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Nakamura, Shoji; Endo, Shunsuke; Rovira Leveroni, G.; Kimura, Atsushi; Shibahara, Yuji*
KURNS Progress Report 2023, P. 46, 2024/07
The present work is an attempt to measure the thermal-neutron capture cross-sections for some nuclides which are of importance in decommissioning to evaluate produced radioactivity. This work selected some of objective nuclides for decommissioning, such as 
Fe, 
Er and 
Hf, and measured thermal-neutron capture cross-sections for these nuclides by a neutron activation method at Kyoto University Research Reactor. The present results were obtained as follows:1.23
0.03 barn for Fe(n,
)
Fe reaction, 8.190.35 barn for Er(n,)
Er reaction and 13.570.14 barn for Hf(n,)
Hf reaction. As a by-product, the measurement of Hf sample also presented 0.4270.006 barn for 
Hf(n,)
Hf reaction. It has been revealed that the data adopted in an evaluated data library differ from the present results by more than experimental uncertainties.
Nakamura, Shoji; Endo, Shunsuke; Kimura, Atsushi; Shibahara, Yuji*
KURNS Progress Report 2022, P. 73, 2023/07
The present study is concerned with the neutron capture cross-sections that contribute to the evaluation of the amount of radionuclides possessing problems in decommissioning. In this study, 
Sc, 
Cu, 
Zn, 
Ag, 
In and 
W were selected among the objective nuclides, and their thermal-neutron capture cross-sections were measured using TC-Pn equipment of the KUR of the Institute for Integrated Radiation and Nuclear Science, Kyoto University. High purity metal samples were prepared. A gold-aluminum ally wire, cobalt and molybdenum foils were used to monitor the neutron flux at the irradiation position of TC-Pn. The flux monitors and metal samples were irradiated for 1 hour at 1-MW operation of the KUR. After irradiation, the irradiation capsule was opened, samples and flux monitors were enclosed in a vinyl bag one by one, and then rays emitted from the samples and monitors were measured with a high-purity Ge detector. The thermal-neutron flux component was derived with the reaction rates of flux monitors (
Au, Co and 
Mo) on the basis of Westcott's convention, and found to be (5.920.10)
10
n/cm
/sec at the irradiation position. The measured reaction rate for each metal sample divided by the evaluated thermal-neutron capture cross-section should give the same value of the thermal-neutron flux component if the cross section is suitable. This time, we found that the cross sections of Sc and 
Zn were consistent with the evaluated one, but those of other nuclides were inconsistent with their evaluated ones; that is, it turned out that their thermal-neutron capture cross-sections should be modified.
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：0.00(Nuclear Science & Technology)The present study performed fast-neutron capture cross-section measurement of 
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 Tc were obtained by measuring decay gamma rays emitted from 
Tc. The neutron flux at an irradiation position was monitored with gold foils. The fast-neutron capture cross section of Tc at neutron energy of 85 keV was derived as 0.4320.023 barn by using the reaction rates of 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.
-process nucleosynthesisBhattacharyya, A.*; Datta, U.*; Rahaman, A.*; Chakraborty, S.*; Aumann, T.*; Beceiro-Novo, S.*; Boretzky, K.*; Caesar, C.*; Carlson, B. V.*; Catford, W. N.*; et al.
Physical Review C, 104(4), p.045801_1 - 045801_14, 2021/10
Times Cited Count：7 Percentile：63.10(Physics, Nuclear)no abstracts in English
Np using graphite thermal columnNakamura, Shoji; Endo, Shunsuke; Kimura, Atsushi; Shibahara, Yuji*
KURNS Progress Report 2020, P. 94, 2021/08
The present study selected Np among radioactive nuclides and aimed to converge a contradiction between reported thermal-neutron capture cross sections. Neutron irradiation was carried out using the graphite thermal column equipped with the Kyoto University Research Reactor. A solution equivalent to 950 Bq order of radioactivity was pipetted out of a Np standard solution and dropped onto a fiber filter, which was then dried with an infrared lamp to prepare a Np sample. The Np sample was quantified using 312-keV gamma ray emitted from 
Pa in a radiation equilibrium with Np. To monitor a thermal-neutron flux component at an irradiation position, the Np sample was irradiated together with several stable nuclides as neutron flux monitors: Sc, Co, Mo, Ta and Au. The reaction rate of Np was obtained from gamma-ray yields given by 
Np and Pa, and then the thermal-neutron capture cross section of Np was derived.
P
rez S
nchez, R.*; Jurado, B.*; Mot, V.*; Roig, O.*; Dupuis, M.*; Bouland, O.*; Denis-Petit, D.*; Marini, P.*; Mathieu, L.*; Tsekhanovich, I.*; et al.
Physical Review Letters, 125(12), p.122502_1 - 122502_5, 2020/09
Times Cited Count：21 Percentile：76.54(Physics, Multidisciplinary)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：8.72(Nuclear Science & Technology)Accurate data of -ray emission probabilities are frequently needed when one quantitatively determines the amount of isotope by -ray measurements or obtains neutron capture cross-sections using them. Americium-243, one of the most important minor actinides, produces 
Am after neutron capture. The 744-keV -ray decaying from the ground state of Am has a relatively large -ray emission probability c.a. 66%, however, its uncertainty is as large as 29%. The uncertainty of the -ray emission probability leads to a major factor of the systematic uncertainty on determining an amount of isotope, and therefore the -ray emission probability was measured by using an activation method and an examined level structure of Cm. In this study, the emission probability of 744-keV ray was derived as 66.51.1%, and its uncertainty was improved from 29% to 2%.
Cs(n,) cross-section using a New DAQ System at ANNRIHales, B. P.; Nakamura, Shoji; Kimura, Atsushi; Iwamoto, Osamu
J-PARC 17-07; J-PARC MLF Annual Report 2016, p.88 - 89, 2017/03
PdNakamura, Shoji; Kimura, Atsushi; Toh, Yosuke; Harada, Hideo; Katabuchi, Tatsuya*; Mizumoto, Motoharu*; Igashira, Masayuki*; Hori, Junichi*; Kino, Koichi*
JAEA-Conf 2015-003, p.113 - 118, 2016/03
Experiments were carried out with the Ge detector of ANNRI to confirm whether or not the weak resonances were surely due to Pd. The prompt rays due to capture reaction of Pd were clearly observed at the -ray energy at 115 kev and around 300 keV. When a TOF spectrum was extracted by gating at the prompt ray around 300 keV, the small resonance peaks were revealed at the neutron energy of 146 and 156 eV.
Harada, Hideo
Kaku Deta Nyusu (Internet), (109), p.44 - 47, 2014/10
Improvement of accuracy of neutron nuclear data for minor actinides (MAs) and long-lived fission products (LLFPs) is required for developing innovative nuclear system transmuting these nuclei. In order to meet the requirement, the project entitled as "Research and development for Accuracy Improvement of neutron nuclear data on Minor ACtinides (AIMAC)" has been started as one of the "Innovative Nuclear Research and Development Program". The AIMAC project team is composed of researchers in four different fields: differential nuclear data measurement, integral nuclear data measurement, nuclear chemistry, and nuclear data evaluation. By integrating all of the forefront knowledge and techniques in these fields, the research project team aims at improving the accuracy of the data. The background, goal and brief research plan of the AIMAC project are explained.
Ge spectrometer by Geant4Goto, Jun; Sugawara, Masahiko*; Oshima, Masumi; Toh, Yosuke; Kimura, Atsushi; Osa, Akihiko; Koizumi, Mitsuo; Mizumoto, Motoharu; Osaki, Toshiro*; Igashira, Masayuki*; et al.
AIP Conference Proceedings 769, p.788 - 791, 2005/05
no abstracts in English
Re isomeric stateHayakawa, Takehito; Shizuma, Toshiyuki; Yamauchi, Toshihiko; Minehara, Eisuke; Arisawa, Takashi
Nuclear Physics A, 718, p.665c - 667c, 2003/05
no abstracts in English
Nakagawa, Tsuneo; Chiba, Satoshi; Osaki, Toshiro*; Igashira, Masayuki*
JAERI-Research 2000-002, p.93 - 0, 2000/02
JAERI-Research-2000-002.pdf:4.41MB
no abstracts in English
CsNakajima, Yutaka; Okubo, Makio; Sugimoto, Masayoshi; Mizumoto, Motoharu; Kawarasaki, Yuki
Annals of Nuclear Energy, 17(10), p.569 - 577, 1990/00
Times Cited Count：3 Percentile：39.96(Nuclear Science & Technology)no abstracts in English
Gd and 
Gd from 1.1 to 235 keVNakajima, Yutaka; ; Mizumoto, Motoharu; ; ; Sugimoto, Masayoshi; Kawarasaki, Yuki
Annals of Nuclear Energy, 16(11), p.589 - 597, 1989/00
Times Cited Count：8 Percentile：66.94(Nuclear Science & Technology)no abstracts in English
; ;
JAERI-M 84-211, 28 Pages, 1984/11
no abstracts in English
;
JAERI-M 8724, 44 Pages, 1980/03
no abstracts in English
Eu and 
Eu from 3 to 100keV; ; ; ; Fuketa, Toyojiro;
Journal of Nuclear Science and Technology, 16(10), p.711 - 719, 1979/10
Times Cited Count：12no abstracts in English
; ;
JAERI-M 6010, 35 Pages, 1975/03
no abstracts in English
Kimura, Atsushi; Nakamura, Shoji; Terada, Kazushi; Nakao, Taro; Toh, Yosuke; Harada, Hideo; Igashira, Masayuki*; Katabuchi, Tatsuya*; Mizumoto, Motoharu*; Takamiya, Koichi*; et al.
no journal, ,
no abstracts in English
