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Journal Articles

Development of the standard evaluated database of nuclear reactions for long lived fission products

Iwamoto, Osamu

ImPACT Fujita Puroguramu Kokai Seika Hokokukai "Kaku Henkan Niyoru Koreberu Hoshasei Haikibutsu No Ohaba Na Teigen, Shigenka" Seika Hokokusho, Shiryoshu, p.102 - 105, 2019/03

Study on the development of the standard evaluated database of nuclear reactions for long lived fission products has been conducted as a part of the ImPACT Fujita Program titled "Reduction and Resource Recycling of High-level Radioactive Wastes through Nuclear Transmutation". The database of the neutron and proton induced reactions on LLFPs and their neighbor nuclei has been developed taking account of the up-to-date theoretical and experimental knowledges. In addition, the update of the calculation methods of deuteron induced reactions has also conducted. Summary of this study will be reported.

Journal Articles

Measurements of gamma-ray emission probabilities in the decay of americium-244g

Nakamura, Shoji; Terada, Kazushi*; Kimura, Atsushi; Nakao, Taro*; Iwamoto, Osamu; Harada, Hideo; Uehara, Akihiro*; Takamiya, Koichi*; Fujii, Toshiyuki*

Journal of Nuclear Science and Technology, 56(1), p.123 - 129, 2019/01

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

Accurate data of $$gamma$$-ray emission probabilities are frequently needed when one quantitatively determines the amount of isotope by $$gamma$$-ray measurements or obtains neutron capture cross-sections using them. Americium-243, one of the most important minor actinides, produces $$^{244}$$Am after neutron capture. The 744-keV $$gamma$$-ray decaying from the ground state of $$^{244}$$Am has a relatively large $$gamma$$-ray emission probability c.a. 66%, however, its uncertainty is as large as 29%. The uncertainty of the $$gamma$$-ray emission probability leads to a major factor of the systematic uncertainty on determining an amount of isotope, and therefore the $$gamma$$-ray emission probability was measured by using an activation method and an examined level structure of $$^{244}$$Cm. In this study, the emission probability of 744-keV $$gamma$$ ray was derived as 66.5$$pm$$1.1%, and its uncertainty was improved from 29% to 2%.

Journal Articles

Measurement of activation cross sections of aluminum for protons with energies between 0.4 GeV and 3.0 GeV at J-PARC

Matsuda, Hiroki; Meigo, Shinichiro; Iwamoto, Hiroki

Progress in Nuclear Science and Technology (Internet), 6, p.171 - 174, 2019/01

Activation cross sections of various materials are strongly required for the improvement of the accuracy of nuclear design and the reduction of the construction costs for spallation neutron sources and transmutation systems. Activation cross sections have been measured in several facilities. However, they have low accuracy and precision. Especially, there are merely experimental data with 3 GeV protons which are used for spallation neutron source (MLF) in J-PARC, the experimental data is required for the improvement of the target materials. Thus, we measured cross sections of tungsten, gold, indium, and beryllium with 0.4 GeV to 3.0 GeV protons. Moreover, ones of aluminium that are set with materials were also measured for a variation of this experiment. It was found that more accurate data than current ones would be measured by using precise beam controls and highly accurate beam monitoring. We compared the experimental data, the evaluated data (JENDL-HE/2007), and the calculations with several intra-nuclear cascade models by PHITS code. Although the experimental data agreed with JENDL-HE/2007, the calculations underestimated about 40%. This could come from the evaporation model (GEM) being included in PHITS code. We found that the calculations agreed with the experimental data by upgrading PHITS code. The cross sections for the other materials have been analysed so far.

Journal Articles

Present status and future plan of JENDL

Iwamoto, Osamu

JAEA-Conf 2018-001, p.87 - 91, 2018/12

Status and plan of JENDL will be presented. After the release of JENDL-4.0 in 2010, six special purpose files have been developed. Four of them were already released and two are under preparation for the release. New decay and yield data for fission products were released as JENDL/FPD-2011 and JENDL/FPY-2011 in 2011, respectively. JENDL-4.0/HE released in 2015 includes proton and neutron induced reaction data up to 200 MeV. Comprehensive decay data were released as JENDL/DDF-2015 which contains data for 3,237 nuclides. New photonuclear reaction data JENDL/PD-2016 and an activation file JENDL/AD-2017 are under preparation for release. Regarding general purpose file, two activities are in progress. One is JENL-4.0u which is created for maintenance of JENDL-4.0 and the other is development of next version of JENDL. For the next JENDL, evaluation for light nuclei and structure material are in progress. It is planed that next version of JENDL will be JENDL-5 which contains nuclear data for all nuclei having natural abundance. Addition of covariance data will be one of the main targets.

Journal Articles

Target test facility for ADS and cross-section experiment in J-PARC

Meigo, Shinichiro; Iwamoto, Hiroki; Matsuda, Hiroki; Takei, Hayanori

Journal of Physics; Conference Series, 1021(1), p.012072_1 - 012072_4, 2018/06

 Times Cited Count:0 Percentile:100

no abstracts in English

Journal Articles

Joint Session of Nuclear Data Subcommittee and Sigma Special Advisory Committee; Present status and future of nuclear data evaluation code in Japan, 3; Development of DEURACS for prediction of deuteron-induced reaction cross section

Nakayama, Shinsuke

Kaku Deta Nyusu (Internet), (120), p.19 - 25, 2018/06

Toward development of accurate deuteron nuclear data, we have been developing a computational code dedicated for the deuteron-induced reaction, called DEURACS. The author presented the developmental status and the future outlook of DEURACS in the joint session of nuclear data subcommittee and sigma special advisory committee, and contributed the outline of the presentation to Nuclear Data News. From our preceding work, it has become possible to predict the $$(d,xn)$$ reactions on light nuclei and the $$(d,xt)$$ reactions. These reactions are important in relation to evaluation of neutron sources and tritium production, respectively. In the future, we plan to improve theoretical models implemented in DEURACS for accurate prediction of nuclide production cross-section on medium-heavy nuclei.

Journal Articles

Measurement of displacement cross-section for structural materials in High-Power Proton Accelerator Facility

Meigo, Shinichiro; Matsuda, Hiroki; Iwamoto, Yosuke; Iwamoto, Hiroki; Hasegawa, Shoichi; Maekawa, Fujio; Yoshida, Makoto*; Ishida, Taku*; Makimura, Shunsuke*; Nakamoto, Tatsushi*

Proceedings of 9th International Particle Accelerator Conference (IPAC '18) (Internet), p.499 - 501, 2018/06

no abstracts in English

Journal Articles

Cross section measurement in J-PARC for neutronics of the ADS

Meigo, Shinichiro; Matsuda, Hiroki; Iwamoto, Hiroki

Proceedings of 13th International Topical Meeting on Nuclear Applications of Accelerators (AccApp '17) (Internet), p.396 - 402, 2018/05

no abstracts in English

Journal Articles

Cutting-edge studies on nuclear data for continuous and emerging need, 6; Processing and validation of nuclear data

Tada, Kenichi; Kosako, Kazuaki*; Yokoyama, Kenji; Konno, Chikara

Nippon Genshiryoku Gakkai-Shi, 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.

Journal Articles

Theoretical model analysis of $$(d,xn)$$ reactions on $$^7$$Li at 25, 40, and 102 MeV

Sadamatsu, Hiroki*; Nakayama, Shinsuke; Watanabe, Yukinobu*; Iwamoto, Osamu; Ogata, Kazuyuki*

JAEA-Conf 2017-001, p.135 - 140, 2018/01

In recent years, the demand for intense neutron sources has been increasing in various applications such as nuclear transmutation of high-level radioactive waste and medical radioisotopes production. Deuteron accelerator-based neutron sources are promised as one of the candidates. Therefore, we have developed a code system dedicated for the deuteron-induced reactions, called DEURACS. In the present work, we focus on deuteron-induced neutron production from $$^7$$Li target. The calculated double differential cross sections for $$(d,xn)$$ reactions at incident energies of 25, 40, and 102 MeV are compared with the measured ones, and the applicability of DEURACS is discussed.

Journal Articles

Determination of fusion barrier distributions from quasielastic scattering cross sections towards superheavy nuclei synthesis

Tanaka, Taiki*; Narikiyo, Yoshihiro*; Morita, Kosuke*; Fujita, Kunihiro*; Kaji, Daiya*; Morimoto, Koji*; Yamaki, Sayaka*; Wakabayashi, Yasuo*; Tanaka, Kengo*; Takeyama, Mirei*; et al.

Journal of the Physical Society of Japan, 87(1), p.014201_1 - 014201_9, 2018/01

 Times Cited Count:4 Percentile:35(Physics, Multidisciplinary)

Excitation functions of quasielastic scattering cross sections for the $$^{48}$$Ca + $$^{208}$$Pb, $$^{50}$$Ti + $$^{208}$$Pb, and $$^{48}$$Ca + $$^{248}$$Cm reactions were successfully measured by using the gas-filled recoil-ion separator GARIS. Fusion barrier distributions were extracted from these data, and compared with the coupled-channels calculations. It was found that the peak energies of the barrier distributions for the $$^{48}$$Ca + $$^{208}$$Pb and $$^{50}$$Ti + $$^{208}$$Pb systems coincide with those of the 2n evaporation channel cross sections for the systems, while that of the $$^{48}$$Ca + $$^{248}$$Cm is located slightly below the 4n evaporation ones. This results provide us helpful information to predict the optimum beam energy to synthesize superheavy nuclei.

Journal Articles

Status of the JENDL project

Iwamoto, Osamu; Shibata, Keiichi; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Ichihara, Akira; Nakayama, Shinsuke

EPJ Web of Conferences (Internet), 146, p.02005_1 - 02005_6, 2017/09

 Times Cited Count:0 Percentile:100

Journal Articles

Developments of a new data acquisition system at ANNRI

Nakao, Taro; Terada, Kazushi; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Harada, Hideo; Katabuchi, Tatsuya*; Igashira, Masayuki*; Hori, Junichi*

EPJ Web of Conferences (Internet), 146, p.03021_1 - 03021_4, 2017/09

 Times Cited Count:2 Percentile:5.7

A new data acquisition system (DAQ system) in J-PARC Materials and Life Science Experimental Facility (MLF) ANNRI was developed. Increasing beam power of MLF in recent years allows beam line users to obtain high quantity experimental data yields. Compared to 2008, more than 20 times beam current is achieved in 2015. For the purpose to correspond strong beam power of MLF, a new DAQ system for the array of the Ge detectors in ANNRI is developed. The DAQ system is also going to be used for processing signals from a Li glass detector, which is under development at ANNRI for measurement of total neutron cross sections. Commissioning experiment of a new DAQ system at ANNRI was performed by using 0.1mmt Au sample with 500kW J-PARC proton beam power. An applicability of time-of-flight method for both neutron capture and total cross-sections measurements was checked. ADC and TDC nonlinearity, energy resolution, multi-channel coincidence and dead time performance for the array of the Ge detectors were also evaluated. The dead time value for Ge detectors was successfully decreased to 1/4 from the previous DAQ system with minor deterioration on energy resolution. The author would like to thank the accelerator and technical staff at J-PARC for operation of the accelerator and the neutron production target and for the other experimental supports. Present study includes the result of "Research and Development for accuracy improvement of neutron nuclear data on minor actinides" entrusted to the Japan Atomic Energy Agency by the Ministry of Education, Culture, Sports, Science and Technology of Japan (MEXT).

Journal Articles

Measurement of aluminum activation cross section and gas production cross section for 0.4 and 3-GeV protons

Meigo, Shinichiro; Nishikawa, Masaaki; Iwamoto, Hiroki; Matsuda, Hiroki

EPJ Web of Conferences (Internet), 146, p.11039_1 - 11039_4, 2017/09

 Times Cited Count:0 Percentile:100

no abstracts in English

Journal Articles

Evaluation of neutron nuclear data on platinum isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 54(2), p.147 - 157, 2017/02

 Times Cited Count:1 Percentile:73.02(Nuclear Science & Technology)

Neutron nuclear data on platinum isotopes have been evaluated for the next version of Japanese Evaluated Nuclear Data Library general-purpose file in the energy region from $$10^{-5}$$ eV to 20 MeV. Resolved resonance parameters of naturally-occurring isotopes were taken from the compilation work of Mughabghab. Unresolved resonance parameters were obtained by fitting to the total and capture cross sections calculated from nuclear models. A statistical model code CCONE was applied to evaluate cross sections above the resolved resonance region. Compound, pre-equilibrium and direct-reaction processes were considered for cross-section calculation. Coupled-channel optical model parameters were employed for the interaction between neutrons and nuclei. The present results reproduce experimental data very well, and are much better than the existing evaluations. The evaluated data are compiled into ENDF-formatted data files.

Journal Articles

Evaluation of neutron nuclear data on mercury isotopes

Shibata, Keiichi

Journal of Nuclear Science and Technology, 53(10), p.1595 - 1607, 2016/10

 Times Cited Count:1 Percentile:79.42(Nuclear Science & Technology)

Neutron nuclear data on mercury isotopes have been evaluated for the next version of Japanese Evaluated Nuclear Data Library general-purpose file in the energy region from $$10^{-5}$$ eV to 20 MeV. Resolved resonance parameters of $$^{200,202}$$Hg were supplemented with the data which had not been considered in the previous library. Unresolved resonance parameters were obtained by fitting to the total and capture cross sections calculated from nuclear models. A statistical model code CCONE was applied to evaluate cross sections above the resolved resonance region. Compound, pre-equilibrium and direct-reaction processes were considered for cross-section calculation. Coupled-channel optical model parameters were employed for the interaction between neutrons and mercury isotopes except $$^{203}$$Hg. The present results reproduce experimental data very well, and are much better than the JENDL-4.0 evaluation. The evaluated data are compiled into ENDF-formatted data files.

Journal Articles

Activation cross-section file for decommissioning of LWRs

Shibata, Keiichi; Iwamoto, Nobuyuki; Kunieda, Satoshi; Minato, Futoshi; Iwamoto, Osamu

JAEA-Conf 2016-004, p.47 - 52, 2016/09

It is required to estimate radioactive products accurately for the decommissioning of LWRs. We have developed the neutron-induced activation cross-section file for this purpose. The products consist of 227 nuclides with half-lives larger than 30 days and 12 nuclides with very long half-lives. Target nuclei were selected by considering possible paths leading to the required products. The activation cross sections of these targets were taken from JENDL-4.0, JENDL/A-96 and the post JENDL-4.0 evaluations. As a result, we produced the activation cross-section file with 302 nuclides. Comparing with other evaluations, there exists a large difference especially for the capture cross sections leading to meta-stable states. The data will be released in FY2016 after achieving further improvements.

Journal Articles

Examination of the surrogate ratio method for the determination of the $$^{93}$$Zr(n,$$gamma$$)$$^{94}$$Zr cross section with $$^{90,92}$$Zr($$^{18}$$O,$$^{16}$$O)$$^{92,94}$$Zr reactions

Yan, S. Q.*; Li, Z. H.*; Wang, Y. B.*; Nishio, Katsuhisa; Makii, Hiroyuki; Su, J.*; Li, Y. J.*; Nishinaka, Ichiro; Hirose, Kentaro; Han, Y. L.*; et al.

Physical Review C, 94(1), p.015804_1 - 015804_5, 2016/07

 Times Cited Count:3 Percentile:57.57(Physics, Nuclear)

Journal Articles

Modelling and analysis of nucleon emission from deuteron-induced reactions at incident energies up to 100 MeV

Nakayama, Shinsuke; Kono, Hiroshi*; Watanabe, Yukinobu*; Iwamoto, Osamu; Ye, T.*; Ogata, Kazuyuki*

EPJ Web of Conferences (Internet), 122, p.04004_1 - 04004_9, 2016/06

 Times Cited Count:4 Percentile:6.9

In recent years, accelerator neutron sources using deuteron-induced reactions on $$^7$$Li, $$^9$$Be, $$^{12}$$C, etc., are proposed for applications in various fields. Engineering design of such facilities requires deuteron nuclear data in a broad incident energy range. We have developed a computational code system dedicated for deuteron nuclear data evaluation in combination with some theoretical models. The code system has been applied to analyses of double-differential $$(d,xp)$$ cross sections for $$^{12}$$C, $$^{27}$$Al, and $$^{58}$$Ni at incident energies up to 100 MeV. On the other hand, there is few experimental double-differential $$(d,xn)$$ cross sections. Therefore, double-differential thick target neutron yields for light nuclei such as $$^9$$Be and $$^{12}$$C are calculated and compared with experimental data. The presentation will show the validation result of the present modelling for nucleon emissions from deuteron-induced reactions through comparison with available experimental data.

Journal Articles

399 (Records 1-20 displayed on this page)