections were measured with high precision for a variety of elements at the PTB time-of-flight spectrometer. The D(d,n) reaction was primarily used for the production of neutrons. Because of the Q value of the reaction and the available deuteron energies, neutrons in the energy range from 6 MeV to 16 MeV can be produced. For the cross section measurement at lower energies, however, another neutron producing reaction is required. The {sup 15}N(p,n){sup 15}O reaction was chosen, as it allows the production of monoenergetic neutrons with up to 5.7MeV energy. In this work, the {sup 15}N(p,n) reaction was studied with focus on the suitability as a source for monoenergetic neutrons in scattering experiments. This includes the measurement of differential cross sections for the neutron producing reaction and the choice of optimum target conditions. Differential elastic and inelastic neutron scattering cross sections were measured for lead at four energies in the region from 2 MeV to 4 MeV incident neutron energy using the time-of-flight technique. A lead sample with natural isotopic composition was used. NE213 liquid scintillation detectors with well-known detection efficiencies were used for the detection of the scattered neutrons. Angle-integrated cross sections were determined by a Legendre polynomial expansion using least-squares methods. Additionally, measurements were carried out for isotopically pure {sup 209}Bi and {sup 181}Ta samples at 4 MeV incident neutron energy

  14. 碰撞反应池-电感耦合等离子体质谱法检测海藻食品中重金属%Determination of heavy metals in seaweed food by inductively coupled plasma-mass spectrometry with octopole reaction system

    王楠; 庞艳华; 孙瑶; 王璇; 李倩; 刘玲玲; 曹际娟

    2015-01-01

    Objective To establish an analysis method of inductively coupled plasma-mass spectrometry (ICP-MS) with octopole reaction system for the determination of 7 heavy metals including Cr, Ni, Cu, As, Cd, Hg and Pb in seaweed food.Methods After microwave digestion, the samples were directly determined by ICP-MS. Internal standard elements of germanium (72Ge), indium (115In) and bismuth (209Bi) were used to correct matrix interference and signal drifting, and the octopole reaction system (ORS) was used to eliminate mass spectrum interferences. Results The linear standard curves were obtained with the correlation coefficient above 0.9992. The detection limit of the method was 0.003~0.028 μg/L, and the relative standard deviation was less than 4.92%. The recovery rates were 85.6%~106.2%.The experimental results of standard reference materials were in good agreement with the certified values. Conclusion The method is simple, fast, and sensitive, and it is suitable for accurate quantitative analysis of heavy metals in seaweed foods.%目的:建立碰撞反应池—电感耦合等离子体质谱法(inductively coupled plasma-mass spectrometry, ICP-MS)测定海藻食品中铬、镍、铜、砷、镉、汞、铅等重金属元素的分析检测方法。方法样品经微波消解后用电感耦合等离子体质谱仪直接进行分析,采用内标元素72Ge、115In和209Bi消除基体干扰和信号漂移,碰撞反应池技术(ORS)消除质谱干扰。结果各元素校正曲线的相关系数均大于0.9992,方法的检出限0.003μg/L~0.028μg/L,相对标准偏差小于4.92%,加标回收率为85.6%~106.2%,标准参考物质的测定结果与标准值相符。结论该方法前处理操作简便快速,灵敏度高,重复性好,适用于海苔、海带、紫菜等海藻食品中多种元素的同时测定。

  15. Development of odd-Z-projectile reactions for transactinide element synthesis

    The development of new odd-Z-projectile reactions leading to the production of transactinide elements is described. The cross section of the even-Z-projectile 208Pb(64Ni, n)271Ds reaction was measured at two new energies using the Berkeley Gas-filled Separator at the Lawrence Berkeley National Laboratory 88-Inch Cyclotron. In total, seven decay chains attributable to 271Ds were observed. These data, combined with previous results, establish an excitation function for the production of 271Ds. The maximum cross section was 20 +15 -11 pb at a center-of-target energy of 311.5 MeV in the laboratory frame.The data from the 271Ds experiments were used to estimate the optimum beam energy for the new odd-Z-projectile 208Pb(65Cu, n)272-111 reaction using the Fusion by Diffusion theory proposed by Swiatecki, Siwek-Wilczynska, and Wilczynski. A cross section for this reaction was measured for the first time, at a center-of-target energy of 321.1 MeV in the laboratory frame. The excitation energy f or compound nuclei formed at the target center was 13.2 MeV. One decay chain was observed, resulting in a measured cross section of 1.7 +3.9 -1.4 pb. This decay chain is in good agreement with previously published data on the decay of 272-111.The new odd-Z-projectile 208Pb(55Mn, n)262Bh reaction was studied at three different projectile energies, and 33 decay chains of 262Bh were observed. The existence of a previously reported alpha-decaying isomeric state in this nuclide was confirmed. Production of the ground state was preferred at all three beam energies. The maximum cross section was 540 +180 -150 pb at a projectile center-of-target energy of 264.0 MeV. This cross section is much larger than that previously reported for the even-Z-projectile 209Bi(54Cr, n)262Bh reaction, which may be because the 54Cr projectile energies in the latter reaction were too high for optimum production of the 1n product. At the highest projectile energy of 268.0 MeV in the target center, two decay

  16. Importance of the wave function tail in computing the pre-emission probability for the halo neutron from 11 Be fusion with light and heavy targets

    In this work, an improved method for the estimation of the neutron pre-emission probability in a fusion process is given, taking into account a more realistic halo neutron distribution with an extreme long tail. It has been demonstrated that core and halo densities can be separated in: ρ(r) = ρc (r) + ρh (r). 11 Be, the only one neutron halo nucleus has two bound states, both of halo type, with one neutron separation energies 0.5 MeV and 0.2 MeV, respectively. The 2s1/2 state is the main component (77%) of the ground state of 11 Be. The density distribution of the halo neutron was determined by solving Schroedinger equation for a separation energy of Sn = - 0.504 MeV using a Woods-Saxon potential. The halo neutron is considered to be on 2s1/2 state. The root mean square radius of 10 Be is taken as 2.90 fm. All the following steps in our estimation are parameter free for the neutron pre-emission probability method. A sharp cut-off approach for the fusion process was used. After computing the volume distribution, we calculated the superficial distribution of the halo neutron on a surface which is perpendicular on the beam direction. The volume was divided in spherical shells with step equal to 0.1 fm in which we considered the probability distribution to be constant. These shells were projected on that surface. After that, the same method was applied for three energies: E1 near the Coulomb barrier, E2 near the energy of an expected experiment and E3 near that value when the compound nucleus explodes. The results are given in a Table. The pre-emission probability is dependent on target radius. For a smaller size target (12 C, Si), the probability is larger than for a large size target nucleus (209 Bi). All these results are thought as an upper limit for the neutron pre-emission probability, due to the fact that the applied model corresponds to a r.m.s. radius of 5.2 fm for 11 Be neutron halo. We want to thank M. Fukuda, I. Bulboaca and F. Carstoiu for help and

  17. Progress report [Parameters for calculation of nuclear reactions of relevance to non-energy nuclear applications

    Extensive effort has been dedicated towards testing RIPL-2/3 database in practical reaction calculations with EMPIRE code. The three major exercises should be considered in this context: 72 full-scale evaluations of neutron induced reactions performed for ENDF/B-VII.0. These calculations include also three actinides; Low-fidelity covariances project that consisted in calculation of sensitivity matrices to 15 model parameters for 309 targets from 19-F to 209-Bi; Calculations for 654 materials from JEFF-3.1/A (up to 60 MeV) performed on the NNDC cluster. These calculations were testing optical model, levels, masses and gamma segments of the RIPL-2/3 database. EMPIRE specific level densities, which are not included in RIPL-2, but are foreseen to be part of RIPL-3 were used in most of the calculations. No critical problems in the RIPL database were detected in these extensive computations. However, one should bear in mind that the calculations concerned nuclei relatively close to the valley of stability. New Coupled-Channel optical potentials were produced as off-spin of the ENDF/B-VII.0 evaluations. These potentials are derived from the global parameterization of the spherical potential. The explicit inclusion of the coupling within the Coupled-Channels model resulted in the reduction of the imaginary surface term of the potential by about 15%. EMPIRE-specific level densities, which were not part of RIPL-2, are going to be included in the current RIPL-3 release. This particular phenomenological approach to level densities involves BCS model between discrete levels and critical energy Ucrt and the Fermi gas approach above. In the latter one the spin distribution is obtained through subtracting rotational energy, thus reducing thermal energy available for intrinsic excitations. The rotational energies are estimated using spin and temperature dependent moments of inertia that effect also rotational enhancement factor. Collective (rotational and vibrational) enhancement

  18. Cold Fusion Production and Decay of Neutron-Deficient Isotopes of Dubnium and Development of Extraction Systems for Group V Elements

    Gates, Jacklyn M. [Univ. of California, Berkeley, CA (United States)

    2008-07-31

    Excitation functions for the 1n and 2n exit channels of the 208Pb(51V,xn)259-xDb reaction were measured. A maximum cross section of the 1n exit channel of 2070$+1100\\atop{-760}$ pb was measured at an excitation energy of 16.0 ± 1.8 MeV. For the 2n exit channel, a maximum cross section of 1660$+450\\atop{-370}$ pb was measured at 22.0 ± 1.8 MeV excitation energy. The 1n excitation function for the 209Bi(50Ti,n)258Db reaction was remeasured, resulting in a cross section of 5480$+1730\\atop{-1370}$ pb at an excitation energy of 16.0 ± 1.6 MeV. Differences in cross section maxima are discussed in terms of the fusion probability below the barrier. The extraction of niobium (Nb) and tantalum (Ta) from hydrochloric acid and mixed hydrochloric acid/lithium chloride media by bis(2-ethylhexyl) hydrogen phosphate (HDEHP) and bis(2-ethylhexyl) hydrogen phosphite (BEHP) was studied. The goal of the experiments was to find a system that demonstrates selectivity among the members of group five of the Periodic Table and is also suitable for the study of dubnium (Db, Z = 105). Experiments with niobium and tantalum were performed with carrier (10-6 M), carrier free (10-10 M) and trace (10-16 M) concentrations of metal using hydrochloric acid solution with concentrations ranging from 1 - 11 M. The extraction of niobium and tantalum from mixed hydrochloric acid/lithium chloride media by HDEHP and BEHP as a function of hydrogen ion (H+) concentration was also investigated. The data obtained are used as the basis to discuss the speciation of niobium and tantalum under the conditions studied and to evaluate possible extraction mechanisms. The 74Se(18O,p3n)88gNb excitation function was measured to determine the best energy for producing the 88Nb used in chemistry experiments. A maximum cross section of 495 +- 5 mb was observed at an 18O energy of 74.0 Me

  19. Nuclear reactions with radioactive and stable beams (Part II); Reacciones nucleares con haces radiactivos y estables (Parte II)

    Aguilera R, E.F.; Martinez Q, E.; Gomez C, A.; Lizcano, D. [ININ, 52045 Ocoyoacac, Estado de Mexico (Mexico)

    2005-12-15

    At the present time there is a great interest at world level in experiments, with accelerated nuclei of short half life. The dispersion, fusion, transfer and break processes in the interaction of weakly light projectiles bounded with targets of Z great its have been object of intense recent investigation, at world level. Our group, in collaboration with the University of Notre Dame, it has measured and analyzed these processes for weakly bound systems as: {sup 6}He + {sup 209}Bi, {sup 8}Li + {sup 208}Pb, {sup 10}Be + {sup 208}Pb. On the other hand a research line that has wakened up great interest, it is that of studies of resonant reactions using the Inverse Kinematics technique with thick targets. The use of this technique allows to measure an entire excitation function with a single bombardment. Our group has carried out, in the ININ, preliminary bombardments for the system {sup 12}C + {sup 4}He. This allowed to establish the feasibility of implementing this technique in our Laboratory. The application of this and other techniques to different systems like {sup 18}O + {sup 4}He, {sup 12}C + {sup 12}C, {sup 12}C + {sup 16}O, {sup 16}O + {sup 16}O, it opens the possibility to measure the fusion of these systems at very low energy and to deepen in the knowledge of the nuclear structure and the nuclear astrophysics. In this technical report, the activities carried out by our group during the second stage of this project, considered for 2005 are described. Also in that year, our group carries out a research stay in the University of Notre Dame, during this stay, the angular distribution of the projectiles of {sup 8}B dispersed in an enriched target of {sup 58}Ni was measured. The same as in the previous experiments, in this occasion it was also possible to measure those angular distributions of the projectiles of {sup 7}Be and {sup 6}Li dispersed in this same target. In this same one our stay group participates in other three experiments proposed by collaborators of

  20. Monte Carlo based weighting functions in neutron capture measurements

    data, e.g. 209Bi. (authors)

  1. Nuclear reactions with radioactive and stable beams (Part II)

    At the present time there is a great interest at world level in experiments, with accelerated nuclei of short half life. The dispersion, fusion, transfer and break processes in the interaction of weakly light projectiles bounded with targets of Z great its have been object of intense recent investigation, at world level. Our group, in collaboration with the University of Notre Dame, it has measured and analyzed these processes for weakly bound systems as: 6He + 209Bi, 8Li + 208Pb, 10Be + 208Pb. On the other hand a research line that has wakened up great interest, it is that of studies of resonant reactions using the Inverse Kinematics technique with thick targets. The use of this technique allows to measure an entire excitation function with a single bombardment. Our group has carried out, in the ININ, preliminary bombardments for the system 12C + 4He. This allowed to establish the feasibility of implementing this technique in our Laboratory. The application of this and other techniques to different systems like 18O + 4He, 12C + 12C, 12C + 16O, 16O + 16O, it opens the possibility to measure the fusion of these systems at very low energy and to deepen in the knowledge of the nuclear structure and the nuclear astrophysics. In this technical report, the activities carried out by our group during the second stage of this project, considered for 2005 are described. Also in that year, our group carries out a research stay in the University of Notre Dame, during this stay, the angular distribution of the projectiles of 8B dispersed in an enriched target of 58Ni was measured. The same as in the previous experiments, in this occasion it was also possible to measure those angular distributions of the projectiles of 7Be and 6Li dispersed in this same target. In this same one our stay group participates in other three experiments proposed by collaborators of other institutions (University of Notre Dame, University of Sao Paulo), where the products of the reactions 6Li, 7Be and

  2. Nucleon-induced fission at intermediate energies

    The absence of a satisfactory theoretical description to predict isotope yields as well as the need for experimental fragment mass and charge distributions at intermediate-energies form the motivation of this work. Like the objects under study, the research presented in this thesis consists two main parts. Part 1 concerns an activation experiment that has been performed at the 'Kernfysisch Versneller Instituut' (Nuclear Physics Accelerator Institute) in Groningen, Netherlands, using the AGOR cyclotron. Fission product yields have been measured resulting from 190 MeV proton-induced fission of natW, 197Au, natPb, 208Pb and 232Th. In Chapter 2 the experimental set up is discussed, followed in Chapter 3 by a description of the data analysis. The results on the reconstructed mass yields and the total fission cross sections are presented in Chapter 4. Part 2 is of a theoretical nature. The objective is to compute fission product mass yields from intermediate-energy nucleon-induced reactions. In the approach presented here, two stages can be distinguished. In the first stage the fission cross section is determined for the various fissioning isotopes as a function of their excitation energy in competition with other processes like pre-equilibrium decay and particle evaporation. ALICE-91 is a nuclear reaction code that takes care of this first stage. The second stage consists of constructing the total fission-fragment mass and charge distributions from the different contributions of all the equilibrated fissioning systems. Hence, a model is needed that gives a prediction for the fission-product mass yields in a large range of mass, charge, and excitation energy of the fissioning nucleus. For this purpose, the multi-modal random neck-rupture model by Brosa is extended with temperature-dependent shell and pairing corrections and a temperature-dependent LDM. The combination of ALICE-91 and the modified Brosa approach is used for the analysis of the experiments given in the

  3. Measurements of 186Re production cross section induced by deuteron on tungsten target at ARRONAX facility

    Full text of publication follows. The ARRONAX cyclotron [Ref.1], acronym for 'Accelerator for Research in Radiochemistry and Oncology at Nantes Atlantique' is a new facility installed in Nantes, France. A dedicated program has been launched on production of innovative radionuclides for PET imaging and for β- and α targeted radiotherapy using proton or α particle. Since the accelerator is also able to deliver deuteron beams up to 35 MeV, we have reconsidered the possibility to use them to produce medical isotopes. Indeed, in some cases, the use of deuterons allows higher production yield than protons. In this study, we have focused on 186Re production using deuteron. This radionuclide is a β- emitter which has chemical properties close to the widely used 99mTc and has been used in clinical trials for palliation of painful bone metastases resulting from prostate and breast cancer [Ref.2]. Production cross section has been measured between 9 and 23 MeV using the ARRONAX deuteron beam and the stacked-foil technique [Ref.3]. A novelty in our work is the use of natTi monitor foils behind each natW target foil in order to record efficiently the deuteron incident flux and energies all over the stack relying on the IAEA recommended cross section [Ref.4] of the natTi(d,x)48V reaction. Typical experimental conditions consist in an irradiation time of 30 minutes in air with a beam intensity of 100 nA. Activity measurements are made using gamma spectrometry. Isotope of interest and contaminants created during irradiation are measured since a good optimization process is supposed to find the best compromise between production yield and purity of the final product. Our new sets of data will be compared with the existing ones [Refs.5, 6] and with results given by TALYS code calculations [Ref.7]. Production yield will be determined and the best production route, using proton or deuteron, identified. References: [1] F.Haddad et al., Eur. J. Med. Mol. Imaging (2008) 35

  4. Rapid analytical technique to identify alpha emitting isotopes in water, air-filters, urine, and solid matrices using a Frisch Grid detector.

    Scarpitta, Salvatore C; Miltenberger, Robert P; Gaschott, Robert; Carte, Nina

    2003-04-01

    A 5-inch-diameter Frisch Grid gas-proportional ionization chamber was utilized at Brookhaven National Laboratory (BNL) to rapidly characterize and quantify alpha-emitting actinides in unprocessed water, soil, air-filter, urine, and solid matrices. Instrument calibrations for the various matrices were performed by spiking representative samples with National Institute of Standards and Technology traceable isotopes of 230Th, 232U, 236Pu, and 243Am. Detection efficiencies were typically 15-20% for solid matrices (soil, concrete, filters, dry urine) and 45% for mass-less water samples. Instrument background over a 512-channel alpha-energy range of 3-8 MeV is very low at 0.01 cps. At optimum efficiency, minimum detectable levels of 0.56 mBq Kg(-1), 74 mBq L(-1) and 14.8 mBq filter(-1) were achievable for 40 x 10(-6) Kg soil, 1 x 10(-3) L tap water (or urine), and 4.5 cm diameter air-filter samples, respectively, each counted for 60 min. Data and spectra are presented showing the quality of results obtained using untreated samples obtained from the BNL Graphite Research Reactor Decommissioning Project. These samples contained Bq to MBq per gram amounts of (239,240)Pu, 241Am, and/or (234,235/238)U (as well as other beta/gamma emitters). Data and spectra are also presented for a very finely pulverized and homogeneous U.S. DOE/RESL soil reference standard (spiked with 239Pu, 241Am, and 233U) that was used to assess precision, accuracy, and reproducibility. Although this technique has its limitations, the advantages are (1) minimal sample preparation, (2) no separation chemistry required, (3) no chemical or hazardous waste generated, and (4) ability to immediately characterize and quantify alpha-emitting nuclides in most matrices. The benefits of this technique to the BNL/DOE Project Managers were rapid (1-2 d) turn-around times coupled with significant cost savings, as compared to commercial off-site analyses. PMID:12705448

  5. Determination of 236U and transuranium elements in depleted uranium ammunition by α-spectrometry and ICP-MS

    It is well known that ammunition containing depleted uranium (DU) was used by NATO during the Balkan conflict. To evaluate the origin of DU (the enrichment of natural uranium or the reprocessing of spent nuclear fuel) it is necessary to directly detect the presence of activation products (236U, 239Pu, 240Pu, 241Am, and 237Np) in the ammunition. In this work the analysis of actinides by α-spectrometry was compared with that by inductively coupled plasma mass spectrometry (ICP-MS) after selective separation of ultratraces of transuranium elements from the uranium matrix. 242Pu and 243Am were added to calculate the chemical yield. Plutonium was separated from uranium by extraction chromatography, using tri-n-octylamine (TNOA), with a decontamination factor higher than 106; after elution plutonium was determined by ICP-MS (239Pu and 240Pu) and α-spectrometry (239+240Pu) after electroplating. The concentration of Pu in two DU penetrator samples was 7 x 10-12 g g-1 and 2 x 10-11 g g-1. The 240Pu/239Pu isotope ratio in one penetrator sample (0.12±0.04) was significantly lower than the 240Pu/239Pu ratios found in two soil samples from Kosovo (0.35±0.10 and 0.27±0.07). 241Am was separated by extraction chromatography, using di(2-ethylhexyl)phosphoric acid (HDEHP), with a decontamination factor as high as 107. The concentration of 241Am in the penetrator samples was 2.7 x 10-14 g g-1 and -15 g g-1. In addition 237Np was detected at ultratrace levels. In general, ICP-MS and α-spectrometry results were in good agreement.The presence of anthropogenic radionuclides (236U, 239Pu,240Pu, 241Am, and 237Np) in the penetrators indicates that at least part of the uranium originated from the reprocessing of nuclear fuel. Because the concentrations of radionuclides are very low, their radiotoxicological effect is negligible. (orig.)

  6. The OSMOSE program for the qualification of integral cross sections of actinides: Preliminary results in a PWR-UOx spectrum

    The need for improved nuclear data for minor actinides has been stressed by various organizations throughout the world - especially for studies relating to plutonium management, waste incineration, transmutation of waste, and Pu burning in future nuclear concepts. Several international programs have indicated a strong desire to obtain accurate integral reaction rate data for improving the major and minor actinides cross sections. Data on major actinides (i.e. 235U, 236U, 238U, 239Pu, 240Pu, 241Pu, 242Pu and 241Am) are reasonably well-known and available in the Evaluated Nuclear Data Files (JEFF, JENDL, ENDF-BX However information on the minor actinides (i.e. 232Th, 233U, 237Np, 238Pu, 242Am, 243Am, 243Cm, 235Cm, 244Cm, 245Cm, 246Cm and 247Cm) is less well-known and considered to be relatively poor in some cases, having to rely on model and extrapolation of few data points. In this framework, the ambitious OSMOSE program between the Commissariat a l'Energie Atomique (CEA), Electricite de France (EDF) and the U.S. Dept. of Energy (DOE) has been undertaken with the aim of measuring the integral absorption rate parameters of actinides in the MINERVE experimental facility located at the CEA Cadarache Research Center. The OSMOSE Program (Oscillation in Minerve of isotopes in 'Eupraxic' Spectra) includes a complete analytical program associated with the experimental measurement program and aims at understanding and resolving potential discrepancies between calculated and measured values. In the OSMOSE program, the reactivity worth of samples containing separated actinides are measured in different neutron spectra using an oscillation technique with an overall expected accuracy better than 3%. Reactivity effects of less than 10 pcm (0.0001 or approximately 1.5 cents) are measured and compared with calibrations to determine the differential reactivity-worth of the individual samples. The first experimental results were obtained with a very good reproducibility in 2005 and

  7. Transuranium Processing Plant semiannual report of production, status, and plans for period ending June 30, 1977

    King, L.J.; Bigelow, J.E.; Collins, E.D.

    1977-12-01

    During the period January 1, 1977, through June 30, 1977, the following amounts of transuranium elements were recovered from 12 irradiated HFIR targets: 0.1g /sup 243/Am, 21g /sup 244/Cm, 29.5 mg /sup 249/Bk, 288 mg /sup 252/Cf, 1.48 mg /sup 253/Es, and 0.7 pg /sup 257/Fm. One batch of high-purity /sup 248/Cm (approximately 50 mg) was separated from /sup 252/Cf. Twenty-three shipments were made from TRU during the period; recipients and the amounts of nuclides are tabulated. Five HFIR targets, each containing 8 to 9 g of curium, were fabricated. During the next 18 months, we expect to obtain totals of 92 mg of /sup 249/Bk, 910 mg of /sup 252/Cf, 3.8 mg of /sup 253/Es (in a mixture of isotopes), 615 ..mu..g of high-purity /sup 253/Es, and 1.6 pg of /sup 257/Fm; we also expect to make available 250 mg of high-purity /sup 248/Cm. No process or equipment changes were made during this report period. Five neutron sources were fabricated during this report period, bringing the total fabricated to date to 97. Two sources that had previously been returned to TRU were reassigned. Special projects included the following: (1) the enrichment of the /sup 244/Pu concentration in 100 mg of plutonium by irradiation to burn out the lighter isotopes, (2) the separation of 245 pg of /sup 254/Cf from 39-hr /sup 254m/Es that was produced by irradiation of 5 ..mu..g of /sup 253/Es, and (3) an experimental separation of cerium from the other rare-earth elements in a TRU process waste solution. The values that we are currently using for transuranium element decay data and for cross-section data in planning irradiation-processing cycles, calculating production forecasts, and assaying products are tabulated in the Appendix.

  8. R and D for actinide partitioning and recovery of valuables from high level waste using radiotracers

    In the context of growing world population with rapidly increasing energy needs and the threat of global warming due to CO2 emission (caused by fossil fuel burning), the nuclear energy may be an attractive option particularly in the developing countries. Recycling of fuel is a unique feature of nuclear power technology which makes it a favourable choice with respect to conservation of energy resources. Steady growth of global fuel reprocessing activities (6000 tHM/annum) implies a vital role of separation science in developing efficient procedures for the separation and purification of actinides and in devising safe procedures for the management of nuclear waste arising at different stages of the PUREX process. High Level Waste (HLW) comprising of the concentrate of the raffinate of the co-extraction cycle (with over 95% of the total radioactivity produced in the burn up process in reactor) need to be isolated from the biosphere. There is a consensus among the waste management technologists that the safest route to achieve this, is to deposit it in a stable geological formation after it's immobilization in suitable glass/Synroc matrix. It ensures that any risk from exposure due to accidental intervention or natural disturbance is minimized. Risk perception is essentially due to the large radiological toxicity associated with alpha emitters like 237Np, 241Am, 243Am and 245Cm. Isotopes of Pu (left unrecovered) present in HLW also contribute towards radiological toxicity. In view of the high cost involved and the need for continuous surveillance, several countries are considering modifying their reprocessing schemes to partition (isolate) long-lived actinides from HLW. Since the volume of the actinide oxides (which retain major fraction of the radio toxicity of HLW) is significantly lower as compared to the other metal oxides present in HLW, such an approach is expected to reduce the cost of immobilization as well as of disposal (in geological repository) and

  9. Influences of different environmental parameters on the sorption of trivalent metal ions on bentonite: batch sorption, fluorescence, EXAFS and EPR studies.

    Verma, P K; Pathak, P N; Mohapatra, P K; Godbole, S V; Kadam, R M; Veligzhanin, A A; Zubavichus, Y V; Kalmykov, S N

    2014-04-01

    The presence of long-lived radionuclides in natural aquatic systems is of great environmental concern in view of their possible migration into biospheres of mankind. Trivalent actinides such as (241/243)Am can contribute a great deal to radioactivity for several thousand years. This migration is significantly influenced by various factors such as pH, complexing ions present in aquatic environments, and the sorption of species involving radionuclides by sediments around water bodies. Clay minerals such as bentonite are known to be highly efficient in radionuclide retention and hence are suitable candidates for backfill materials. This study presents experimental results on the interaction of Eu(iii) and Gd(iii) (chemical analogs of Am(iii) and Cm(iii)) with bentonite clay under varying experimental conditions of contact time, pH, and the presence of complexing anions such as humic acid (HA) and citric acid (cit). The sorption of HA on bentonite decreased with increasing the pH from 2 to 8, which was attributed to electrostatic interactions between HA and the bentonite surfaces. The sorption of Eu(iii) on bentonite colloids showed marginal variation with pH (>95%). However, a decrease in Eu(iii) sorption was observed in the presence of HA beyond pH 5 due to the increased aqueous complexation of Eu(iii) with deprotonated HA in the aqueous phase. The complexation of Eu(iii) with citrate ions was studied using Time Resolved Laser induced Fluorescence Spectroscopy (TRLFS) to explain the sorption data. Extended X-ray absorption fine structure (EXAFS) and electron paramagnetic resonance (EPR) investigations were carried out to understand the local chemical environment surrounding Eu(iii) and Gd(iii) (EPR probe) sorbed on bentonite under different experimental conditions. Surface complexation modelling shows the predominant formation of ≡XOEu(+2) (silanol) up to pH < 7, and beyond which ≡YOEu(OH)(+) (aluminol) is responsible for the quantitative sorption of Eu(iii) onto

  10. Phytoremediation: role of terrestrial plants and aquatic macrophytes in the remediation of radionuclides and heavy metal contaminated soil and water.

    Sharma, Sunita; Singh, Bikram; Manchanda, V K

    2015-01-01

    Nuclear power reactors are operating in 31 countries around the world. Along with reactor operations, activities like mining, fuel fabrication, fuel reprocessing and military operations are the major contributors to the nuclear waste. The presence of a large number of fission products along with multiple oxidation state long-lived radionuclides such as neptunium ((237)Np), plutonium ((239)Pu), americium ((241/243)Am) and curium ((245)Cm) make the waste streams a potential radiological threat to the environment. Commonly high concentrations of cesium ((137)Cs) and strontium ((90)Sr) are found in a nuclear waste. These radionuclides are capable enough to produce potential health threat due to their long half-lives and effortless translocation into the human body. Besides the radionuclides, heavy metal contamination is also a serious issue. Heavy metals occur naturally in the earth crust and in low concentration, are also essential for the metabolism of living beings. Bioaccumulation of these heavy metals causes hazardous effects. These pollutants enter the human body directly via contaminated drinking water or through the food chain. This issue has drawn the attention of scientists throughout the world to device eco-friendly treatments to remediate the soil and water resources. Various physical and chemical treatments are being applied to clean the waste, but these techniques are quite expensive, complicated and comprise various side effects. One of the promising techniques, which has been pursued vigorously to overcome these demerits, is phytoremediation. The process is very effective, eco-friendly, easy and affordable. This technique utilizes the plants and its associated microbes to decontaminate the low and moderately contaminated sites efficiently. Many plant species are successfully used for remediation of contaminated soil and water systems. Remediation of these systems turns into a serious problem due to various anthropogenic activities that have

  11. Importance of neutron cross-sections for transmutation

    Accurate neutron cross-section data is fundamental to the reliable design of any transmutation device, and, in particular, of an accelerator-driven system (ADS). Calculations of the behaviour of the core depend strongly on the cross-section data: parameters such as the multiplication coefficient, power densities or reactivity may vary significantly depending on the nuclear-data (ND) library used. These potential discrepancies justify the need to improve the present data for several isotopes and reaction channels, for a wide range of neutron energies from thermal to high-energy. This paper follows on from work performed in the context of the nTOF-ND-ADS project of the EURATOM 5th framework program, where a preliminary analysis of the effects of different cross-section data was carried out using the Monte Carlo code package FLUKA-EAMC. That study was based on the Pb-Bi cooled 80 MWth energy-amplifier prototype, and included comparison of parameters such as source multiplication coefficient ksrc, neutron spectra, neutron balance and one-group cross-sections for different isotopes using different nuclear-data evaluations. The present work expands this analysis to other isotopes of interest such as 233U, 243Am, 244,245Cm and the long-lived fission fragments (LLFFs) 99Tc and 129I. A direct comparison of nuclear-data libraries to indicate the spread between values was performed. The paper also extends the sensitivity analysis of the parameters mentioned above to moderated systems, such as TRADE (triga accelerator-driven experiment): a 1 MW triga reactor coupled with a 110-140 MeV-2 mA proton cyclotron. Study of the discrepancies in the thermal and epithermal regions is essential for the design of systems for the transmutation of LLFF (transmutation by adiabatic resonance crossing, TARC) and also important for minor actinides (MAs) for which sub-threshold fission should not be neglected. These studies highlight the relative importance of different isotopes and assess the

  12. Concentration and speciation of plutonium, americium, uranium, thorium, potassium and 137Cs in a venice canal sediment sample

    Testa, C.; Desideri, D.; Guerra, F.; Meli, M. A.; Roselli, C.; Degetto, S.

    1999-01-01

    A sequential extraction method consisting of six operationally-defined fractions has been developed for determining the geochemical partitioning of natural (U, Th, 40K) and antropogenic (Pu, Am, 137Cs) radionuclides in a 40-50 cm deep sediment sample collected in a Venice canal. Extraction chromatography with Microthene-TOPO (U, Th), Microthene-TNOA (Pu) and Microthene-HDEHP (Am) column was used for the chemical separation of a single radionuclide; the final recoveries were calculated by adding 236U, 229Th, 242Pu and 243Am as the yield tracers. After electrodeposition the alpha spectrometry was carried out. 137Cs and 40K were measured by gamma spectrometry. The total concentrations in the wet sample (Bq/kgd), obtained by a complete disgregation of the matrix by wet and dry treatment, were the following: 239+240Pu=1.03±0.07, 238Pu=0.022±0.005, 241Am=0.337±0.027, 137Cs=9.78±0.78, 238U=28.84±1.62, 232Th=21.42±1.93, 40K=376.05±12.78. The mean ratio 238Pu/239+240Pu (0.02) shows a contamination due essentially to fall-out and U and Th alpha spectra indicate the natural origin of two elements. The absence of 134Cs in the sample proves that at 40-50 cm depth the sediment was not affected by the Chernobyl fall-out. As far as the speciation is concerned the following fractions were considered: water soluble, carbonates, Fe-Mn oxides, organic matter, acid soluble, residue. Pu (˜67%) an Am (˜95%) were present principally in the carbonate fraction; U was more distributed and about 30% and 45% appeared in the carbonate fraction and in the residue respectively; the majority of Th was present in the residue (˜60%); 40K was totally present in the residue; finally 137Cs was found mostly in the acid soluble fraction (˜53%) and in the residue (˜47%). Some stable elements (Fe, Mn, Al, Ti, Ca, Pb, Ba) were also determined in the different fractions to get more information about the chemical association of the single radionuclides.

  13. The OSMOSE Experimental Program for the qualification of integral cross sections of actinides

    The need of better nuclear data on minor actinides has been stressed by various organizations throughout the world. It especially deals with the studies on plutonium management and waste incineration in existing systems and transmutation of waste or Pu burning in future nuclear concepts. To address this issue, a Working Party of the OECD has been concerned with identifying these needs and has produced a detailed High Priority Request List for Nuclear Data. The first step in obtaining better nuclear data consists in measuring accurate integral data and comparing them to integrated energy dependent data: this comparison provides a direct assessment of the effect of deficiencies in the differential data. Several international programs have indicated a strong desire to obtain accurate integral reaction rate data for improving the major and minor actinides cross sections. Data on major actinides (i.e. 235U, 236U, 238U, 239Pu, 240Pu, 241Pu, 242Pu and 241Am) are reasonably well-known and available in the Evaluated Nuclear Data Files (JEFF, JENDL, ENDF-B). However information on the minor actinides (i.e. 232Th, 233U, 237Np, 238Pu, 242Am, 243Am, 242Cm, 243Cm, 244Cm, 245Cm, 246Cm and 247Cm) is less well-known and considered to be relatively poor in some cases, having to rely on model and extrapolation of few data points. In this framework, the ambitious OSMOSE program between the Commissariat a l'Energie Atomique (CEA), Electricite de France (EDF) and the U.S. Department of Energy (DOE) has been undertaken with the aim of measuring the integral absorption rate parameters of actinides in the MINERVE experimental facility located at the CEA Cadarache Research Center. The OSMOSE Program (Oscillation in Minerve of isOtopes in 'Eupraxic' Spectra) includes a complete analytical program associated with the experimental measurement program and aims at understanding and resolving potential discrepancies between calculated and measured values. The OSMOSE program began in 2005 and will

  14. Type Ia Supernovae as Sites of the p-process: Two-dimensional Models Coupled to Nucleosynthesis

    Travaglio, C.; Röpke, F. K.; Gallino, R.; Hillebrandt, W.

    2011-10-01

    Beyond Fe, there is a class of 35 proton-rich nuclides, between 74Se and 196Hg, called p-nuclei. They are bypassed by the s and r neutron capture processes and are typically 10-1000 times less abundant than the s- and/or r-isotopes in the solar system. The bulk of p-isotopes is created in the "gamma processes" by sequences of photodisintegrations and beta decays in explosive conditions in both core collapse supernovae (SNe II) and in Type Ia supernovae (SNe Ia). SNe II contribute to the production of p-nuclei through explosive neon and oxygen burning. However, the major problem in SN II ejecta is a general underproduction of the light p-nuclei for A SN Ia delayed detonation model as well as pure deflagration models. The white dwarf precursor is assumed to have reached the Chandrasekhar mass in a binary system by mass accretion from a giant/main-sequence companion. We use enhanced s-seed distributions, with seeds directly obtained from a sequence of thermal pulse instabilities both in the asymptotic giant branch phase and in the accreted material. We apply the tracer-particle method to reconstruct the nucleosynthesis by the thermal histories of Lagrangian particles, passively advected in the hydrodynamic calculations. For each particle, we follow the explosive nucleosynthesis with a detailed nuclear reaction network for all isotopes up to 209Bi. We select tracers within the typical temperature range for p-process production, (1.5-3.7) × 109 K, and analyze in detail their behavior, exploring the influence of different s-process distributions on the p-process nucleosynthesis. In addition, we discuss the sensitivity of p-process production to parameters of the explosion mechanism, taking into account the consequences on Fe and alpha elements. We find that SNe Ia can produce a large amount of p-nuclei, both the light p-nuclei below A = 120 and the heavy-p nuclei, at quite flat average production factors, tightly related to the s-process seed distribution. For the first

  15. Nuclear Magnetic Resonance Studies of Topological Insulators and Materials with a Large Spin-Orbit Coupling

    Nisson, David Mark

    Nuclear magnetic resonance (NMR) studies were performed on large single crystals of the topological insulator materials Bi2Se 3 and Bi2Te2Se, as well as the doped topological superconductor candidate CuxBi2Se3. Samples were grown using the facilities of the Department of Physics at the University of California, Davis. Bi2Se3 crystals were grown under different conditions to control the intrinsic concentration of carrier electrons, which arises from an inherent tendency for Se vacancies to form during growth. The electrical properties, including carrier concentration of each sample, were then characterized by electrical transport measurements. Frequency swept 209Bi spectra for these samples reveal a relatively weak electric field gradient producing a splitting of about 160 kHz, and a shift that depends on the carrier concentration. The correlation between shift and intrinsic carrier concentration determines the hyperfine coupling strength between the Bi nuclei and the bulk carrier electrons. The spin-lattice relaxation rate T1--1 was also measured as a function of temperature. It is mostly temperature-independent, indicating that in samples of Bi2Se3 grown by the Bridgman method, relaxation may occur by spin diffusion to impurities rather than by previously reported mechanisms. Nuclear magnetic resonance measurements were also performed on single crystals of Bi2Se3 as a function of the angle between the field and the c-axis of the crystal lattice. These frequency-swept measurements revealed anomalous behavior that deviated significantly from what would be expected of the angular dependence of the resonance spectrum. Powder samples reveal spectra that differ still from the expectations from the single-crystal data. These phenomena are explained in part by the fact that the nutation time tpi/2) depends on the angle as a result of overlap between the central and satellite transitions, but may in addition be the result of screening of the radiofrequency field by the

  16. Importance of lifetime effects in breakup and suppression of complete fusion in reactions of weakly bound nuclei

    Cook, K. J.; Simpson, E. C.; Luong, D. H.; Kalkal, Sunil; Dasgupta, M.; Hinde, D. J.

    2016-06-01

    Background: Complete fusion cross sections in collisions of light weakly bound nuclei and high-Z targets show suppression of complete fusion at above-barrier energies. This has been interpreted as resulting from the breakup of the weakly bound nucleus prior to reaching the fusion barrier, reducing the probability of complete charge capture. Below-barrier studies of reactions of 9Be have found that the breakup of 8Be formed by neutron stripping dominates over direct breakup and that transfer-triggered breakup may account for the observed suppression of complete fusion. Purpose: This paper investigates how the above conclusions are affected by lifetimes of the resonant states that are populated prior to breakup. If the mean life of a populated resonance (above the breakup threshold) is much longer than the fusion time scale, then its breakup (decay) cannot suppress complete fusion. For short-lived resonances, the situation is more complex. This work explicitly includes the mean life of the short-lived 2+ resonance in 8Be in classical dynamical model calculations to determine its effect on energy and angular correlations of the breakup fragments and on model predictions of suppression of cross sections for complete fusion at above-barrier energies. Method: Previously performed coincidence measurements of breakup fragments produced in reactions of 9Be with 144Sm, 168Er, 186W, 196Pt, 208Pb, and 209Bi at energies below the barrier have been reanalyzed using an improved efficiency determination of the BALiN detector array. Predictions of breakup observables and of complete and incomplete fusion at energies above the fusion barrier are then made using the classical dynamical simulation code platypus, modified to include the effect of lifetimes of resonant states. Results: The agreement of the breakup observables is much improved when lifetime effects are included explicitly. Sensitivity to subzeptosecond lifetime is observed. The predicted suppression of complete fusion

  17. Gamma-Ray Library and Uncertainty Analysis: Passively Emitted Gamma Rays Used in Safeguards Technology

    can be especially challenging to identify. The super cooled detectors have a marked improvement in energy resolution, allowing the possibility of deconvolution of mixtures of gamma rays that was unavailable with high purity germanium detectors. Isotopic analysis codes require libraries of gamma rays. In certain situations, isotope identification can be made in the field, sometimes with a short turnaround time, depending on the choice of detector and software analysis package. Sodium iodide and high purity germanium detectors have been successfully used in field scenarios. The newer super cooled detectors offer dramatically increased resolution, but they have lower efficiency and so can require longer collection times. The different peak shapes require software development for the specific detector type and field application. Libraries can be tailored to specific scenarios; by eliminating isotopes that are certainly not present, the analysis time may be shortened and the accuracy may be increased. The intent of this project was to create one accurate library of gamma rays emitted from isotopes of interest to be used as a reliable reference in safeguards work. All simulation and spectroscopy analysis codes can draw upon this best library to improve accuracy and cross-code consistency. Modeling codes may include MCNP and COG. Gamma-ray spectroscopy analysis codes may include MGA, MGAU, U235 and FRAM. The intent is to give developers and users the tools to use in nuclear energy safeguards work. In this project, the library created was limited to a selection of actinide isotopes of immediate interest to reactor technology. These isotopes included 234-238U, 237Np, 238-242Pu, 241,243Am and 244Cm. These isotopes were examined, and the best of gamma-ray data, including line energies and relative strengths were selected.

  18. Determination of actinides by alpha spectrometric methods

    attributes of mass activities of radionuclides in oyster mushroom's sporocarps compared to their sub-base. We used two methods to separate the monitored radionuclides in a radiochemical analyse. The first of them was an extraction fluid - fluid with Aliquat-336 to separate Pu and TOPO to separate Am. The second method was a proceeding modified by us and utilizing principles of an extraction chromatography with TRU Resin and DGA Resin sorbents made by Eichrom Company. An effectivity and a suitability of both applied methods were monitored following the attributes of radiochemical extractions used in tracer's radionuclides 242Pu a 243Am in this particular type of environmental samples. The reliability of the modified methodology, in accordance to selected criteria for validation of analytical method, was proved by comparison of both above mentioned methods. material delivered from IAEA, which presented a soil sample with code identification Soil IAEA-375. The obtained values of mass activities of 239+240Pu, 239Pu and 241Am used in reference material, demonstrated a conformity with IAEA values, whereby we fulfilled one of the significant conditions of validate process. At the end of this thesis we applied the modified method of extraction chromatography with UTEVA Resin sorbent to define mass activities of uranium on soil and water samples where we monitored attributes of radiochemical extractions of 232U tracer's radionuclide as the criteria of utilizability. The reliability of our modified method was verified by participation in international interlaboratory comparative proficiency tests and our results were in accordance with results of the reference laboratory. It means also a fulfilment of notable standard of the validate process. The results of all realized experimentations of radionuclides separation whether by extraction fluid - fluid or by extraction chromatography were determined by alpha-spectrometric measurements. (author)

  19. ZZ SINEX, 100 Neutron-Group Neutron Reaction Cross-Section Library from ENDF/B by SUPERTOG for ANISN

    , Cl, K, Ca, V, Cr, 55-Mn, Fe, 59-Co, Ni, Cu, 63-Cu, 65-Cu, Nb, Mo, 107-Ag, 109-Ag, 135-Xe, 133-Cs, 149-Sm, 151-Eu, 153-Eu, Gd, 164-Dy, 175-Lu, 176-Lu, 181-Ta, 182-Ta, 182-W, 183-W, 184-W, 186-W, 185-Re, 187-Re, 197-Au, Pb, 232-Th, 233-Pa, 234-U, 235-U, 238-U, 238-Pu, 239-Pu, 240-Pu, 241-Pu, 242-Pu, 241-Am, 243-Am, and 244-Cm. 2 - Method of solution: DLC-24 was generated by SUPERTOG from nuclear data in either point-by-point or parametric representation as specified by ENDF/B. This data is averaged over each specified group width. For the top 99 groups, the explicit assumption was made that the flux (weighting function) has the shape of a fission spectrum jointed at 0.0674 MeV by a 1/E tail. When resonance data were available, resolved and unresolved resonance contributions were calculated, using the infinite dilution approximation. For the thermal group (group 100), values for all materials except hydrogen were taken from the Maxwellian average values derived from the ENDF/B data. The values for hydrogen are more consistent for hydrogen in water. It should be noted that these thermal group values are in some cases different from values used in the latest version of DLC-2

  20. ZZ DLC-2D/100G, 100 Neutron-Group Cross-Section Library by SUPERTOG Calculation for ANISN, DOT

    1 - Nature of physical problem solved: Format: ANISN, DOT or DTF-4; Number of groups: 100; Nuclides: H, D, He, He-3, Li-6, Li-7, Be-9, B-10, B-11, C-12, N-14, O-16, Na-23, Mg, Al-27, Si, Cl, K, Ca, V, Cr, Mn-55, Fe, Co-59, Ni, Cu, Cu-63, Cu-65, Nb, Mo, Ag-107, Xe-135, Cs-133, Sm-149, Eu-151, Eu-153, Gd, Dy-164, Lu-175, Lu-176, Ta-181, Ta-182, W-182, W-183, W-184, W-186, Re-185, Re-187, Au-197, Pb, Th-232, Pa-233, U-234, U-235, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-243, and Cm-244. Origin: The nuclides in DLC-2 are those which have been released as category I ENDF/B by the National Neutron Cross Section Center, Brookhaven National Laboratory. Weighting spectrum: The explicit assumption was made that the flux has the shape of a fission spectrum joined at 0.0674 MeV by a 1/E tail. Neutron transport calculations can be performed with DLC-2 data. Since the data are intended for use in multigroup discrete-ordinates or Monte Carlo transport codes which treat anisotropic scattering, possible cross section angular expansion is limited only by the options available in the particular code used. Specifically, the retrieval program manipulates DLC-2 such that it conforms to input requirements of the ANISN, DOT, or DTF-4 codes, or any computer code using data in the ANISN or DTF-4 format. The nuclides in DLC-2 are those which have been released as category I ENDF/B by the National Neutron Cross Section Center, Brookhaven National Laboratory. The library contains data for H, D, He, 3-He, 6-Li, 7-Li, 9-Be, 10-B, 11-B, 12-C, 14-N, 16-O, 23-Na, Mg, 27-Al, Si, Cl, K, Ca, V, Cr, 55-Mn, Fe, 59-Co, Ni, Cu, 63-Cu, 65-Cu, Nb, Mo, 107-Ag, 135-Xe, 133-Cs, 149-Sm, 151-Eu, 153-Eu, Gd, 164-Dy, 175-Lu, 176-Lu, 181-Ta, 182-Ta, 182-W, 183-W, 184-W, 186-W, 185-Re, 187-Re, 197-Au, Pb, 232-Th, 233-Pa, 234-U, 235-U, 238-U, 238-Pu, 239-Pu, 240-Pu, 241-Pu, 242-Pu, 241-Am, 243-Am, and 244-Cm. 2 - Method of solution: DLC-2 was generated by SUPERTOG from nuclear data in either point

  1. Gamma-Ray Library and Uncertainty Analysis: Passively Emitted Gamma Rays Used in Safeguards Technology

    Parker, W

    2009-09-18

    streams can be especially challenging to identify. The super cooled detectors have a marked improvement in energy resolution, allowing the possibility of deconvolution of mixtures of gamma rays that was unavailable with high purity germanium detectors. Isotopic analysis codes require libraries of gamma rays. In certain situations, isotope identification can be made in the field, sometimes with a short turnaround time, depending on the choice of detector and software analysis package. Sodium iodide and high purity germanium detectors have been successfully used in field scenarios. The newer super cooled detectors offer dramatically increased resolution, but they have lower efficiency and so can require longer collection times. The different peak shapes require software development for the specific detector type and field application. Libraries can be tailored to specific scenarios; by eliminating isotopes that are certainly not present, the analysis time may be shortened and the accuracy may be increased. The intent of this project was to create one accurate library of gamma rays emitted from isotopes of interest to be used as a reliable reference in safeguards work. All simulation and spectroscopy analysis codes can draw upon this best library to improve accuracy and cross-code consistency. Modeling codes may include MCNP and COG. Gamma-ray spectroscopy analysis codes may include MGA, MGAU, U235 and FRAM. The intent is to give developers and users the tools to use in nuclear energy safeguards work. In this project, the library created was limited to a selection of actinide isotopes of immediate interest to reactor technology. These isotopes included {sup 234-238}U, {sup 237}Np, {sup 238-242}Pu, {sup 241,243}Am and {sup 244}Cm. These isotopes were examined, and the best of gamma-ray data, including line energies and relative strengths were selected.

  2. Study of heavy elements at IMP

    The present status of heavy elements research at IMP (Institute of Modern Physics, Chinese Academy of Science, Lanzhou) is reviewed. Many efforts have been devoted into the stuclies of actinides and of transactinides. Some progresses have been made in synthesis and identification of new nuclides and studies of their exotic decay properties in these regions. The rapid chemical separation procedures have been widely applied when the half-lives of the expected nuclides are long enough. Three new neutron-rich isotopes of 237,238Th, 239Pa were produced by heavy-ion induced multinucleon transfer reaction and fast neutron-induced (n, 2p) reaction. A new neutron-deficient transuranium nuclide 235Am was also produced via proton-induced reaction and identified for the first time by using He-jet transportation, liquid-liquid extraction and x-γ coincidence measurements. The half-life of 235Am was determined to be 15±5 min. The β-delayed fission of 230Ac was observed for the first time and the BDF probability of 230Ac was determined to be (1.19±0.40)x10-8. Two new transactinide nuclides of 259Db and 265Bh were produced successfully via the reactions of 241Am(22Ne, 4n) 259Db and 243Am(26Mg, 4n) 265Bh, respectively at HIRFL (Heavy Ion Research Facility at Lanzhou). The high-radioactive americium targets with thickness of ∼1 mg/cm2 were prepared on 7μm aluminum or 15μm beryllium by molecular platting method at one single cycle. The reaction products were transported and collected using the helium-jet coupling with the rotating wheel apparatus. The identification of 259Db was based on the genetic relationship between the new activity and the known nuclide established by α-recoiled milking measurement. The half-life of 259Db were determined to be 0.5 s and the alpha energy was Ea = 9.47 MeV. Another new isotope 265Bh was identified based on observation of the α-α correlation between the 265Bh and its daughter 261Db and 257Lr nuclei using an improved rotating-wheel system

  3. OREST, LWR Burnup Simulation Using Program HAMMER and ORIGEN

    printer-output. 3 - Restrictions on the complexity of the problem: NEA version is limited for 100 loops, 1000 burnup time-steps and 10 post-irradiation steps. GRS recommends the use of LWR fuels based on oxygen and on the main HAMMER isotopes 235-U, 236-U, 238-U, 237-Np, 238-Pu, 239-Pu, 240-Pu, 241-Pu, 242-Pu, 241-Am and 243-Am. Gadolinium entries should be handled with care if singular positions of Gd-rods in real assemblies are found. Other mixture entries at start of calculation should only be impurities. Cladding should be Zr, Al or stainless steel. Special options for handling other materials can be found in the user description. Activation of structure materials is not calculated. Strong heterogeneous assembly problems outside of the input data processor should be pre-calculated by using more-dimensional codes to achieve a neutron spectra equivalent HAMMER lattice (FEC-method). Coolant pressure, coolant temperatures and coolant steam contents are assumed to be constant during burnup. During each program loop neutron spectra and cross sections are assumed to be constant

  4. ZZ DLC-16 COBB, 123 Neutron-Group Cross-Section Library from ENDF/B for XSDRN Calculation

    1 - Nature of physical problem solved: Format: XSDRN; Number of groups: 123; Nuclides: H, D, He, Be-9, B-10, C-12, O-16, Na-23, Mg, Al-27, Ti, Cr, Mn-55, Fe, Ni, Cu, Cu-63, Cu-65, Nb-93, Mo, Xe-135, Sm-149, Eu-151, Eu-153, Gd, Dy-164, Lu-175, Lu-176, W-182, W-183, W-184, W-186, Re-185, Re-187, Au-197, U-233, U-234, U-235, U-236, U-238, Np-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Am-241, Am-243, and Cm-244. Origin: Mainly ENDF/B; Weighting spectrum: Fast cross sections → 1/E (14 MeV to .414 eV) Thermal cross sections → 1/E (1.86 eV to 0.125 eV) → Maxwell-Boltzmann (0.125 eV to 0.0047 eV). The library is intended to be a source of evaluated data for the cross section preparation code XSDRN. It supplements, rather than replaces, the existing XSDRN master library which is distributed with the code package. The library contains data for H, D, He, 9-Be, 10-B, 12-C, 16-O, 23-Na, Mg, 27-Al, Ti, Cr, 55-Mn, Fe, Ni, Cu, 63-Cu, 65-Cu, 93-Nb, Mo, 135-Xe, 149-Sm, 151-Eu, 153-Eu, Gd, 164-Dy, 175-Lu, 176-Lu, 182-W, 183-W, 184-W, 186-W, 185-Re, 187-Re, 197-Au, 233-U, 234-U, 235-U, 236-U, 238-U, 237-Np, 238-Pu, 239-Pu, 240-Pu, 241-Pu, 242-Pu, 241-Am, 243-Am, and 244-Cm. 2 - Method of solution: The library contains ENDF/B version 2 cross sections processed through several steps (primarily by SUPERTOG) into the standard XSDRN 123-group energy structure. These steps are - (a) process fast cross sections with SUPERTOG into standard GAM-2 energy structure (14 MeV to 0.414 eV), using a 1/E weighting function, and produce a GAM-2 tape. (This step was performed by R. Q. Wright, Math Div., ORNL). (b) Process thermal cross sections with SUPERTOG into standard 30-group THERMOS energy group structure (1.86 eV to 0.0047 eV), using a Maxwell-Boltzmann distribution with temperature 293 deg.K as a weighting function for E < 0.125 eV coupled to a 1/E weighting function for E from 0.125 eV to 1.86 eV. (c) Compute room temperature free-gas kernels, using THERMOS tape-making program, and

  5. Measurement of the production yield for negative Bi-209 ions and compounds

    In order to perform high sensitivity Accelerator Mass Spectrometry (AMS) measurements of the ratio 210 Bi/209 Bi an important constraint is the use of a high ion current produced by the ion sputtering source. Until now, the information regarding the production of negative Bi ions by sputtering with Cs+ is rather sparse. The electron affinity (EA) is in some extend proportional to the yield of produced negative ions and can be used as a first approximation in this evaluation. For Bi the EA is 0.95 eV. To obtain reliable information about the production yield of negative ions produced by the sputter process of Cs+ ions on Bi (as metallic and other chemical forms) we used the AMS injector deck and performed an experiment in which all negative ion species produced were magnetically analysed. To determine the optimal sputtering yield of negative Bi ions the targets were prepared as Bi2O3, Bi(NO3)3 and metallic Bi. The target material was mixed with Ag and pressed into the source sample holder made of silver. Different fractions of Bi/Ag mixing have been tested to determine the best mechanical resistance and a good electric conductivity. The measurements were performed using the AMS Injector. The negative ions produced in the sputter source are extracted and accelerated up to 15 keV. Then, the negative ions pass through the 90 angle analyzing magnet where the selection of the desired ion species is performed and are measured in the second Faraday cup situated at the exit of the analyzer. In the experiment, the negative ion current was measured in both Faraday cups placed at the entrance and at the exit of the magnetic analyzer. In the first cup, at the entrance of the analyzer, we measure the overall ion current accompanied by electrons. The electron current is depending on the ion source operation conditions and in our source this represents about 20% from the total negative current. This fraction can be determined by removing the electrons from the total beam using the

  6. Artificial radionuclides in the atmosphere over Lithuania

    Systematic observations of radionuclide composition and concentration in the atmosphere have been carried out at the Institute of Physics in Vilnius since 1963. An increase in activity concentration of radionuclides in the atmosphere was observed after nuclear weapon tests and the Chernobyl NPP accident. At present the radiation situation in Lithuania is determined by two main sources of radionuclides, forest fire and resuspension products transferred from highly polluted region of the Ukraine and Belarus. During forest fires the increase in activity concentration of 137Cs in the atmosphere was registered in many countries and in Lithuania as well. This work summarizes the experimental data on transport of cesium, plutonium, americium from the highly contaminated territories after the Chernobyl accident. The activity concentrations of 137Cs were measured in two - three days samples while plutonium and americium in monthly samples. In addition, the analyses of the events of the increase activity concentration, meteorological situation, speciation of radionuclides and mechanisms of formation and transformation of aerosol carriers of radionuclides are presented. Aerosols were sampled on perchlorvinyl filters and the large volume air samplers with a flow rate from 2400 m3/h to about 6000 m3/h were used. The radiochemical analyses of monthly samples of aerosol ashes (about 30 g) were performed. For separation of Pu isotopes the TOPO/cyclohexane extraction and radiochemical purification using UTEVA resin were performed, Am was separated after TOPO/cyclohexane extraction using TRU and TEVA resins (100-150 μm). 242Pu and 243Am were used as tracers in the separation procedure. The alpha spectrometry measurements of Pu and Am isotopes deposited on a stainless steel disc were carried out with the Alphaquattro (Silena) spectrometer. 137Cs was determined by gamma-ray spectrometry using the high purity HPGe detector (resolution - 1.9 keV/1.33 Mev, efficiency - 42%). Accuracy

  7. ZZ MATXSLIBJ33, JENDL-3.3 based, 175 N-42 photon groups (VITAMIN-J) MATXS library for discrete ordinates multi-group

    -156, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Tb-159, Er-162, Er-164, Er-166, Er-167, Er-168, Er-170, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Ta-181, W-182, W-183, W-184, W-186, Hg-196, Hg-198, Hg-199, Hg-200, Hg-201, Hg-202, Hg-204, Pb-204, Pb-206, Pb-207, Pb-208, Bi-209, Ra-223, Ra-224, Ra-225, Ra-226, Ac-225, Ac-226, Ac-227, Th-227, Th-228, Th-229, Th-230, Th-232, Th-233, Th-234, Pa-231, Pa-232, Pa-233, U-232, U-233, U-234, U-235, U-236, U-237, U-238, Np-235, Np-236, Np-237, Np-238, Np-239, Pu-236, Pu-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-244, Pu-246, Am-241, Am-242, Am-242m, Am-243, Am-244, Am-244m, Cm-240, Cm-241, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Cm-249, Cm-250, Bk-247, Bk-249, Bk-250, Cf-249, Cf-250, Cf-251, Cf-252, Cf-254, Es-254, Es-255, Fm-255 Temperatures: 300 K. Origin: JENDL-3.3. Weighting spectrum: -- iwt=11 for NJOY-99. Legendre expansion: P6. Thermal scattering: free gas model. Self shielding: sigma-0, infinity, 10000, 1000, 300, 100, 30, 10, 1, 0.1, 1. E-5. Kerma factors are provided. NEA-1707/03: Corrections were made to the continuous inelastic scattering matrices (MT=91), for all nuclides for which this channel is open. This replaces the previous version. 2 - Methods: The nuclear data processing system NJOY-99.67 was used to produce MATXSLIBJ33. It can be further processed using TRANSX-2.15. 3 - Restrictions on the complexity of the problem: Accuracy of pointwise cross-section reconstruction: 0.1%; Upper limit of thermal region: 4.6 eV

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

    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

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

    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

  10. New Fragment Separation Technology for Superheavy Element Research

    Shaughnessy, D A; Moody, K J; Henderson, R A; Kenneally, J M; Landrum, J H; Lougheed, R W; Patin, J B; Stoyer, M A; Stoyer, N J; Wild, J F; Wilk, P A

    2008-01-28

    found that the efficiency of transporting products from the target chamber to the detector array was much too low for applications in heavy element experiments where production rates are on the order of one atom per day or less. Work continues on the MASHA separator, and once the efficiency has been improved, we plan to continue our work on the Pu target for future element 114 experiments. Due to the delays of the MASHA separator, work on establishing the identity of heavy element species produced through nuclear reactions focused instead on chemical separations. In particular, element 115 decays through a series of alpha decays, terminating with an element 105 isotope with a long half-life ({approx} 1 day). By chemically separating the element 105 daughter and observing its subsequent fission decay, the identity of the original parent nucleus can be established through the genetic correlation of the initial series of alpha decays. Chemical separations of element 105 were developed in Switzerland, Russia, and at LLNL. Over the course of two experiments, reaction products from the {sup 243}Am+{sup 48}Ca reaction were collected in a copper block and subsequently processed for chemical separation of the Group Five elements [8,9,13,15]. The Group Five elements were initially separated from the Group Four species, and then the samples were sub-divided into tantalum and niobium fractions. All of the fission events were observed in the tantalum fractions, which implied that element 105 behaved more like tantalum under the chemical conditions of these experiments. These experiments were very successful, and not only demonstrated that chemical separation could be performed on single atoms of interest, but also lent proof to the identity of the parent nucleus as element 115. Subsequent analysis of the alpha spectra taken during the experiment further prove that the fission events observed during the two experiments came from element 105 as the decay daughter of element 115 and

  11. Subcritical assemblies with fast and thermal neutron spectrum driven with high intensity neutron generator NG-12-1

    from polyethylene blocks with the channels to place the fuel pins and has a square lattice with 2.0 cm pitch. The subcritical assembly has been loaded with UO2 fuel (U-235 enrichment equal to 10 %). Central part of the core is a neutron producing lead target 10 cm diameter and 60 cm length. There are channels for location of detectors of neutron flux monitoring system at the boundaries of the core and experimental channels with diameter of 25 mm for radii 5, 10 and 16 cm for placing different type of samples or Cf-252 source inside the core. The core is surrounded by high purity graphite reflector 40.0 cm thickness and thin 1.5 mm Cd layer. The 'Yalina' facility can be used to study the physics of multiplying media at different subcriticality levels, large range of different configurations (geometry, composition) and external sources (Cf-252, D(d,n)He-3,D(T,n)He-4). A wide experimental program on the basis of the facility since that time has been already performed. The measurements of spatial neutron flux distribution, spectral indices, external neutron source importance, transmutation reactions rates (129I, 237Np, 243Am), neutron flux time evolution, multiplication factor Keff, source multiplication factor Ks for different levels of subcriticality of the assembly driven by neutron generator operating in continuous and pulse modes with Ti3H, TiD targets and 252Cf source placed at various position inside the core is going on. The analysis of the sequence of experimental data has been performed with MCNP code and with different neutron libraries (ENDFB-VI, ENDFB-IV). The comparison of the theoretical and experimental data shows that in a number of cases they agree relatively well within error margins. Further investigations at the National Academy of Sciences of Belarus will be performed in the framework of strategy of booster sub-critical systems driven by a neutron generator. The facility will be put into operation by May of 2005. The basic idea of a fast spectrum

  12. ZZ FSXJ32, MCNP nuclear data library based on JENDL-3.2. ZZ FSXLIBJ33, MCNP nuclear data library based on JENDL-3.3

    -103, Rh-105, Pd-102, Pd-104, Pd-105, Pd-106, Pd-107, Pd-108, Pd-110, Ag-107, Ag-109, Ag-110m,Cd-106, Cd-108, Cd-110, Cd-111, Cd-112, Cd-113, Cd-114, Cd-116, In-113, In-115, Sn-112, Sn-114, Sn-115, Sn-116, Sn-117, Sn-118, Sn-119, Sn-120, Sn-122, Sn-123, Sn-124, Sn-126, Sb-121, Sb-123, Sb-124, Sb-125, Te-120, Te-122, Te-123, Te-124, Te-125, Te-126, Te-127m,Te-128, Te-129m,Te-130, I -127, I -129, I -131, Xe-124, Xe-126, Xe-128, Xe-129, Xe-130, Xe-131, Xe-132, Xe-133, Xe-134, Xe-135, Xe-136, Cs-133, Cs-134, Cs-135, Cs-136, Cs-137, Ba-130, Ba-132, Ba-134, Ba-135, Ba-136, Ba-137, Ba-138, Ba-140, La-138, La-139, Ce-140, Ce-141, Ce-142, Ce-144, Pr-141, Pr-143, Nd-142, Nd-143, Nd-144, Nd-145, Nd-146, Nd-147, Nd-148, Nd-150, Pm-147, Pm-148, Pm-148m,Pm-149, Sm-144, Sm-147, Sm-148, Sm-149, Sm-150, Sm-151, Sm-152, Sm-153, Sm-154, Eu-151, Eu-152, Eu-153, Eu-154, Eu-155, Eu-156, Gd-152, Gd-154, Gd-155, Gd-156, Gd-157, Gd-158, Gd-160, Tb-159, Er-162, Er-164, Er-166, Er-167, Er-168, Er-170, Hf-174, Hf-176, Hf-177, Hf-178, Hf-179, Hf-180, Ta-181, W-182, W-183, W-184, W-186, Hg-196, Hg-198, Hg-199, Hg-200, Hg-201, Hg-202, Hg-204, Pb-204, Pb-206, Pb-207, Pb-208, Bi-209, Ra-223, Ra-224, Ra-225, Ra-226, Ac-225, Ac-226, Ac-227, Th-227, Th-228, Th-229, Th-230, Th-232, Th-233, Th-234, Pa-231, Pa-232, Pa-233, U-232, U-233, U-234, U-235, U-236, U-237, U-238, Np-235, Np-236, Np-237, Np-238, Np-239, Pu-236, Pu-237, Pu-238, Pu-239, Pu-240, Pu-241, Pu-242, Pu-244, Pu-246, Am-241, Am-242, Am-242m, Am-243, Am-244, Am-244m, Cm-240, Cm-241, Cm-242, Cm-243, Cm-244, Cm-245, Cm-246, Cm-247, Cm-248, Cm-249, Cm-250, Bk-247, Bk-249, Bk-250, Cf-249, Cf-250, Cf-251, Cf-252, Cf-254, Es-254, Es-255, Fm-255 Temperatures: 300 K. Origin: JENDL-3.3. Thermal scattering: Free gas model Kerma factors are provided. The original JENDL-3.3 has two problems in Am-241 data. One is the missing of MF/MT=4/18, and the other is the incorrect neutron spectra for MT=18 below 500 keV. The updated data have been produced as JENDL-3