Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 41

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

Journal Articles

Deuteron nuclear data for the design of accelerator-based neutron sources: Measurement, model analysis, evaluation, and application

Watanabe, Yukinobu*; Kin, Tadahiro*; Araki, Shohei*; Nakayama, Shinsuke; Iwamoto, Osamu

EPJ Web of Conferences (Internet), 146, p.03006_1 - 03006_6, 2017/09

 Percentile:100

The design of $$(d,xn)$$ neutron sources requires comprehensive nuclear data of deuteron-induced reactions. Therefore, we have launched a research project on deuteron nuclear data, which is composed of measurements, theoretical model code development, cross section evaluation, and application to production of radioisotopes for medical use. Our goal is to develop a state-of-art deuteron nuclear data library up to 200 MeV necessary for the design of accelerator neutron sources with deuteron beam. The present status is reported in the presentation.

Journal Articles

Development of a code system DEURACS for theoretical analysis and prediction of deuteron-induced reactions

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

EPJ Web of Conferences (Internet), 146, p.12025_1 - 12025_4, 2017/09

 Times Cited Count:1 Percentile:14.04

Recently, intensive neutron sources using deuteron accelerator have been proposed for various applications. Accurate and comprehensive deuteron nuclear data library over wide ranges of target mass number and incident energy are indispensable for the design of deuteron accelerator neutron sources. Thus, we have developed an integrated code system dedicated for analysis and prediction of deuteron-induced reactions, which is called DEUteron-induced Reaction Analysis Code System (DEURACS). In the present work, the analysis of $$(d,xn)$$ reactions is extended to higher incident energy up to nearly 100 MeV and also DEURACS is applied to $$(d,xd)$$ reactions at 80 and 100 MeV. The DEURACS calculations reproduce the experimental double-differential cross sections for the $$(d,xn)$$ and $$(d,xd)$$ reactions well.

Journal Articles

Neutron production in deuteron-induced reactions on Li, Be, and C at an incident energy of 102 MeV

Araki, Shohei*; Watanabe, Yukinobu*; Kitajima, Mizuki*; Sadamatsu, Hiroki*; Nakano, Keita*; Kin, Tadahiro*; Iwamoto, Yosuke; Satoh, Daiki; Hagiwara, Masayuki*; Yashima, Hiroshi*; et al.

EPJ Web of Conferences (Internet), 146, p.11027_1 - 11027_4, 2017/09

 Percentile:100

In recently years, deuteron-induced reaction is considered to produce the neutron source for application fields such as radiation damage fusion materials and boron neutron capture therapy. However, as the experimental data are not sufficient at incident energies above 60 MeV, the theoretical models are not validated. Therefore, we measured the double differential cross sections (DDXs) for Li, Be and C at 100 MeV at the Research Center for Nuclear Physics in Osaka University. The DDXs were measured at 6 angles (0$$^{circ}$$$$sim$$25$$^{circ}$$ and neutron energy was determined by a time of flight method. Three different-size NE213 liquid organic scintillators located at a distance of 7 m, 24 m and 74 m respectively were adopted as neutron detectors. In the measured DDXs, a broad peak due to deuteron breakup process was observed at approximately half of the deuteron incident energy. The DDXs calculated by PHITS did not reproduce the experimental ones due to lack of theoretical model.

Journal Articles

FRENDY; A New nuclear date processing system being developed at JAEA

Tada, Kenichi; Nagaya, Yasunobu; Kunieda, Satoshi; Suyama, Kenya; Fukahori, Tokio

EPJ Web of Conferences (Internet), 146, p.02028_1 - 02028_5, 2017/09

 Percentile:100

JAEA 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.

Journal Articles

Nuclear data evaluation of long-lived fission products; Microscopic vs. phenomenological optical potentials

Minato, Futoshi; Iwamoto, Osamu; Minomo, Kosho*; Ogata, Kazuyuki*; Iwamoto, Nobuyuki; Kunieda, Satoshi; Furutachi, Naoya

EPJ Web of Conferences (Internet), 146, p.12032_1 - 12032_4, 2017/09

 Percentile:100

Phenomenological 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.

Journal Articles

Technical developments for accurate determination of amount of samples used for TOF measurements

Terada, Kazushi; Nakao, Taro; Nakamura, Shoji; Kimura, Atsushi; Iwamoto, Osamu; Harada, Hideo; Takamiya, Koichi*; Hori, Junichi*

EPJ Web of Conferences (Internet), 146, p.03019_1 - 03019_4, 2017/09

 Times Cited Count:2 Percentile:4.05

The research project entitled "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)" has been started to improve the reliability of the neutron cross section date of MAs. In order to obtain accurate cross section data, it is indispensable to determine the amount of MA sample accurately and non-destructively. However, the uncertainty concerning the amount of sample is not assured in some cases. Therefore, as a part of the AIMAC project, this study is aimed to development the technique for accurate determination of the amount of samples by two different methods: $$gamma$$-ray spectroscopic method and calorimetric method. This contribution presents the developed techniques together with results obtained by two independent techniques.

Journal Articles

Application of modified REFIT code for J-PARC/MLF to evaluation of neutron capture cross section on $$^{155,157}$$Gd

Mizuyama, Kazuhito; Iwamoto, Nobuyuki; Iwamoto, Osamu; Hasemi, Hiroyuki*; Kino, Koichi*; Kimura, Atsushi; Kiyanagi, Yoshiaki*

EPJ Web of Conferences (Internet), 146, p.11042_1 - 11042_4, 2017/09

 Percentile:100

Gadolinium has been used as neutron-absorbing material in a thermal reactor since $$^{155,157}$$ have large thermal neutron capture cross sections. Nevertheless, there is a discrepancy between RPI data and JENDL-4.0 data for $$^{157}$$Gd. The criticality in the reactor is very sensitive to the capture cross section. The RPI data made the criticality of Gd-loaded thermal systems in ICSBEP overestimated. Recently, the neutron capture cross sections of $$^{155,157}$$Gd were measured by the neutron time-of-flight (TOF) method using the Accurate Neutron-Nucleus Reaction measurement Instrument (ANNRI) in the J-PARC/MLF. The pulsed neutron beam from the Japan Spallation Neutron Source (JSNS) was used with a double-bunch structure in this measurement, since the incident proton beam is normally delivered in a double-bunch scheme in the J-PARC. In addition to this, it is necessary to take into account the energy resolution of the pulsed neutron beam at the JSNS for the accurate derivation of resolved resonance parameters. In this study, using the least-squares multilevel R-matrix code REFIT modified to include the double bunch structure and the resolution function for the ANNRI, we fitted the calculated capture cross sections of $$^{155,157}$$Gd to the experimental data at the ANNRI. We derived the resonance parameters for some low-lying resonances of the two Gd isotopes.

Journal Articles

Neutron capture cross section measurements of $$^{120}$$Sn, $$^{122}$$Sn and $$^{124}$$Sn with the array of Ge spectrometer at the J-PARC/MLF/ANNRI

Kimura, Atsushi; Harada, Hideo; Nakamura, Shoji; Toh, Yosuke; Igashira, Masayuki*; Katabuchi, Tatsuya*; Mizumoto, Motoharu*; Hori, Junichi*

EPJ Web of Conferences (Internet), 146, p.11031_1 - 11031_4, 2017/09

 Percentile:100

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

 Percentile:100

Journal Articles

Status of the R-matrix code AMUR toward a consistent cross-section evaluation and covariance analysis for the light nuclei

Kunieda, Satoshi

EPJ Web of Conferences (Internet), 146, p.12029_1 - 12029_4, 2017/09

 Percentile:100

The 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 + $$^7$$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.

Journal Articles

Inter-comparison of Hauser-Feshbach model codes toward better actinide evaluations

Capote, R.*; Hilaire, S.*; Iwamoto, Osamu; Kawano, Toshihiko*; Sin, M.*

EPJ Web of Conferences (Internet), 146, p.12034_1 - 12034_4, 2017/09

 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:4.05

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

Research and development for accuracy improvement of neutron nuclear data on minor actinides

Harada, Hideo; Iwamoto, Osamu; Iwamoto, Nobuyuki; Kimura, Atsushi; Terada, Kazushi; Nakao, Taro; Nakamura, Shoji; Mizuyama, Kazuhito; Igashira, Masayuki*; Katabuchi, Tatsuya*; et al.

EPJ Web of Conferences (Internet), 146, p.11001_1 - 11001_6, 2017/09

 Times Cited Count:1 Percentile:14.04

Journal Articles

Improving nuclear data accuracy of $$^{241}$$ Am and $$^{237}$$ Np capture cross sections

$v{Z}$erovnik, G.*; Schillebeeckx, P.*; Cano-Ott, D.*; Jandel, M.*; Hori, Junichi*; Kimura, Atsushi; Rossbach, M.*; Letourneau, A.*; Noguere, G.*; Leconte, P.*; et al.

EPJ Web of Conferences (Internet), 146, p.11035_1 - 11035_4, 2017/09

 Times Cited Count:2 Percentile:4.05

Journal Articles

Analysis of energy resolution in the KURRI-LINAC pulsed neutron facility

Sano, Tadafumi*; Hori, Junichi*; Takahashi, Yoshiyuki*; Yashima, Hiroshi*; Lee, J.*; Harada, Hideo

EPJ Web of Conferences (Internet), 146, p.03031_1 - 03031_3, 2017/09

 Times Cited Count:1 Percentile:14.04

Journal Articles

High precision analysis of isotopic composition for samples used for nuclear cross-section measurements

Shibahara, Yuji*; Hori, Junichi*; Takamiya, Koichi*; Fujii, Toshiyuki*; Fukutani, Satoshi*; Sano, Tadafumi*; Harada, Hideo

EPJ Web of Conferences (Internet), 146, p.03028_1 - 03028_4, 2017/09

 Percentile:100

Journal Articles

Delayed $$gamma$$-ray spectroscopy combined with active neutron interrogation for nuclear security and safeguards

Koizumi, Mitsuo; Rossi, F.; Rodriguez, D.; Takamine, Jun; Seya, Michio; Bogucarska, T.*; Crochemore, J.-M.*; Varasano, G.*; Abbas, K.*; Pedersen, B.*; et al.

EPJ Web of Conferences (Internet), 146, p.09018_1 - 09018_4, 2017/09

 Percentile:100

Journal Articles

Neutron resonance analysis for nuclear safeguards and security applications

Paradela, C.*; Heyse, J.*; Kopecky, S.*; Schillebeeckx, P.*; Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Tsuchiya, Harufumi

EPJ Web of Conferences (Internet), 146, p.09002_1 - 09002_4, 2017/09

 Percentile:100

Journal Articles

Evaluation of neutron total and capture cross sections on $$^{99}$$Tc in the unresolved resonance region

Iwamoto, Nobuyuki; Katabuchi, Tatsuya*

EPJ Web of Conferences (Internet), 146, p.02049_1 - 02049_4, 2017/09

 Percentile:100

Journal Articles

Influence of the neutron transport tube on neutron resonance densitometry

Kitatani, Fumito; Tsuchiya, Harufumi; Koizumi, Mitsuo; Takamine, Jun; Hori, Junichi*; Sano, Tadafumi*

EPJ Web of Conferences (Internet), 146, p.09032_1 - 09032_3, 2017/09

 Percentile:100

41 (Records 1-20 displayed on this page)