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Journal Articles

DPA calculations for heavy-ion and proton incident reactions in high-energy region using the PHITS code

Iwamoto, Yosuke; Niita, Koji*; Sawai, Tomotsugu; Ronningen, R. M.*; Baumann, T.*

JAEA-Conf 2011-002, p.157 - 162, 2011/09

Radiation damage measured as a function of DPA is one of the critical issues for high-intensity beams, especially heavy-ions. The DPA model in PHITS has recently been extended to include contributions from Coulomb elastic scattering of transported charged particles. For the Coulomb elastic scattering, a universal one-parameter differential scattering cross section equation introduced by J. Lindhard et al. is employed instead of the differential Rutherford cross section which is a function of six parameters; charge and mass number of incident and produced particles, kinetic energy of incident particle and scattered angle. In this work, we compare PHITS results for the 130 MeV/u $$^{76}$$6Ge+$$^{184}$$W reaction with calculated results of TRIM which is two-dimensional damage calculation code. Then we calculate DPA for different ions, targets and energies in the energy region from 100 MeV/u to 1 GeV/u and evaluate the systematics of DPA.

Journal Articles

Sensitivity analysis for higher order Legendre coefficients of elastic scattering matrices

Chiba, Go

JAEA-Conf 2011-002, p.217 - 222, 2011/09

We perform a sensitivity analysis focusing on higher order Legendre coefficients of elastic scattering matrices. Through the sensitivity analysis, it is found that an attention should be paid to the kind of multi-group cross sections used for library effect calculations. Non-negligible library effects are observed in higher order Legendre coefficients of elastic scattering matrices of uranium-238 and iron-56 between JENDL-4.0 and other modern nuclear data files. It is concluded that higher order Legendre coefficients should be accounted for if accurate estimation of a library effect is required.

Journal Articles

Sensitivity analysis for curium isotope concentrations of light water reactor mixed-oxide burned fuel

Chiba, Go; Ishikawa, Makoto

JAEA-Conf 2011-002, p.211 - 216, 2011/09

With a help of the depletion perturbation theory, sensitivities of curium isotope concentrations to nuclear data are calculated for light water reactor mixed-oxide burned fuel. Through the present study, phenomenon of the curium isotope generations during a reactor operation is well understood. In addition, important nuclear data for accurate prediction of the curium isotope concentrations are specified. These information may be helpful to investigate a cause of discrepancy between experimental and calculation values for the curium isotope concentrations.

Journal Articles

JENDL-4.0 benchmark for high temperature gas-cooled reactor, HTTR

Goto, Minoru; Shimakawa, Satoshi; Yasumoto, Takashi*

JAEA-Conf 2011-002, p.11 - 16, 2011/09

In the past, benchmark calculations of the HTTR criticality approach, which is a Japanese HTGR, have been performed by several countries, and almost of the calculations have overestimated its excess reactivity. In Japan, the benchmark calculations were performed by JAEA, and the calculations also resulted in overestimation. JAEA improved this overestimation by revising the problem geometry and replacing nuclear data library with JENDL-3.3, which was the latest JENDL at that time. However, the overestimation remained and this problem had not been resolved until today. We performed the calculation of the HTTR criticality approach with several nuclear data libraries, and found the slightly difference of the capture cross section of carbon at thermal energy among the libraries causes the difference of the $$k$$$$_{eff}$$ values to be not negligible. This cross section value had not been concerned in reactor neutronics calculation because of its small value on the order of 10$$^{-3}$$ burn, and consequently the cross section value had not been revised for a long time even in the major nuclear data libraries: JENDL, ENDF/B and JEFF. We have thought the cross section value should be revised based on the latest measurement data to improve the accuracy of the neutronics calculations for HTTR. On May in 2010, the latest JENDL (JENDL-4) was released by JAEA, and the capture cross section of carbon was revised. Consequently, JENDL-4 yielded 0.4-0.9%$$Delta$$k smaller $$k$$$$_{eff}$$ values than JENDL-3.3 in the calculation for the HTTR critical approach, and then the problem of the overestimation of the excess reactivity in the HTTR benchmark calculation was resolved.

Journal Articles

Personal perspective of strategy on nuclear data activities at JAEA

Fukahori, Tokio

JAEA-Conf 2011-002, p.5 - 10, 2011/09

The JENDL-4 is released in 2010 as one of goals of the first period mid-term research plan for JAEA. In the plan for the second period, the objective is "incident energy expansion of JENDL". The objective can be achieved by producing JENDL/HE, JENDL/PD, JENDL/PK. For this purpose, the nuclear reaction model code, CCONE, is planned to be improved by adding some models. The nuclear data for burn-up, activation, and PKA/DPA calculations will be prepared for the applications of reactors, safety research, material science, nuclear forensics, etc. The urgent problems for human resources, presence to the stake-holders, and budget (especially for nuclear data measurements) should be solved, for example, by efforts of the international collaborations, etc. The most urgent item is "covariance business" and this must be solved at least its direction of preparation.

Journal Articles

Measurements of neutron capture cross sections at J-PARC/MLF/ANNRI, 2

Hori, Junichi*; Fujii, Toshiyuki*; Fukutani, Satoshi*; Furusaka, Michihiro*; Furutaka, Kazuyoshi; Goko, Shinji*; Harada, Hideo; Hiraga, Fujio*; Igashira, Masayuki*; Kamiyama, Takashi*; et al.

JAEA-Conf 2011-002, p.29 - 34, 2011/09

The neutron capture cross sections of $$^{93}$$Zr, $$^{99}$$Tc and $$^{107}$$Pd have been measured relative to the $$^{10}$$B(n,$$alphagamma$$) standard cross section by the neutron time-of-flight (TOF) method. Neutron capture $$gamma$$ rays were measured with a 4$$pi$$ Ge spectrometer as a part of the Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI) installed at the neutron Beam Line No.4 (BL04) of the Material and Life science experimental Facility (MLF) in the Japan Proton Accelerator Research Complex (J-PARC). This paper presents the preliminary results.

Journal Articles

Journal Articles

Activation analyses by the beam losses in the IFMIF/EVEDA accelerator

Maebara, Sunao; Takahashi, Hiroki; Sakaki, Hironao; Hirabayashi, Keiichi*; Hidaka, Kosuke*; Shigyo, Nobuhiro*; Watanabe, Yukinobu*; Sagara, Kenshi*

JAEA-Conf 2011-002, p.199 - 204, 2011/09

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