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Journal Articles

Neutron total and capture cross-section measurements of $$^{155}$$Gd and $$^{157}$$Gd in the thermal energy region with the Li-glass detectors and NaI(Tl) spectrometer installed in J-PARC$$cdot$$MLF$$cdot$$ANNRI

Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Rovira Leveroni, G.; Iwamoto, Osamu; Iwamoto, Nobuyuki; Harada, Hideo; Katabuchi, Tatsuya*; Terada, Kazushi*; Hori, Junichi*; et al.

Journal of Nuclear Science and Technology, 60(6), p.678 - 696, 2023/06

 Times Cited Count:2 Percentile:56.43(Nuclear Science & Technology)

Journal Articles

Angular correlation of the two gamma rays produced in the thermal neutron capture on gadolinium-155 and gadolinium-157

Goux, P.*; Glessgen, F.*; Gazzola, E.*; Singh Reen, M.*; Focillon, W.*; Gonin, M.*; Tanaka, Tomoyuki*; Hagiwara, Kaito*; Ali, A.*; Sudo, Takashi*; et al.

Progress of Theoretical and Experimental Physics (Internet), 2023(6), p.063H01_1 - 063H01_15, 2023/06

 Times Cited Count:0 Percentile:0.01(Physics, Multidisciplinary)

Journal Articles

Integral experiment of $$^{129}$$I(n, $$gamma$$) using fast neutron source in the "YAYOI" reactor

Nakamura, Shoji; Toh, Yosuke; Kimura, Atsushi; Hatsukawa, Yuichi*; Harada, Hideo

Journal of Nuclear Science and Technology, 59(7), p.851 - 865, 2022/07

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

The present study performed integral experiments of $$^{129}$$I using a fast-neutron source reactor "YAYOI" of the University of Tokyo to validate evaluated nuclear data libraries. The iodine-129 sample and flux monitors were irradiated by fast neutrons in the Glory hole of the YAYOI reactor. Reaction rates of $$^{129}$$I were obtained by measurement of decay gamma-rays emitted from $$^{130}$$I. The validity of the fast-neutron flux spectrum in the Glory hole was confirmed by the ${it C/E}$ ratios of the reaction rates of flux monitors. The experimental reaction rate of $$^{129}$$I was compared with that calculated with both the fast-neutron flux spectrum and evaluated nuclear data libraries. The present study revealed that the evaluated nuclear data of $$^{129}$$I cited in JENDL-4.0 should be reduced as much as 18% in neutron energies ranging from 10 keV to 3 MeV, and supported the reported data by Noguere ${it et al.}$ below 100 keV.

Journal Articles

Integral experiments of technetium-99 using fast-neutron source reactor "YAYOI"

Nakamura, Shoji; Hatsukawa, Yuichi*; Kimura, Atsushi; Toh, Yosuke; Harada, Hideo

Journal of Nuclear Science and Technology, 58(12), p.1318 - 1329, 2021/12

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

The present study performed fast-neutron capture cross-section measurement of $$^{99}$$Tc by an activation method using a fast-neutron source reactor "YAYOI" of the University of Tokyo. Technetium-99 samples were irradiated with reactor neutrons using a pneumatic system. Reaction rates of $$^{99}$$Tc were obtained by measuring decay gamma rays emitted from $$^{100}$$Tc. The neutron flux at an irradiation position was monitored with gold foils. The fast-neutron capture cross section of $$^{99}$$Tc at neutron energy of 85 keV was derived as 0.432$$pm$$0.023 barn by using the reaction rates of $$^{99}$$Tc, evaluated cross-section data and the fast-neutron flux spectrum of the YAYOI reactor. The present study agreed with the evaluated nuclear data library JENDL-4.0.

Journal Articles

Neutron capture cross sections of curium isotopes measured with ANNRI at J-PARC

Kawase, Shoichiro*; Kimura, Atsushi; Harada, Hideo; Iwamoto, Nobuyuki; Iwamoto, Osamu; Nakamura, Shoji; Segawa, Mariko; Toh, Yosuke

Journal of Nuclear Science and Technology, 58(7), p.764 - 786, 2021/07

 Times Cited Count:1 Percentile:32.89(Nuclear Science & Technology)

Journal Articles

High-spin states in $$^{35}$$S

Go, Shintaro*; Ideguchi, Eiji*; Yokoyama, Rin*; Aoi, Nori*; Azaiez, F.*; Furutaka, Kazuyoshi; Hatsukawa, Yuichi; Kimura, Atsushi; Kisamori, Keiichi*; Kobayashi, Motoki*; et al.

Physical Review C, 103(3), p.034327_1 - 034327_8, 2021/03

 Times Cited Count:4 Percentile:58.42(Physics, Nuclear)

JAEA Reports

Development of MIG2DF Version 2

Takai, Shizuka; Kimura, Hideo*; Uchikoshi, Emiko*; Munakata, Masahiro; Takeda, Seiji

JAEA-Data/Code 2020-007, 174 Pages, 2020/09

JAEA-Data-Code-2020-007.pdf:4.23MB

The MIG2DF computer code is a computer program that simulates groundwater flow and radionuclide transport in porous media for the safety assessment of radioactive waste disposal. The original version of MIG2DF was released in 1992. The original code employs a two-dimensional (vertical or horizontal cross-section, or an axisymmetric configuration) finite-element method to approximate the governing equations for density-dependent saturated-unsaturated groundwater flow and radionuclide transport. Meanwhile, for geological disposal of radioactive wastes, landscape evolution such as uplift and erosion needs to be assessed as a long-term geological and climate events, considering site conditions. In coastal areas, the impact to groundwater flow by change of salinity distribution to sea level change also needs to be considered. To deal with these events in the assessment, we have revised the original version of MIG2DF and developed the external program which enables MIG2DF to consider unsteady landscape evolution. In these developments, this report describes an upgrade of MIG2DF (Version 2) and presents the configuration, equations, methods, and verification. This reports also give the explanation external programs of MIG2DF: PASS-TRAC (the particle tracking code), PASS-PRE (the code for dataset preparation), and PASS-POST (the post-processing visualization system).

Journal Articles

HPRL; International cooperation to identify and monitor priority nuclear data needs for nuclear applications

Dupont, E.*; Bossant, M.*; Capote, R.*; Carlson, A. D.*; Danon, Y.*; Fleming, M.*; Ge, Z.*; Harada, Hideo; Iwamoto, Osamu; Iwamoto, Nobuyuki; et al.

EPJ Web of Conferences, 239, p.15005_1 - 15005_4, 2020/09

 Times Cited Count:5 Percentile:99.59

JAEA Reports

Investigation of the function of RPA software and examination of its application to JAEA's work

Kimura, Hideo; Takita, Hayato

JAEA-Technology 2020-002, 50 Pages, 2020/05

JAEA-Technology-2020-002.pdf:5.03MB

Japan Atomic Energy Agency is strongly promoting business process re-engineering (BPR) of the entire organization in order to achieve more efficient, centralized and IT-style work. As part of this BPR, we have been studying the introduction of robotic process automation (RPA), which has been making remarkable progress in recent years, in order to further streamline and improve efficiency mainly for administrative work. In order to implement an appropriate RPA, the characteristics of each RPA software were clarified by investigating the functions of major RPA software and developing sample robots. Furthermore, we categorized various tasks that are expected to utilize RPA software and examined the application of RPA software to each business pattern.

Journal Articles

Dose estimation for contaminated soil storage in living environment

Takai, Shizuka; Shimada, Asako; Sawaguchi, Takuma; Takeda, Seiji; Kimura, Hideo

Radiation Protection Dosimetry, 188(1), p.1 - 7, 2020/01

 Times Cited Count:0 Percentile:0.01(Environmental Sciences)

After the Fukushima Nuclear Power Plant accident, most of radiocesium-contaminated soil generated from decontamination activities outside Fukushima prefecture has been stored at decontamination sites such as schools, parks and residential lands (storage at sites) according to the Decontamination Guidelines. However, additional exposure due to the present storage has not been evaluated. Moreover, entering storage sites, which is not restricted for storage at sites, was not considered in safety assessment conducted in the guidelines. To continue the storage and confirm the effectiveness, understanding of present possible exposures is important. In this study, we evaluated exposure doses for residents and users of storage sites based on the present situation. As a result, annual doses due to residence were 10$$^{-2}$$ to 10$$^{-3}$$ mSv y$$^{-1}$$ and doses due to annual entries were of the order of 10$$^{-3}$$ mSv y$$^{-1}$$. Hence, we confirmed that the exposure due to present storage outside Fukushima is significantly less than 1 mSv y$$^{-1}$$.

Journal Articles

Measurement of the $$^{235}$$U(n, f) cross section relative to the $$^{6}$$Li(n, t) and $$^{10}$$B(n, $$alpha$$) standards from thermal to 170 keV neutron energy range at n_TOF

Amaducci, S.*; Harada, Hideo; Kimura, Atsushi; 118 of others*

European Physical Journal A, 55(7), p.120_1 - 120_19, 2019/07

 Times Cited Count:18 Percentile:90.63(Physics, Nuclear)

The $$^{235}$$U(n, f) cross section was measured at n_TOF relative to $$^{6}$$Li(n, t) and $$^{10}$$B(n, $$alpha$$), in a wide energy range (25 meV$$sim$$170 keV) with 1.5% systematic uncertainty, making use of a stack of six samples and six silicon detectors placed in the neutron beam. The present results indicate that the cross section in the 9$$sim$$18 keV neutron energy range is indeed overestimated by almost 5% in the recently released evaluated data files ENDF/B-VIII.0 and JEFF3.3. Furthermore, these new high-resolution data confirm the existence of resonance-like structures in the keV neutron energy region. From the present data, a value of 249.7$$pm$$1.4(stat)$$pm$$0.94(syst) b eV has been extracted for the cross section integral between 7.8 and 11 eV, confirming the value of 247.5$$pm$$3 b eV recently established as a standard.

Journal Articles

Measurements of the $$^{243}$$Am neutron capture and total cross sections with ANNRI at J-PARC

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

Journal of Nuclear Science and Technology, 56(6), p.479 - 492, 2019/06

 Times Cited Count:11 Percentile:85.03(Nuclear Science & Technology)

JAEA Reports

Technical report on the development of finance and contract information system Ver.4

Kimura, Hideo; Hikasa, Naoki*; Kugenuma, Yuji*; Doi, Toshiharu*; Kikuchi, Yoshitaka*

JAEA-Technology 2019-004, 25 Pages, 2019/05

JAEA-Technology-2019-004.pdf:3.02MB

JAEA has developed the "Financial and contract information system" for effective and efficient accomplishment of the mission-critical tasks. Because the development of the next system was necessary with the end in the support time limit of the current system, we carried out the development of the next system in 2018. While the addition of the electronic approval function or the adoption of the latest package software largely performed a functional enhancement until now by applying distributed systems construction technique based on the separation procurement that we devised progressively, in development, we extremely realized procurement with the low cost.

Journal Articles

Gamma-ray spectrum from thermal neutron capture on gadolinium-157

Hagiwara, Kaito*; Yano, Takatomi*; Das, P. K.*; Lorenz, S.*; Ou, Iwa*; Sakuda, Makoto*; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Nobuyuki; Harada, Hideo; et al.

Progress of Theoretical and Experimental Physics (Internet), 2019(2), p.023D01_1 - 023D01_26, 2019/02

 Times Cited Count:29 Percentile:87.26(Physics, Multidisciplinary)

Journal Articles

Cross section measurements of $$^{155,157}$$Gd(n,$$gamma$$) induced by thermal and epithermal neutrons

Mastromarco, M.*; Manna, A.*; Aberle, O.*; Andrzejewski, J.*; Harada, Hideo; Kimura, Atsushi; n_TOF Collaboration*; 116 of others*

European Physical Journal A, 55(1), p.9_1 - 9_20, 2019/01

 Times Cited Count:24 Percentile:92.79(Physics, Nuclear)

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:1 Percentile:11.41(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

Measurements of neutron total and capture cross sections of $$^{241}$$Am with ANNRI at J-PARC

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

Journal of Nuclear Science and Technology, 55(10), p.1198 - 1211, 2018/10

AA2017-0628.pdf:2.06MB

 Times Cited Count:16 Percentile:88.54(Nuclear Science & Technology)

Journal Articles

$$^7$$Be(n,p)$$^7$$Li reaction and the cosmological lithium problem; Measurement of the cross section in a wide energy range at n_TOF at CERN

Damone, L.*; Barbagallo, M.*; Mastromarco, M.*; Cosentino, L.*; Harada, Hideo; Kimura, Atsushi; n_TOF Collaboration*; 152 of others*

Physical Review Letters, 121(4), p.042701_1 - 042701_7, 2018/07

 Times Cited Count:47 Percentile:92.13(Physics, Multidisciplinary)

Journal Articles

Integrating radiation protection criteria for radioactive waste management into remediation procedures in existing exposure situations after a nuclear accident

Sugiyama, Daisuke*; Kimura, Hideo; Tachikawa, Hirokazu*; Iimoto, Takeshi*; Kawata, Yosuke*; Ogino, Haruyuki*; Okoshi, Minoru*

Journal of Radiological Protection, 38(1), p.456 - 462, 2018/03

 Times Cited Count:0 Percentile:0.01(Environmental Sciences)

Experience after the accident at the Fukushima Daiichi Nuclear Power Station has shown that there is a need to establish radiation protection criteria for radioactive waste management consistent with the criteria adopted for the remediation of existing exposure situations. A stepwise approach to setting such criteria is proposed. Initially, a reference level for annual effective dose from waste management activities in the range 1-10 mSv should be set, with the reference level being less than the reference level for ambient dose. Subsequently, the reference level for annual effective dose from waste management activities should be reduced in one or more steps to achieve a final target value of 1 mSv. The dose criteria at each stage should be determined with relevant stakeholder involvement. Illustrative case studies show how this stepwise approach might be applied in practice.

Journal Articles

Cutting-edge studies on nuclear data for continuous and emerging need, 2; Nuclear data measurements and theoretical analysis in the resonance region

Kimura, Atsushi; Harada, Hideo; Kunieda, Satoshi; Katabuchi, Tatsuya*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 59(11), p.654 - 658, 2017/11

no abstracts in English

380 (Records 1-20 displayed on this page)