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Iwamoto, Osamu; Iwamoto, Nobuyuki; Shibata, Keiichi; Ichihara, Akira; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke
EPJ Web of Conferences, 239, p.09002_1 - 09002_6, 2020/09
Times Cited Count：1 Percentile：89.98Kunieda, Satoshi; Furutachi, Naoya; Minato, Futoshi; Iwamoto, Nobuyuki; Iwamoto, Osamu; Nakayama, Shinsuke; Ebata, Shuichiro*; Yoshida, Toru*; Nishihara, Kenji; Watanabe, Yukinobu*; et al.
Journal of Nuclear Science and Technology, 56(12), p.1073 - 1091, 2019/12
Times Cited Count：3 Percentile：57.07(Nuclear Science & Technology)A new nuclear data library, JENDL/ImPACT-2018, is developed for an innovative study on the transmutation of long-lived fission products. Nuclear reaction cross- sections are newly evaluated for incident neutrons and protons up to 200 MeV for 163 nuclides including long-lived nuclei such as 
Se, 
Zr, 
Pd and 
Cs. Our challenge is an evaluation of cross-sections for a number of unstable nuclei over a wide energy range where the experimental data are very scarce. We estimated cross- sections based on a nuclear model code CCONE that incorporates an advanced knowledge on the nuclear structure theory and a model-parameterization based on a new experimental cross-sections measured by the inverse kinematics. Through comparisons with available experimental data on the stable isotopes, it is found that the present data give predictions of cross-sections better than those in the existing libraries.
Tada, Kenichi; Kunieda, Satoshi
KURNS-EKR-5, p.229 - 232, 2019/12
The R-matrix limited formula is formatted by the current nuclear data format and it is adopted some nuclei in the latest evaluated nuclear data library. Since the processing of the R-matrix limited formula is significantly different to the other resonance formulae, it is difficult to treat this formula without large modification of the nuclear data processing code. In this study, we implemented one of the Rmatrix code AMUR to treat this formula in FRENDY. The processing results of FRENDY are compared to those of NJOY2016 to verify FRENDY. The comparison results indicate that FRENDY appropriately treat the R-matrix limited formula with similar computational time.
Be systemThompson, I. J.*; deBoer, R. J.*; Dimitriou, P.*; Kunieda, Satoshi; Pigni, M. T.*; Arbanas, G.*; Leeb, H.*; Srdinko, Th.*; Hale, G.*; Tamagno, P.*; et al.
European Physical Journal A, 55(6), p.92_1 - 92_16, 2019/06
Times Cited Count：5 Percentile：72.04(Physics, Nuclear)In this paper we present, for the first time, the results of a comprehensive effort to verify the most widely used R-matrix codes in the various fields of nuclear science and applications: AMUR, AZURE2, CONRAD, EDA, FRESCO, GECCCOS, and SAMMY. In addition to the description of the capabilities of the codes and their specifications, we discuss the results of a joint exercise which was coordinated by the International Atomic Energy Agency. The aim of the exercise was to compare calculations of charged-particle reaction cross sections for the light composite system Be. The calculations were performed by the codes using identical input R-matrix parameters and other specifications and were limited to charged-particle channels.
Iwamoto, Osamu; Kunieda, Satoshi; Iwamoto, Nobuyuki
Isotope News, (763), p.4 - 7, 2019/06
no abstracts in English
Tada, Kenichi; Kunieda, Satoshi; Nagaya, Yasunobu
JAEA-Data/Code 2018-014, 106 Pages, 2019/01
JAEA-Data-Code-2018-014.pdf:1.76MB
JAEA-Data-Code-2018-014-appendix(DVD-ROM).zip:6.99MB
A new nuclear data processing code FRENDY has been developed in order to process the evaluated nuclear data library JENDL. Development of FRENDY helps to disseminate JENDL and various nuclear calculation codes. FRENDY is developed not only to process the evaluated nuclear data file but also to implement the FRENDY functions to other calculation codes. Users can easily use many functions e.g., read, write, and process the evaluated nuclear data file, in their own codes when they implement the classes of FRENDY to their codes. FRENDY is coded with considering maintainability, modularity, portability and flexibility. The processing method of FRENDY is similar to that of NJOY. The current version of FRENDY treats the ENDF-6 format and generates the ACE file which is used for the continuous energy Monte Carlo codes such as PHITS and MCNP. This report describes the nuclear data processing methods and input instructions for FRENDY.
Matsuda, Norihiro; Kunieda, Satoshi; Okamoto, Tsutomu*; Tada, Kenichi; Konno, Chikara
Progress in Nuclear Science and Technology (Internet), 6, p.225 - 229, 2019/01
Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Kahler, A. C.*; Talou, P.*; Plompen, A. J.*; Schillebeeckx, P.*; et al.
Nuclear Data Sheets, 148, p.189 - 213, 2018/02
Times Cited Count：49 Percentile：98.76(Physics, Nuclear)The CIELO collaboration has studied neutron cross sections on nuclides that significantly impact criticality in nuclear facilities - 
U, 
U, 
Pu, 
Fe, 
O and 
H - with the aim of improving the accuracy of the data and resolving previous discrepancies in our understanding. This multi-laboratory pilot project, coordinated via the OECD/NEA Working Party on Evaluation Cooperation (WPEC) Subgroup 40 with support also from the IAEA, has motivated experimental and theoretical work and led to suites of new evaluated libraries that accurately reflect measured data and also perform well in integral simulations of criticality. This report summarizes our results and outlines plans for the next phase of this collaboration.
Sanami, Toshiya*; Nishio, Katsuhisa; Hagiwara, Masayuki*; Iwase, Hiroshi*; Kunieda, Satoshi; Nakamura, Shoji
JAEA-Conf 2017-001, 222 Pages, 2018/01
JAEA-Conf-2017-001.pdf:30.89MB
The 2016 Symposium on Nuclear Data was held at Kobayashi Hall of High Energy Accelerator Research Organization, on November 17 and 18, 2016. The symposium was organized by the Nuclear Data Division of the Atomic Energy Society of Japan in cooperation with Radiation Science Center, High Energy Accelerator Research Organization, Nuclear Science and Engineering Center of Japan Atomic Energy Agency and North Kanto Branch of Atomic Energy Society of Japan. In the symposium, there were one tutorial, "Historical Evolution of Accelerators" and four oral sessions, "Overview of the ImPACT Program - Reduction and Resource Recycling of High Level Wastes through Nuclear Transmutation", "Facilities and experiments for nuclear data in Japan", "Nuclear data from measurement to application", and "Progress of neutron nuclear data measurement and research for its basics and application". In addition, recent research progress on experiments, evaluation, benchmark and application was presented in the poster session. Among 65 participants, all presentations and following discussions were very active and fruitful. This report consists of total 31 papers including 10 oral and 21 poster presentations.
Kimura, Atsushi; Harada, Hideo; Kunieda, Satoshi; Katabuchi, Tatsuya*
Nihon Genshiryoku Gakkai-Shi ATOMO
, 59(11), p.654 - 658, 2017/11
no abstracts in English
Suyama, Kenya; Kunieda, Satoshi; Fukahori, Tokio; Chiba, Go*
Nihon Genshiryoku Gakkai-Shi ATOMO, 59(10), p.598 - 602, 2017/10
The nuclear data is the data on the reaction probability between the neutron and the nuclide in a narrow sense. However generally speaking, it is the data describing the physical change of the nuclide and the status of the nuclear ration. Since Japan had started the nuclear energy development, the nuclear data has been one of the most important technical development theme. Now, the nuclear data library of Japan, i.e., JENDL, is well recognized internationally because of the highest-accuracy and fully-furnished types of the included data. This serial lecture describes the significance and the status of the nuclear data development, the international trend, and the direction of the future development.
Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio
EPJ Web of Conferences, 146, p.02028_1 - 02028_5, 2017/09
Times Cited Count：0 Percentile：0.08JAEA has started to develop new nuclear data processing system FRENDY (FRom Evaluated Nuclear Data libralY to any application). In this presentation, the outline of the development of FRENDY is presented. And functions and performances of FRENDY are demonstrated by generation and validation of the continuous energy cross section data libraries for MVP, PHITS and MCNP codes.
Minato, Futoshi; Iwamoto, Osamu; Minomo, Kosho*; Ogata, Kazuyuki*; Iwamoto, Nobuyuki; Kunieda, Satoshi; Furutachi, Naoya
EPJ Web of Conferences, 146, p.12032_1 - 12032_4, 2017/09
Times Cited Count：1 Percentile：69.68Phenomenological optical potential is known to be able to describe the elastic scattering process. It is applied widely to the nuclear data evaluation of the cross section. Many kinds of the optical potential have been studied so far. However, the parameters in the phenomenological optical potentials are determined so as to reproduce existing experimental data, so that use of it for unmeasured nuclei such as neutron-rich nuclei is not necessarily reliable. Recently, a new optical potential derived from the microscopic effective reaction theory (MERT) was proposed. Since the formulation of MERT is based on the NN effective interaction, any parameterizations in the optical potential aren't needed. Therefore, it is capable of calculating nuclei whose scattering cross section isn't measured. We incorporate the optical potentials of MERT in code CCONE and start nuclear data evaluation of several nuclei. In this work, we discuss difference of cross sections evaluated by MERT's optical potentials and conventional phenomenological ones.
Iwamoto, Osamu; Shibata, Keiichi; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Ichihara, Akira; Nakayama, Shinsuke
EPJ Web of Conferences, 146, p.02005_1 - 02005_6, 2017/09
Times Cited Count：0 Percentile：0.08Kunieda, Satoshi
EPJ Web of Conferences, 146, p.12029_1 - 12029_4, 2017/09
Times Cited Count：4 Percentile：95.35The cross-sections on the light-nuclei are drawing attention for the ion-beam analysis, the astrophysics and the medical applications and so on. However, there still exist inconsistencies between the measured and evaluated data, which could bring a large uncertainty in the practical applications. The R-matrix formalism is rigorous and straightforward to the quantum mechanics, in which the S-matrix is deduced from the measured cross-sections in the resonance energy region. We present the status of the code with new features on the theoretical calculation and the correction for the measurements. Some example evaluations are also presented for the p + Li reaction. Especially, we focus on the covariance analysis on the resonance parameters and the cross-sections. This is relevant not only to the estimation of the cross-sections uncertainty but also to visualizing natures in the resonant reactions.
Chadwick, M. B.*; Capote, R.*; Trkov, A.*; Kahler, A. C.*; Herman, M. W.*; Brown, D. A.*; Hale, G. M.*; Pigni, M.*; Dunn, M.*; Leal, L.*; et al.
EPJ Web of Conferences, 146, p.02001_1 - 02001_9, 2017/09
Times Cited Count：6 Percentile：97.85The CIELO collaboration has studied neutron cross sections on nuclides (O, Fe, 
U and Pu) that significantly impact criticality in nuclear technologies with the aim of improving the accuracy of the data and resolving previous discrepancies in our understanding. This multi-laboratory pilot project, coordinated via the OECD/NEA Working Party on Evaluation Cooperation (WPEC) Subgroup 40 with support also from the IAEA, has motivated experimental and theoretical work and led to suites of new evaluated libraries that accurately reflect measured data and also perform well in integral simulations of criticality.
Carlson, A. D.*; Pronyaev, V.*; Hale, G. M.*; Zhenpeng, C.*; Capote, R.*; Dur
n, I.*; Hambsch, F.-J.*; Kawano, Toshihiko*; Kunieda, Satoshi; 13 of others*
EPJ Web of Conferences, 146, p.02025_1 - 02025_4, 2017/09
Times Cited Count：4 Percentile：95.35Evaluations are being done for the 
H(n,n), 
Li(n,t), 
B(n,
), B(n,
), C(n,n), 
Au(n,
), U(n,f) and U(n,f) standard cross sections. Evaluations are also being done for data that are not traditional standards including: the Au(n,) cross section at energies below where it is considered a standard; reference cross sections for prompt -ray production in fast neutron-induced reactions; reference cross sections for very high energy fission cross sections; the U thermal neutron fission spectrum and the 
Cf spontaneous fission neutron spectrum and the thermal constants.
Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio
Journal of Nuclear Science and Technology, 54(7), p.806 - 817, 2017/07
Times Cited Count：21 Percentile：95.6(Nuclear Science & Technology)JAEA has developed an evaluated nuclear data library JENDL and several nuclear analysis codes such as MARBLE2, SRAC, MVP and PHITS. Though JENDL and these computer codes have been widely used in many countries, the nuclear data processing system to generate the data library for application programs had not been developed in Japan and foreign nuclear data processing systems, e.g., NJOY and PREPRO are used. To process the new library for JAEA's computer codes immediately and independently, JAEA started to develop the new nuclear data processing system FRENDY in 2013. In this paper, outline, function, and verification of FRENDY are described.
Iwamoto, Osamu; Sanami, Toshiya*; Kunieda, Satoshi; Koura, Hiroyuki; Nakamura, Shoji
JAEA-Conf 2016-004, 247 Pages, 2016/09
JAEA-Conf-2016-004.pdf:26.48MB
The 2015 Symposium on Nuclear Data was held at Ibaraki Quantum Beam Research Center, on November 19 and 20, 2015. The symposium was organized by the Nuclear Data Division of the Atomic Energy Society of Japan in cooperation with Nuclear Science and Engineering Center of Japan Atomic Energy Agency and North Kanto Branch of Atomic Energy Society of Japan. In the symposium, there were two tutorials, "Theory of Few-Body Systems and Recent Topics" and "Use of Covariance Data 2015" and four oral sessions, "Recent Research Topics", "Progress of AIMAC Project", "Present Status of JENDL Evaluated Files", and "Nuclear Data Applications". In addition, recent research progress on experiments, evaluation, benchmark and application was presented in a poster session. Among 99 participants, all presentations and following discussions were very active and fruitful. This report consists of total 46 papers including 13 oral and 33 poster presentations.
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.
