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Iwamoto, Osamu; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Nakayama, Shinsuke; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Nagaya, Yasunobu; Tada, Kenichi; et al.
EPJ Web of Conferences, 284, p.14001_1 - 14001_7, 2023/05
Times Cited Count：0 Percentile：0.21(Nuclear Science & Technology)Otsuka, Naohiko*; Iwamoto, Osamu
EPJ Web of Conferences, 284, p.08011_1 - 08011_4, 2023/05
Times Cited Count：2 Percentile：98.3(Nuclear Science & Technology)Tada, Kenichi; Endo, Tomohiro*
EPJ Web of Conferences, 284, p.14013_1 - 14013_4, 2023/05
Times Cited Count：0 Percentile：0.21(Nuclear Science & Technology)The self-shielding effect in the unresolved resonance region has a large impact on the fast- and intermediate-spectrum reactors. The probability table method is widely used for continuous-energy Monte Carlo calculation codes to treat the effect. In this method, a table provides the probability distribution of the cross-section for a nuclide in the given energy grid points. The table is generated by averaging with a lot of "ladders" which represent pseudo resonance structures. Though many nuclear data processing codes require the number of ladders as an input parameter to generate the probability table, an optimal number of ladders has not been investigated. Our previous study revealed that the suitable number of ladders depends on the nuclide and its resonance parameters. This result indicates that it is very difficult for users to find the optimal number of ladders. We developed the calculation method of the statistical uncertainty for the probability table generation.
Kodeli, I. A.*; Fleming, M.*; Cabellos, O.*; Leal, L.*; Celik, Y.*; Ding, Y.*; Jansky, B.*; Neudecker, D.*; Novak, E.*; Simakov, S.*; et al.
EPJ Web of Conferences, 284, p.15002_1 - 15002_8, 2023/05
Times Cited Count：1 Percentile：89.57(Nuclear Science & Technology)Working Party on International Nuclear Data Evaluation Co-operation Subgroup 47 (WPEC SG47) entitled "Use of Shielding Integral Benchmark Archive and Database for Nuclear Data Validation" was started in June 2019 with the objectives to promote more systematic and wider use of shielding benchmark experiments in nuclear data and transport code validation and development, to provide feedback on the Shielding Integral Benchmark Archive and Database (SINBAD). Complementing the database with new features was discussed, for example providing the nuclear data sensitivity profiles more systematically would facilitate and better guide the use of data, and the information on the geometry, (radiation source) and materials is expected to allow an easier and less error prone computational model preparation for different transport codes. Examples of the use and some views on future development of the SINBAD benchmark database will be presented in the paper.
Nakayama, Shinsuke; Iwamoto, Osamu; Sublet, J.-Ch.*
EPJ Web of Conferences, 284, p.14011_1 - 14011_4, 2023/05
JENDL-5, the latest version of the Japanese evaluated nuclear data library, includes several sub-libraries to contribute to various applications. In this paper, we outline the evaluation and validation of the deuteron reaction sub-library developed mainly for the design of accelerator-based neutron sources and the alpha-particle reaction sub-library developed mainly for use in the back-end field. As for the deuteron sub-library, the data for 
Li, 
Be, and 
C from JENDL/DEU-2020 were partially modified and adopted. The data up to 200 MeV for 
Al, 
Cu, and 
Nb, which are important as accelerator structural materials, were newly evaluated based on the calculations with the DEURACS code. As for the alpha-particle sub-library, the data up to 15 MeV for 18 light nuclides from Li to Si isotopes were evaluated based on the calculations with the CCONE code, and then only the neutron production cross sections were replaced with the data of JENDL/AN-2005. Validation on neutron yield by Monte Carlo transport simulations was performed for both sub-libraries. As a result, it was confirmed that the simulations based on the sub-libraries showed good agreement with experimental data.
Konno, Chikara; Kwon, Saerom*
EPJ Web of Conferences, 284, p.15010_1 - 15010_4, 2023/05
Times Cited Count：0 Percentile：0.21(Nuclear Science & Technology)For the JENDL development we analyzed the iron in-situ experiment at the DT neutron source facility FNS in JAEA with the two-dimensional Sn code DORT and the latest nuclear data libraries: JENDL-4.0, ENDF/B-VIII.0 and JEFF-3.3. As a result, we found that the result with ENDF/B-VIII.0 reproduced the measured data worse than those with JENDL-4.0 and JEFF-3.3 as follows: overestimation of neutron flux below a few keV, underestimation of the reaction rate of 
In(n,n')
In sensitive to neutrons above 0.3 MeV and underestimation of neutron flux above 10 MeV. Our detailed study specified that the inelastic scattering cross section of Fe-56 in ENDF/B-VIII.0 mainly caused the overestimation of neutron flux below a few keV and underestimation of the reaction rate of In(n,n')In and that the angular distribution data of the elastic scattering and the cross section of the (n,2n) reaction of 
Fe in ENDF/B-VIII.0 were the reason of the underestimation of neutron flux above 10 MeV.
Iwamoto, Hiroki; Nakano, Keita; Meigo, Shinichiro; Satoh, Daiki; Iwamoto, Yosuke; Sugihara, Kenta*; Nishio, Katsuhisa; Ishi, Yoshihiro*; Uesugi, Tomonori*; Kuriyama, Yasutoshi*; et al.
EPJ Web of Conferences, 284, p.01023_1 - 01023_4, 2023/05
Times Cited Count：0 Percentile：0.21(Nuclear Science & Technology)For accurate prediction of neutronic characteristics for accelerator-driven systems (ADS) and a source term of spallation neutrons for reactor physics experiments for the ADS at Kyoto University Critical Assembly (KUCA), we have launched an experimental program to measure nuclear data on ADS using the Fixed Field Alternating Gradient (FFAG) accelerator at Kyoto University. As part of this program, the proton-induced double-differential thick-target neutron-yields (TTNYs) and cross-sections (DDXs) for iron, lead, and bismuth have been measured with the time-of-flight (TOF) method. For each measurement, the target was installed in a vacuum chamber on the beamline and bombarded with 107-MeV proton beams accelerated from the FFAG accelerator. Neutrons produced from the targets were detected with stacked, small-sized neutron detectors for several angles from the incident beam direction. The TOF spectra were obtained from the detected signals and the FFAG kicker magnet's logic signals, where gamma-ray events were eliminated by pulse shape discrimination. Finally, the TTNYs and DDXs were obtained from the TOF spectra by relativistic kinematics. The measured TTNYs and DDXs were compared with calculations by the Monte Carlo transport code PHITS with its default physics model of INCL version 4.6 combined with GEM and those with the JENDL-4.0/HE nuclear data library.
Kunieda, Satoshi
EPJ Web of Conferences, 284, p.03014_1 - 03014_4, 2023/05
Times Cited Count：0 Percentile：0.21(Nuclear Science & Technology)For thorough understanding resonant theories and cause of discrepancies among different cross-section measurements, development of an R-matrix analysis code AMUR is being progressed. The code is organized by "theoretical" and "experimental" classes based on the object-oriented framework. In the theoretical class, with sharing the same compound nucleus, the independent distant poles can optionally be assumed for the simultaneous analysis of different projectile + nucleus pairs to see the relation between the channel radius and the theoretical background. In the experimental class, to simulate experimental conditions, calculated cross-sections can be corrected by the Doppler broadening, resolution functions, re-normalization, adding contaminant elements. I demonstrate some example analyses of measured cross-sections with AMUR both for the light and heavier nuclei to show effects of those new options. Also, preliminary results will be shown from analyses for experimental data of J-PARC/ANNRI.
Dimitriou, P.*; Chen, Z.*; deBoer, R. J.*; Hale, G.*; Kunieda, Satoshi; Leeb, H.*; Paris, M.*; Pigni, M. T.*; Srdinko, Th.*; Tamagno, P.*; et al.
EPJ Web of Conferences, 284, p.03002_1 - 03002_5, 2023/05
Times Cited Count：0 Percentile：0.21(Nuclear Science & Technology)Charged-particle-induced reactions at low energies in the resolved resonance region are important for applications such as ion beam analysis of materials and management of the nuclear fuels. However, the evaluated nuclear data libraries maintained by national or international coordinated efforts (ENDF, JEFF, JENDL, CENDL) are to date, incomplete as far as charged-particle- induced reactions in the resolved resonance region are concerned. The IAEA Nuclear Data Section is coordinating an international effort to (i) verify that the existing R-matrix codes are consistent, (ii) evaluate charged-particle cross sections in the resolved resonance region, (iii) produce evaluated nuclear data files for further processing and finally (iv) disseminate the evaluated data through general purpose evaluated nuclear data libraries. We present the results of the effort made thus far on (1) verification of the available R-matrix codes, minimization methods and calculation of covariances, (2) the evaluation of the compound system 
Be*, and (3) improving 
reaction data for the applications.
Watanabe, Yukinobu*; Sadamatsu, Hiroki*; Araki, Shohei; Nakano, Keita; Kawase, Shoichiro*; Kin, Tadahiro*; Iwamoto, Yosuke; Satoh, Daiki; Hagiwara, Masayuki*; Yashima, Hiroshi*; et al.
EPJ Web of Conferences, 284, p.01041_1 - 01041_4, 2023/05
Times Cited Count：0 Percentile：0.21(Nuclear Science & Technology)Intensive fast neutron sources using deuteron accelerators have been proposed for the study of medical RI production, radiation damage for fusion reactor materials, nuclear transmutation of radioactive waste, and so on. Neutron production data from various materials bombarded by deuterons are required for the design of such neutron sources. In the present work, we have conducted a systematic measurement of double-differential neutron production cross sections (DDXs) for a wide atomic number range of targets (Li, Be, C, Al, Cu, Nb, In, Ta, and Au) at an incident energy of 200 MeV in the Research Center for Nuclear Physics (RCNP), Osaka University. A deuteron beam accelerated to 200 MeV was transported to the neutron experimental hall and focused on a thin target foil. Emitted neutrons from the target were detected by two different-size EJ301 liquid organic scintillators located at two distances of 7 m and 20 m, respectively. The neutron DDXs were measured at six angles from 0
to 25). The neutron energy was determined by a conventional time-of-flight (TOF) method. The measured DDXs were compared with theoretical model calculations by the DEUteron-induced Reaction Analysis Code System (DEURACS) and PHITS. The result indicated that the DEURACS calculation provides better agreement with the measured DDXs than the PHITS calculation.
Iwamoto, Hiroki; Nakano, Keita*; Meigo, Shinichiro; Takeshita, Hayato; Maekawa, Fujio
EPJ Web of Conferences, 284, p.01033_1 - 01033_4, 2023/05
Times Cited Count：1 Percentile：0.21(Nuclear Science & Technology)no abstracts in English
Watanabe, Shoto*; Minato, Futoshi; Kimura, Masaaki*; Iwamoto, Nobuyuki
no journal, ,
Litaize, O.*; Piau, V.*; Chalil, A.*; Ogawa, Tatsuhiko; Chebboubi, A.*; Gook, A.*; Gunsing, F.*; Kessedjian, G.*; Lhuillier, D.*; Mancusi, D.*; et al.
no journal, ,
The Monte-Carlo code FIFRELIN was originally developed for the simulation of first chance fission of fissile nuclei. In this study, its interfaces to radiation transport code PHITS, extension for neutron capture reactions, and a function to calculate neutrinos from fission fragments were developed. In order to extend FIFRELIN for neutron capture reactions, accurate gamma-ray yield was obtained by tuning the level density considering the nuclide species and excitation energy. Accurate neutrino yield was obtained by adopting up-to-date database on the thermal neutron capture state. JAEA developed an interface of FIFRELIN to PHITS to perform new FIFRELIN benchmark using FIFRELIN-DCHAIN joint calculation.
