Tada, Kenichi; Kosako, Kazuaki*; Yokoyama, Kenji; Konno, Chikara
Nihon Genshiryoku Gakkai-Shi ATOMO, 60(3), p.168 - 172, 2018/03
The neutronics calculation codes cannot treat the evaluated nuclear data file directly. The nuclear data processing is required to use the nuclear data file in the neutronics calculation codes. The nuclear data processing is not just a converter but also many processes to evaluate the physical values for the neutronics calculation codes. In this paper, we describe the overview of the nuclear data processing and validation of the nuclear data.
Kunieda, Satoshi; Iwamoto, Osamu; Iwamoto, Nobuyuki; Minato, Futoshi; Okamoto, Tsutomu; Sato, Tatsuhiko; Nakashima, Hiroshi; Iwamoto, Yosuke; Iwamoto, Hiroki; Kitatani, Fumito; et al.
JAEA-Conf 2016-004, p.41 - 46, 2016/09
Neutron- and proton-induced cross-section data are required in a wide energy range beyond 20 MeV, for the design of accelerator applications. New evaluations are performed with recent knowledge in the optical and pre-equilibrium model calculations. We also evaluated cross-sections for p+Li and p+Be which have been highly requested from a medical field. The present high-energy nuclear data library, JENDL-4.0/HE, includes evaluated cross-sections for incident neutrons and protons up to 200 MeV (for about 130 nuclei). We overview substantial features of the library, i.e., (1) systematic evaluation with CCONE code, (2) challenges for evaluations of light nuclei and (3) inheritance of JENDL-4.0 and JENDL/HE-2007. In this talk, we also focus on the results of benchmark calculation for neutronics to show performance of the present library.
Iwamoto, Nobuyuki; Kosako, Kazuaki*; Murata, Toru*
JAEA-Conf 2016-004, p.53 - 58, 2016/09
Photonuclear data have been required to propose non-destructive assay and high energy -ray therapy as well as shielding design of an electron accelerator facility. A new photonuclear data file has been developed to take into account a wide variety of use. Nuclear data of stable light nuclides from Li to Ca were evaluated with experimental data and nuclear structural data. For nuclides above Ca, the photon absorption cross sections were calculated with GDR and QD model by nuclear reaction model codes, ALICE-F and CCONE. The incident photon energy covers the range up to 140 MeV. The data included absorption, particle production yield and nuclide production cross sections, and energy-angle differential cross sections of emitted particles. The new version has the nuclear data of 181 nuclides. In addition, an extended version is also planned to be released, in which systematic calculations by the ALICE-F code were performed for ~2500 nuclides other than those included in standard file.
Murata, Toru*; Kosako, Kazuaki*; Iwamoto, Nobuyuki
JAEA-Conf 2016-004, p.153 - 158, 2016/09
The experimental photo-nuclear data of H were measured by Faul et al. These data were analyzed with the same model as those applied to He photo-nuclear reactions to obtain production cross sections of neutron, proton and deuteron and also energy spectrum of these particles. Evaluated quantities will be contained in new Photo-nuclear Data File of JENDL. With these cross section of neutron production, feasibility study was made to reduce H density in the waste water by photon irradiation using an electron LINAC. Photon energy and angular distributions of bremsstrahlung were estimated using the method given by Hisdal, taking into account the multiple scattering of the incident electrons in the target. Preliminary results of photon energy spectrum at some emission angles and the H(,n)+(,2n) cross sections will be shown in the presentation. In case of irradiation of the waste water sample thickness of 50 cm with forward angle emission photon beam produced by 10mA electrons 100 sec., about a few percent reduction of H are expected with rough estimation.
Murata, Toru; Iwamoto, Nobuyuki; Kosako, Kazuaki*
JAEA-Conf 2015-003, p.237 - 242, 2016/03
Development of non-destructive assay technique of nuclear materials is required for the nuclear safeguard and nuclear security, especially for high level radioactive wastes such as vitrified solids. For these objects, irradiation of high transparent rays and detection of fission responses with high discrimination are required and will be attained with high energy photon irradiation and delayed neutron detections. To study the feasibility of the methods and to design the apparatus, the delayed neutron data will be requested. Their evaluation was performed approximately by utilizing neutron induced fission delayed neutron data of JENDL-4.0 for the same compound nucleus as the photo-fission. If the same compound nucleus data were not available, group delayed neutron intensities (say six or so groups) were calculated with the method given by Brady and England with the cumulative fission yields systematics given by Wahl. The present results will be given at the symposium.
Kojima, Kensuke; Okumura, Keisuke; Kosako, Kazuaki*; Torii, Kazutaka*
JAEA-Research 2015-019, 90 Pages, 2016/01
At the decommissioning of light water reactors (LWRs), it is important to evaluate an amount of radioactivity in the ex-core structures such as a reactor containment vessel, radiation shieldings, and so on. It is thought that the leakage neutron spectra in these radioactivation regions, which strongly affect the induced radioactivity, would be changed by different reactor core configurations such as fuel assembly loading pattern and fuel burnups. This study was intended to evaluate these effects. For the purpose, firstly, partial neutron currents on the core surfaces were calculated for some core configurations. Then, the leakage neutron flux spectra in major radioactivation regions were calculated based on the provided currents. Finally, influence of the core configurations upon the neutron flux spectra was evaluated. As a result, it has been found that the influence is small on the spectrum shapes of neutron fluxes. However, it is necessary to pay attention to the facts that intensities of the leakage neutron fluxes are changed by the configurations and that intensities and spectrum shapes of the leakage neutron fluxes are changed depending on the angular direction around the core.
Konno, Chikara; Maeda, Shigetaka; Kosako, Kazuaki*
Energy Procedia, 71, p.213 - 218, 2015/05
We report a problem on multigroup cross section data MATXS files with multiple temperatures. This problem was newly found out through neutron and flux calculations in a simple model of experimental fast reactor Joyo with DORT and MATXSLIB-J40, which is a multigroup cross section data file (300, 600, 900, 1200, 1800 K) of the latest Japanese Nuclear Data Library version 4.0 (JENDL-4.0) processed with the NJOY99 code. The calculated total neutron fluxes were almost the same both in 300 K and 600 K, while the total fluxes in 600 K were by 10% higher those that in 300 K. Through our detailed investigation, it was found out that the MATXS data format processed with NJOY was not consistent to that assumed in TRANSX for production data. In order to solve this problem, we made a simple program for modifying MATXS files to ones suitable to TRANSX. MATXSLIB-J40 will be revised with this program.
Kosako, Kazuaki*; Murata, Toru*; Iwamoto, Nobuyuki
Nuclear Physics and -ray sources for Nuclear Security and Nonproliferation, p.261 - 268, 2014/12
The next version of JENDL Photonuclear data is now being developed by using the photon absorption cross sections based on giant dipole resonances and the nuclear reaction model codes, ALICE-F and CCONE. The incident photon energy covers the range from particle emission threshold to 140 MeV. The data include absorption, particle production yield and nuclide production cross sections, and energy-angle differential cross sections of emitted particles. In the present revision much emphasis is placed on the following topics: (1) Nuclear data of light nuclei from Li to Ca isotopes are systematically evaluated with experimental data. (2) Integral tests of photoneutron yields for Fe, Cu and W performed at Hokkaido University are used to evaluate and verify their nuclide production data. (3) The number of nuclei is increased to 181 in order to take into account the use in many application fields.
Sakurai, Takeshi; Kosako, Kazuaki*; Mori, Takamasa
Progress in Nuclear Science and Technology (Internet), 2, p.318 - 329, 2011/10
Sakurai, Takeshi; Kosako, Kazuaki*; Mori, Takamasa
Proceedings of Joint International Conference of 7th Supercomputing in Nuclear Application and 3rd Monte Carlo (SNA + MC 2010) (USB Flash Drive), 8 Pages, 2010/10
Sasa, Toshinobu; Sugawara, Takanori; Fukahori, Tokio; Kosako, Kazuaki*
Proceedings of 10th OECD/NEA Information Exchange Meeting on Actinide and Fission Product Partitioning and Transmutation (CD-ROM), 8 Pages, 2010/00
The latest version of JENDL High Energy File (JENDL/HE-2007) includes the reaction cross section of proton and neutron for 106 nuclides below 3 GeV to simulate accelerator application such as spallation neutron source and accelerator-driven system. A NJOY-99.251 code was modified to produce continuous energy cross section library for MCNPX code system from JENDL/HE-2007. Higher temperature libraries were also produced to simulate reactor systems accurately. Several test calculation was done with typical fast reactor and accelerator-driven transmutation system and good agreement was observed the k-effective values compared with existing JENDL-3.3 based cross section library.
Takada, Hiroshi; Kosako, Kazuaki*; Fukahori, Tokio
Journal of Nuclear Science and Technology, 46(6), p.589 - 598, 2009/06
The most updated high energy nuclear data file, JENDL/HE-2007, was validated with focus on heavy elements of W, Pb and Hg through analyses of spallation experiments using thick targets at incident proton energies from 0.5 to 2.83 GeV. For this purpose, the processing of the PHITS code system was adjusted to simulate nucleon transport phenomena using only a cross-section library up to 3 GeV with an aid of an intranuclear cascade evaporation model for treating pion-induced reactions. The data in JENDL/HE-2007 predicted well the neutron spectra produced in thick targets with energies lower than 15 MeV while underestimated those from 20 to 100 MeV by a factor of 0.4 to 0.5. It is also confirmed that the cross-section data of the Nb(n,4n)Nb and Co(n,4n)Co reaction for high energy neutron field are reasonable. The present accuracy of JENDL/HE-2007 is almost as same as for the traditional method using intranuclear cascade model of Bertini.
Sasa, Toshinobu; Sugawara, Takanori; Kosako, Kazuaki*; Fukahori, Tokio
JAEA-Data/Code 2008-022, 18 Pages, 2008/11
The latest JENDL High Energy File (JENDL/HE) was released in 2007 to respond the requirements of reaction data in high energy range up to several GeV to design accelerator facilities such as accelerator-driven systems and research complex like J-PARC. To apply the JENDL/HE-2007 file to the design study, the cross section library of FXJH7 series was constructed from the JENDL/HE file for the calculation using MCNP and MCNPX codes which are widely used in the field of nuclear reactors, fusion reactors, accelerator facilities, medical applications, and so on. In this report, the outline of the JENDL/HE-2007 file, modification of nuclear data processing code NJOY99, construction of FXJH7 library and test calculations for shielding and eigenvalue analyses are summarized.
Shibata, Keiichi; Nakagawa, Tsuneo; Fukahori, Tokio; Iwamoto, Osamu; Ichihara, Akira; Iwamoto, Nobuyuki; Kunieda, Satoshi; Otsuka, Naohiko; Katakura, Junichi; Watanabe, Yukinobu*; et al.
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.727 - 732, 2008/05
General- and special-purpose JENDL data files are being produced in cooperation with the Japanese Nuclear Data Committee. We have developed nuclear model codes to improve the quality of MA and FP data. In the FP region, we obtained global coupled-channel optical model parameters, which can be applied to neutron- and proton-induced reaction data up to 200 MeV. These parameters are used for statistical model calculation. Resolved resonance parameters of MA and FP nuclei were updated to improve the low-energy behavior of the cross sections by using recent measurements. As a follow-up of JENDL-3.3, which was released in 2002, covarainces of several nuclei were estimated for a study on ADS. Concerning special-purpose files, the compilation of the 2007 versions of JENDL High Energy File and Photonulcear Data Files is in the final stage.
Kishida, Norio*; Murata, Toru*; Asami, Tetsuo*; Kosako, Kazuaki*; Maki, Koichi*; Harada, Hideo*; Lee, Y.*; Chang, J.*; Chiba, Satoshi; Fukahori, Tokio
AIP Conference Proceedings 769, p.199 - 202, 2005/05
Nuclear data for photonuclear reactions are required in the field of shielding design of high-energy electron accelerators and high-energy -ray therapy. The JENDL Photonuclear Data File was prepared by a working group on nuclear data evaluations for photonuclear reactions in Japanese Nuclear Data Committee. From a survey of many literatures, it is difficult to construct the photonuclear data file by using only measured data, since there are not sufficient experimental data. We were therefore evaluating with theoretical calculations based on statistical nuclear reaction models. The photonuclear cross sections that are to be contained in the file are as follows: photoabsorption cross sections, yield cross sections and DDX for neutrons, protons, deuterons, tritons, He-particles and alpha-particles, and isotope production cross sections. For the actinide nuclides, photofission cross sections are also included. The maximum energy of incident photons is 140 MeV and stored are the photonuclear data for 68 nuclides from H to Np.
Watanabe, Yukinobu*; Fukahori, Tokio; Kosako, Kazuaki*; Shigyo, Nobuhiro*; Murata, Toru*; Yamano, Naoki*; Hino, Tetsushi*; Maki, Koichi*; Nakashima, Hiroshi; Odano, Naoteru*; et al.
AIP Conference Proceedings 769, p.326 - 331, 2005/05
An overview is presented of recent nuclear data evaluations performed for the JENDL high-energy (JENDL-HE) file, in which neutron and proton cross sections for energies up to 3 GeV are included for the whole 132 nuclides. The current version of the JENDL-HE file consists of neutron total cross sections, nucleon elastic scattering cross sections and angular distributions, nonelastic cross sections, production cross sections and double-differential cross sections of secondary light particles ( He, , and ) and -rays, isotope production cross sections, and fission cross sections in the ENDF6 format. The present evaluations are performed on the basis of experimental data and theoretical model calculations. For the cross section calculations, we have constructed a hybrid calculation code system with some available nuclear model codes and systematics-based codes, such as ECIS96, OPTMAN, GNASH, JQMD, JAM, TOTELA, FISCAL, and so on. The evaluated cross sections are compared with available experimental data and the other evaluations. Future plans of our JENDL-HE project are discussed along with prospective needs of high-energy cross section data.
Sakurai, Takeshi; Kosako, Kazuaki*; Mori, Takamasa
Monte Karuro Keisanho Kodoka No Genjo; Dai-3-Kai Monte Karuro Shimyureshon Kenkyukai Hobunshu, p.168 - 176, 2004/12
no abstracts in English
Kosako, Kazuaki*; Yamano, Naoki*; Fukahori, Tokio; Shibata, Keiichi; Hasegawa, Akira
JAERI-Data/Code 2003-011, 38 Pages, 2003/07
The third revision of JENDL-3 (JENDL-3.3) was released in May 2002. The library is useful for many applications. For users' convenience, we have produced two JENDL-3.3 based libraries FSXLIB-J33 and MATXSLIB-J33 for transport calculation codes such as MCNP and ANISN. These two libraries are available on request.
Kai, Tetsuya; Maekawa, Fujio; Kasugai, Yoshimi; Kosako, Kazuaki*; Takada, Hiroshi; Ikeda, Yujiro
JAERI-Research 2002-005, 65 Pages, 2002/03
Reliability assessment for the High Energy Particle Induced Radioactivity Calculation Code DCHAIN-SP 2001 was carried out through analysis of integral activation experiments with 14-MeV neutrons. The following three series of experiments conducted at the D-T neutron source facility, FNS, in JAERI were employed: (1) the decay gamma-ray measurement experiment for fusion reactor materials, (2) the decay heat measurement experiment for 32 fusion reactor materials, and (3) the integral activation experiment on mercury.As a result, it was found that the calculations with DCHAIN-SP 2001 predicted the experimental data for (1)(3) approximately within 30%, 20% and 20%, respectively. It was concluded that the activation cross section data below 20 MeV and the associated decay data as well as the calculation algorithm for solving the Beteman equation that was the master equation of DCHAIN-SP were adequate.
Chiba, Satoshi; Fukahori, Tokio; Shibata, Keiichi; Yu, B.*; Kosako, Kazuaki*; Yamamuro, Nobuhiro*
Journal of Nuclear Science and Technology, 39(2), p.187 - 194, 2002/02
no abstracts in English