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Journal Articles

Updates to the AMUR code for R-matrix analyses on heavy nuclei

Kunieda, Satoshi; Endo, Shunsuke; Kimura, Atsushi

EPJ Web of Conferences, 281, p.00017_1 - 00017_6, 2023/03

The AMUR code, which is based on the multi-channel/multi-level R-matrix theory, is under development for the cross-section evaluation with the covariance data in the resolved resonance energy region. Although, the code was initially designed for the analysis of the light-nuclei, the authors extended its capability toward the analysis of heavier nuclei by introducing the Reich-Moore approximation and the free-gas approximation for the Doppler broadening. In this work, we challenge a resonance analysis of neutron cross-section data measured in J-PARC/ANNRI with AMUR, in which the resolution functions and the double-bunching effects were taken into account inside the code. In this presentation, let us show results of resonance analysis on some of the J-PARC/ANNRI measurements together with covariance of the resonance parameters and cross-sections, for the first time. We also plan to discuss differences of correlation matrices among approximations of the R-matrix theory to understand physics underlying on the resonant reaction.

Journal Articles

Covariance of resonance parameters ascribed to systematic uncertainties in experiments

Endo, Shunsuke; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Iwamoto, Nobuyuki; Rovira Leveroni, G.

EPJ Web of Conferences, 281, p.00012_1 - 00012_5, 2023/03

Journal Articles

Water contents in aggregates and cement pastes determined by gravimetric analysis and prompt $$gamma$$-ray analysis

Kinoshita, Norikazu*; Noto, Takuma*; Nakajima, Hitoshi*; Kosako, Kazuaki*; Kato, Takahiro*; Kuroiwa, Yoichi*; Kurabe, Misako*; Sasaki, Yuki*; Torii, Kazuyuki*; Maeda, Makoto; et al.

Journal of Radioanalytical and Nuclear Chemistry, 332(2), p.479 - 486, 2023/02

Journal Articles

Study of the $$N=32$$ and $$N=34$$ shell gap for Ti and V by the first high-precision multireflection time-of-flight mass measurements at BigRIPS-SLOWRI

Iimura, Shun*; Rosenbusch, M.*; Takamine, Aiko*; Tsunoda, Yusuke*; Wada, Michiharu*; Chen, S.*; Hou, D. S.*; Xian, W.*; Ishiyama, Hironobu*; Yan, S.*; et al.

Physical Review Letters, 130(1), p.012501_1 - 012501_6, 2023/01

Journal Articles

Neutron capture cross-section measurement by mass spectrometry for Pb-204 irradiated in JRR-3

Nakamura, Shoji; Shibahara, Yuji*; Kimura, Atsushi; Endo, Shunsuke; Shizuma, Toshiyuki*

Journal of Nuclear Science and Technology, 10 Pages, 2023/00

 Times Cited Count:0 Percentile:0.04(Nuclear Science & Technology)

In recent years, research has been advanced on lead-cooled fast reactors and accelerator drive systems, and it is required to improve the accuracy of the neutron capture cross section of Pb isotopes. Although $$^{204}$$Pb has a small natural abundance, it is of importance because it produces the long-lived radionuclide $$^{205}$$Pb (17.3 million years) by neutron capture reaction. However, it is difficult to measure its cross section by a conventional activation method using a nuclear reactor because the induced radioactivity of $$^{205}$$Pb is weak. Hence, the cross-section measurement was performed by applying mass spectrometry. This presentation gives the details of the experiment and the results obtained in the neutron capture cross-section measurement of $$^{204}$$Pb using mass spectroscopy.

Journal Articles

Measurements of capture cross-section of $$^{93}$$Nb by activation method and half-life of $$^{94}$$Nb by mass analysis

Nakamura, Shoji; Shibahara, Yuji*; Endo, Shunsuke; Kimura, Atsushi

Journal of Nuclear Science and Technology, 11 Pages, 2023/00

 Times Cited Count:0

The thermal-neutron capture cross section ($$sigma$$$$_{0}$$) and resonance integral (I$$_{0}$$) for $$^{93}$$Nb among nuclides for decommissioning were measured by an activation method and the half-life of $$^{94}$$Nb by mass analysis. Niobium-93 samples were irradiated with a hydraulic conveyer installed in the research reactor in Institute for Integral Radiation and Nuclear Science, Kyoto University. Gold-aluminum, cobalt-aluminum alloy wires were used to monitor thermal-neutron fluxes and epi-thermal Westcott's indexes at an irradiation position. A 25-$$mu$$m-thick gadolinium foil was used to sort out reactions ascribe to thermal-and epi-thermal neutrons. Its thickness provided a cut-off energy of 0.133 eV. In order to attenuate radioactivity of $$^{182}$$Ta due to impurities, the Nb samples were cooled for nearly 2 years. The induced radio activity in the monitors and Nb samples were measured by $$gamma$$-ray spectroscopy. In analysis based on Westcott's convention, the $$sigma$$$$_{0}$$ and I$$_{0}$$ values were derived as 1.11$$pm$$0.04 barn and 10.5$$pm$$0.6 barn, respectively. After the $$gamma$$-ray measurements, mass analysis was applied to the Nb sample to obtain the reaction rate. By combining data obtained by both $$gamma$$-ray spectroscopy and mass analysis, the half-life of $$^{94}$$Nb was derived as (2.00$$pm$$0.15)$$times$$10$$^{4}$$ years.

Journal Articles

Development of a neutron beam monitor with a thin plastic scintillator for nuclear data measurement using spallation neutron source

Nakano, Hideto*; Katabuchi, Tatsuya*; Rovira Leveroni, G.; Kodama, Yu*; Terada, Kazushi*; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke

Journal of Nuclear Science and Technology, 59(12), p.1499 - 1506, 2022/12

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

Journal Articles

Measurement of the transverse asymmetry of $$gamma$$ rays in the $$^{117}$$Sn($$n,gamma$$)$$^{118}$$Sn reaction

Endo, Shunsuke; Okudaira, Takuya*; Abe, Ryota*; Fujioka, Hiroyuki*; Hirota, Katsuya*; Kimura, Atsushi; Kitaguchi, Masaaki*; Oku, Takayuki; Sakai, Kenji; Shima, Tatsushi*; et al.

Physical Review C, 106(6), p.064601_1 - 064601_7, 2022/12

 Times Cited Count:0 Percentile:0.02(Physics, Nuclear)

no abstracts in English

Journal Articles

$$^{241}$$Am neutron capture cross section measurement and resonance analysis

Rovira Leveroni, G.; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Iwamoto, Osamu; Iwamoto, Nobuyuki; Katabuchi, Tatsuya*; Kodama, Yu*; Nakano, Hideto*; Sato, Yaoki*

JAEA-Conf 2022-001, p.91 - 96, 2022/11

Journal Articles

Thermal-neutron capture cross-section measurements of neptunium-237 with graphite thermal column in KUR

Nakamura, Shoji; Shibahara, Yuji*; Endo, Shunsuke; Kimura, Atsushi

Journal of Nuclear Science and Technology, 59(11), p.1388 - 1398, 2022/11

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

The present study selected $$^{237}$$Np among radioactive nuclides and aimed to measure the thermal-neutron capture cross-section for $$^{237}$$Np in a well-thermalized neutron field by an activation method. A $$^{237}$$Np standard solution was used for irradiation samples. A thermal-neutron flux at an irradiation position was measured with neutron flux monitors: $$^{45}$$Sc, $$^{59}$$Co, $$^{98}$$Mo, $$^{181}$$Ta and $$^{197}$$Au. The $$^{237}$$Np sample and flux monitors were irradiated together for 30 minutes in the graphite thermal column equipped with the Kyoto University Research Reactor. The similar irradiation was carried out twice. After the irradiations, the $$^{237}$$Np samples were quantified using 312-keV gamma ray emitted from $$^{233}$$Pa in a radiation equilibrium with $$^{237}$$Np. The reaction rates of $$^{237}$$Np were obtained from gamma-ray peak net counts given by $$^{238}$$Np, and then the thermal-neutron capture cross-section of $$^{237}$$Np was found to be 173.8$$pm$$4.4 barn by averaging the results obtained by the two irradiations. The present result was in agreement with the reported data given by a time-of-flight method within the limit of uncertainty.

Journal Articles

Absolute quantification of $$^{137}$$Cs activity in spent nuclear fuel with calculated detector response function

Sato, Shunsuke*; Nauchi, Yasushi*; Hayakawa, Takehito*; Kimura, Yasuhiko; Kashima, Takao*; Futakami, Kazuhiro*; Suyama, Kenya

Journal of Nuclear Science and Technology, 9 Pages, 2022/10

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

A new non-destructive method for evaluating $$^{137}$$Cs activity in spent nuclear fuels was proposed and experimentally demonstrated for physical measurements in burnup credit implementation. $$^{137}$$Cs activities were quantified using gamma ray measurements and numerical detector response simulations without reference fuels, in which 137Cs activities are well known. Fuel samples were obtained from a lead use assembly (LUA) irradiated in a commercial pressurized water reactor (PWR) up to 53 GWd/t. Gamma rays emitted from the samples were measured using a bismuth germinate (BGO) scintillation detector through a collimator attached to a hot cell. The detection efficiency of gamma rays with the detector was calculated using the PHITS particle transport calculation code considering the measurement geometry. The relative activities of $$^{134}$$Cs, $$^{137}$$Cs, and $$^{154}$$Eu in the sample were measured with a high-purity germanium (HPGe) detector for more accurate simulations of the detector response for the samples. The absolute efficiency of the detector was calibrated by measuring a standard gamma ray source in another geometry. $$^{137}$$Cs activity in the fuel samples was quantified using the measured count rate and detection efficiency. The quantified $$^{137}$$Cs activities agreed well with those estimated using the MVP-BURN depletion calculation code.

Journal Articles

Low-lying dipole strength distribution in $$^{204}$$Pb

Shizuma, Toshiyuki*; Endo, Shunsuke; Kimura, Atsushi; Massarczyk, R.*; Schwengner, R.*; Beyer, R.*; Hensel, T.*; Hoffmann, H.*; Junghans, A.*; R$"o$mer, K.*; et al.

Physical Review C, 106(4), p.044326_1 - 044326_11, 2022/10

 Times Cited Count:0 Percentile:0.02(Physics, Nuclear)

no abstracts in English

Journal Articles

Measurements of thermal-neutron capture cross-section of the $$^{237}$$Np(n, $$gamma$$) reaction with TC-Pn in KUR

Nakamura, Shoji; Endo, Shunsuke; Kimura, Atsushi; Shibahara, Yuji*

KURNS Progress Report 2021, P. 93, 2022/07

In terms of nuclear transmutation studies of minor actinides in nuclear wastes, the present work selected $$^{237}$$Np among them and aimed to measure the thermal-neutron capture cross-section of $$^{237}$$Np using a well-thermalized neutron field by a neutron activation method because there have been discrepancies among reported cross-section data. A $$^{237}$$Np standard solution was used for irradiation samples. The thermal-neutron flux at an irradiation position was measured with flux monitors: $$^{45}$$Sc, $$^{59}$$Co, $$^{98}$$Mo, $$^{181}$$Ta and $$^{197}$$Au. The $$^{237}$$Np sample was irradiated together with the flux monitors for 30 minutes in the graphite thermal column equipped in the Kyoto University Research Reactor. The similar irradiation was repeated once more to confirm the reproducibility of the results. After irradiation, the $$^{237}$$Np samples were quantified using 312-keV gamma-ray emitted from $$^{233}$$Pa in radiation equilibrium with $$^{237}$$Np. The reaction rates of $$^{237}$$Np were obtained from the peak net counts of gamma-rays emitted from generated $$^{238}$$Np, and then the thermal-neutron capture cross-section of $$^{237}$$Np was found to be 173.8$$pm$$4.7 barn by averaging the results obtained by the two irradiations. The present result was in agreement with the reported data given by a time-of-flight method within a limit of uncertainty.

Journal Articles

Effect of sample density in prompt $$gamma$$-ray analysis

Maeda, Makoto; Segawa, Mariko; Toh, Yosuke; Endo, Shunsuke; Nakamura, Shoji; Kimura, Atsushi

Scientific Reports (Internet), 12(1), p.6287_1 - 6287_8, 2022/06

 Times Cited Count:1 Percentile:43.85(Multidisciplinary Sciences)

Journal Articles

KeV-neutron capture cross-section measurement of $$^{197}$$Au with a Cr-filtered neutron beam at the ANNRI beamline of MLF/J-PARC

Rovira Leveroni, G.; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke; Iwamoto, Osamu; Iwamoto, Nobuyuki; Katabuchi, Tatsuya*; Kodama, Yu*; Nakano, Hideto*; Sato, Yaoki*; et al.

Journal of Nuclear Science and Technology, 59(5), p.647 - 655, 2022/05

 Times Cited Count:1 Percentile:25.87(Nuclear Science & Technology)

Journal Articles

Angular distribution of $$gamma$$ rays from the $$p$$-wave resonance of $$^{118}$$Sn

Koga, Jun*; Takada, Shusuke*; Endo, Shunsuke; Fujioka, Hiroyuki*; Hirota, Katsuya*; Ishizaki, Kohei*; Kimura, Atsushi; Kitaguchi, Masaaki*; Niinomi, Yudai*; Okudaira, Takuya*; et al.

Physical Review C, 105(5), p.054615_1 - 054615_5, 2022/05

 Times Cited Count:1 Percentile:56.18(Physics, Nuclear)

no abstracts in English

Journal Articles

Neutron filtering system for fast neutron cross-section measurement at ANNRI

Rovira Leveroni, G.; Iwamoto, Osamu; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Nobuyuki; Endo, Shunsuke; Katabuchi, Tatsuya*; Terada, Kazushi*; Kodama, Yu*; Nakano, Hideto*; et al.

JAEA-Conf 2021-001, p.156 - 161, 2022/03

Journal Articles

Development of a neutron beam monitor for nuclear data measurement using spallation neutron source

Nakano, Hideto*; Katabuchi, Tatsuya*; Rovira Leveroni, G.*; Kodama, Yu*; Terada, Kazushi*; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke

JAEA-Conf 2021-001, p.166 - 170, 2022/03

Journal Articles

A New method to reduce systematic uncertainties of capture cross section measurement using a sample rotation system

Kodama, Yu*; Katabuchi, Tatsuya*; Rovira Leveroni, G.; Nakano, Hideto*; Terada, Kazushi*; Kimura, Atsushi; Nakamura, Shoji; Endo, Shunsuke

JAEA-Conf 2021-001, p.162 - 165, 2022/03

Journal Articles

Neutron capture and total cross-section measurements and resonance parameter analysis of niobium-93 below 400 eV

Endo, Shunsuke; Kimura, Atsushi; Nakamura, Shoji; Iwamoto, Osamu; Iwamoto, Nobuyuki; Rovira Leveroni, G.; Terada, Kazushi*; Meigo, Shinichiro; Toh, Yosuke; Segawa, Mariko; et al.

Journal of Nuclear Science and Technology, 59(3), p.318 - 333, 2022/03

 Times Cited Count:1 Percentile:25.87(Nuclear Science & Technology)

142 (Records 1-20 displayed on this page)