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Journal Articles

New approach to description of ($$d$$,$$xn$$) spectra at energies below 50 MeV in Monte Carlo simulation by intra-nuclear cascade code with distorted wave born approximation

Hashimoto, Shintaro; Iwamoto, Yosuke; Sato, Tatsuhiko; Niita, Koji*; Boudard, A.*; Cugnon, J.*; David, J.-C.*; Leray, S.*; Mancusi, D.*

Nuclear Instruments and Methods in Physics Research B, 333, p.27 - 41, 2014/08

 Times Cited Count:18 Percentile:86.15(Instruments & Instrumentation)

Recently, accelerator-based neutron sources have been considered for scientific research and medical applications, where deuteron-induced reactions of Li, Be, or C targets at low ($$<$$50 MeV) incident energies are essential to produce high-intensity neutron beams. Description of the reactions in simulations of particle transport are required to estimate dose distributions. In this study, we developed a new method that combines the Intra-Nuclear Cascade of Li$`e$ge (INCL) and Distorted Wave Born Approximation (DWBA), and incorporated it into the Particle and Heavy Ion Transport code System (PHITS). A proton-stripping process and transitions between discrete states of nuclei are considered in the method by INCL and DWBA, respectively. We applied the method to reproduce neutron spectra in the reactions on thin and thick targets. Results obtained by PHITS with the method successfully agreed with experimental data, which were not reproduced by the old model.

Journal Articles

New approach for describing nuclear reactions based on intra-nuclear cascade coupled with DWBA

Hashimoto, Shintaro; Iwamoto, Yosuke; Sato, Tatsuhiko; Niita, Koji*; Boudard, A.*; Cugnon, J.*; David, J.-C.*; Leray, S.*; Mancusi, D.*

Progress in Nuclear Science and Technology (Internet), 4, p.418 - 421, 2014/04

There is a growing interest in the use of accelerator-based neutron sources for scientific and medical applications. For neutron source design, computer codes that can evaluate neutron yields are indispensable; PHITS (Particle and Heavy Ion Transport code System) is one of suitable candidates. In this study, we proposed a new nuclear reaction model based on INCL coupled with the DWBA calculation for an accurate calculation of neutron yields. The DWBA calculation describes discrete peaks in neutron spectra. Although these peaks are not the major part of neutron sources, the estimation of their contributions is necessary, since neutrons from the peaks have high energies close to those of the incident particle. We will present the calculation method of our approach and results for proton and deuteron induced reactions on Li, Be, and C targets at incident energies from 10 to 100 MeV.

Journal Articles

Verification of high-energy transport codes on the basis of activation data

Titarenko, Yu. E.*; Batyaev, V. F.*; Butko, M. A.*; Dikarev, D. V.*; Florya, S. N.*; Pavlov, K. V.*; Titarenko, A. Yu.*; Tikhonov, R. S.*; Zhivun, V. M.*; Ignatyuk, A. V.*; et al.

Physical Review C, 84(6), p.064612_1 - 064612_19, 2011/11

 Times Cited Count:19 Percentile:76.34(Physics, Nuclear)

Nuclide production cross sections measured at the Institute for Theoretical and Experimental Physics (ITEP) for the targets of $$^{rm nat}$$Cr, $$^{56}$$Fe, $$^{rm nat}$$Ni, $$^{93}$$Nb, $$^{181}$$Ta, $$^{rm nat}$$W, $$^{rm nat}$$Pb, and $$^{209}$$Bi irradiated by protons with energies from 40 to 2600 MeV were used to estimate the predictive accuracy of several popular high-energy transport codes. A general agreement of the ITEP data with the data obtained by other groups, including the numerous GSI data measured by the inverse kinematics method was found. Simulations of the measured data were performed with a number of codes. Deviation factors between the calculated and experimental cross sections have been estimated for each target and for the whole energy range covered by our measurements. Further improvements of all tested here codes are recommended. In addition, new measurements at ITEP of nuclide yields from the $$^{208}$$Pb target irradiated by 500-MeV protons are presented.

Journal Articles

Verification of high-energy transport codes on the basis of activation data

Titarenko, Yu. E.*; Batyaev, V. F.*; Butko, M. A.*; Dikarev, D. V.*; Florya, S. N.*; Pavlov, K. V.*; Titarenko, A. Yu.*; Tikhonov, R. S.*; Zhivun, V. M.*; Ignatyuk, A. V.*; et al.

LA-UR-11-02704, 31 Pages, 2011/06

Nuclide production cross sections measured at ITEP for the targets of $$^{nat}$$Cr, $$^{56}$$Fe,$$^{nat}$$Ni, $$^{93}$$Nb, $$^{181}$$Ta, $$^{nat}$$W, $$^{nat}$$Pb, $$^{209}$$Bi irradiated by protons with energies from 40 to 2600 MeV were used to estimate the predictive accuracy of several popular high-energy transport codes. A general agreement of the ITEP data with the data obtained by other groups, including the numerous GSI data measured by the inverse kinematics method was found. Simulations of the measured data were performed with the MCNPX (Bertini and ISABEL options), CEM03.02, INCL4.2+ABLA, INCL4.5+ABLA07, PHITS, and CASCADE.07 codes. Deviation factors between the calculated and experimental cross sections have been estimated for each target and for the whole energy range covered by our measurements. Further improvements of all tested here codes are recommended.

Journal Articles

Measurement and simulation of the cross sections for nuclide production in $$^{56}$$Fe and $$^{rm nat}$$Cr targets irradiated with 0.04- to 2.6-GeV protons

Titarenko, Yu. E.*; Batyaev, V. F.*; Titarenko, A. Yu.*; Butko, M. A.*; Pavlov, K. V.*; Florya, S. N.*; Tikhonov, R. S.*; Zhivun, V. M.*; Ignatyuk, A. V.*; Mashnik, S. G.*; et al.

Physics of Atomic Nuclei, 74(4), p.523 - 536, 2011/04

 Times Cited Count:11 Percentile:61.64(Physics, Nuclear)

The cross sections for nuclide production in thin $$^{56}$$Fe and $$^{rm nat}$$Cr targets irradiated by 0.04 to 2.6 GeV protons are measured by direct $$gamma$$ spectrometry using two $$gamma$$ spectrometers with the resolutions of 1.8 and 1.7 keV for the $$^{60}$$Co 1332 keV $$gamma$$ line. As a result, 649 yields of radioactive residual product nuclei have been obtained. The $$^{27}$$Al($$p$$, $$x$$)$$^{22}$$Na reaction has been used as a monitor reaction. The experimental data are compared with the MCNPX (BERTINI, ISABEL), CEM03.02, INCL4.2, INCL4.5, PHITS, and CASCADE07 calculations.

Journal Articles

Measurement and simulation of the cross sections for nuclide production in $$^{93}$$Nb and $$^{rm nat}$$Ni targets irradiated with 0.04- to 2.6-GeV protons

Titarenko, Yu. E.*; Batyaev, V. F.*; Titarenko, A. Yu.*; Butko, M. A.*; Pavlov, K. V.*; Florya, S. N.*; Tikhonov, R. S.*; Zhivun, V. M.*; Ignatyuk, A. V.*; Mashnik, S. G.*; et al.

Physics of Atomic Nuclei, 74(4), p.537 - 550, 2011/04

 Times Cited Count:18 Percentile:75.17(Physics, Nuclear)

The cross sections for nuclide production in thin $$^{93}$$Nb and $$^{rm nat}$$Ni targets irradiated by 0.04 to 2.6 GeV protons are measured by direct $$gamma$$ spectrometry using two $$gamma$$ spectrometers with the resolutions of 1.8 and 1.7 keV for the $$^{60}$$Co 1332-keV $$gamma$$ line. As a result, 1112 yields of radioactive residual product nuclei have been obtained. The $$^{27}$$Al($$p$$, $$x$$)$$^{22}$$Na reaction has been used as a monitor reaction. The experimental data are compared with the MCNPX (BERTINI, ISABEL), CEM03.02, INCL4.2, INCL4.5, PHITS, and CASCADE07 calculations.

Journal Articles

Measurement and simulation of the cross sections for nuclide production in $$^{rm nat}$$W and $$^{181}$$Ta targets irradiated with 0.04- to 2.6-GeV protons

Titarenko, Yu. E.*; Batyaev, V. F.*; Titarenko, A. Yu.*; Butko, M. A.*; Pavlov, K. V.*; Florya, S. N.*; Tikhonov, R. S.*; Zhivun, V. M.*; Ignatyuk, A. V.*; Mashnik, S. G.*; et al.

Physics of Atomic Nuclei, 74(4), p.551 - 572, 2011/04

 Times Cited Count:24 Percentile:81.43(Physics, Nuclear)

The cross sections for nuclide production in thin $$^{rm nat}$$W and $$^{181}$$Ta targets irradiated by 0.04 to 2.6GeV protons are measured by direct $$gamma$$ spectrometry using two $$gamma$$ spectrometers with the resolutions of 1.8 and 1.7 keV for the $$^{60}$$Co 1332-keV $$gamma$$ line. As a result, 1895 yields of radioactive residual product nuclei have been obtained. The $$^{27}$$Al($$p$$, $$x$$)$$^{22}$$Na reaction has been used as a monitor reaction. The experimental data are compared with the MCNPX (BERTINI, ISABEL), CEM03.02, INCL4.2, INCL4.5, PHITS, and CASCADE07 calculations.

Journal Articles

Measurement and simulation of the cross sections for the production of $$^{148}$$Gd in thin $$^{rm nat}$$W and $$^{181}$$Ta targets irradiated with 0.4- to 2.6-GeV protons

Titarenko, Yu. E.*; Batyaev, V. F.*; Titarenko, A. Yu.*; Butko, M. A.*; Pavlov, K. V.*; Florya, S. N.*; Tikhonov, R. S.*; Zhivun, V. M.*; Ignatyuk, A. V.*; Mashnik, S. G.*; et al.

Physics of Atomic Nuclei, 74(4), p.573 - 579, 2011/04

 Times Cited Count:8 Percentile:52.71(Physics, Nuclear)

The cross sections for the production of $$^{148}$$Gd in $$^{rm nat}$$W and $$^{181}$$Ta targets irradiated by 0.4-, 0.6-, 0.8-, 1.2-, 1.6-, and 2.6-GeV protons at the ITEP accelerator complex have been measured by direct $$alpha$$ spectrometry without chemical separation. The experimental data have been compared with the data obtained at other laboratories and with the theoretical simulations of the yields on the basis of the BERTINI, ISABEL, CEM03.02, INCL4.2, INCL4.5, CASCADE07, and PHITS codes.

Journal Articles

Gas production and activation calculation in MEGAPIE

Thiolliere, N.*; David, J.-C.*; Eid, M.*; Konobeyev, A. Y.*; Eikenberg, J.*; Fischer, U.*; Gr$"o$schel, F.*; Guertin, A.*; Latg$'e$, C.*; Lemaire, S.*; et al.

Proceedings of International Conference on the Physics of Reactors, Nuclear Power; A Sustainable Resource (PHYSOR 2008) (CD-ROM), 8 Pages, 2008/09

Gas measurements by $$gamma$$ spectroscopy in the MEGAwatt PIlot Experiment (MEGAPIE) project has led to the determination of main radioactive isotopes released by the LBE. Comparison with calculations performed with several validated codes supplies important volatile elements release fraction estimation in a spallation target. In addition, calculations with MCNPX2.5.0, FLUKA and SNT codes coupled with evolution programs have been performed in order to study the activation of the target and structural materials. The induced database is relevant for safety and radioprotection during operation, for the post-irradiation experiments and for target dismantlement.

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