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Journal Articles

Neutron capture cross-section measurements with TC-Pn in KUR for some nuclides targeted for decommissioning

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, $$^{45}$$Sc, $$^{63}$$Cu, $$^{64}$$Zn, $$^{109}$$Ag, $$^{113}$$In and $$^{186}$$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 $$gamma$$ 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 ($$^{197}$$Au, $$^{59}$$Co and $$^{98}$$Mo) on the basis of Westcott's convention, and found to be (5.92$$pm$$0.10)$$times$$10$$^{10}$$ n/cm$$^{2}$$/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 $$^{45}$$Sc and $$^{94}$$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.

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 light neutron-rich nuclei relevant for $$r$$-process nucleosynthesis

Bhattacharyya, 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

AA2021-0553.pdf:7.41MB

 Times Cited Count:5 Percentile:57.13(Physics, Nuclear)

no abstracts in English

Journal Articles

Thermal-neutron capture cross-section measurement of $$^{237}$$Np using graphite thermal column

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

KURNS Progress Report 2020, P. 94, 2021/08

The present study selected $$^{237}$$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 $$^{237}$$Np standard solution and dropped onto a fiber filter, which was then dried with an infrared lamp to prepare a $$^{237}$$Np sample. The $$^{237}$$Np sample was quantified using 312-keV gamma ray emitted from $$^{233}$$Pa in a radiation equilibrium with $$^{237}$$Np. To monitor a thermal-neutron flux component at an irradiation position, the $$^{237}$$Np sample was irradiated together with several stable nuclides as neutron flux monitors: $$^{45}$$Sc, $$^{59}$$Co, $$^{98}$$Mo, $$^{181}$$Ta and $$^{197}$$Au. The reaction rate of $$^{237}$$Np was obtained from gamma-ray yields given by $$^{238}$$Np and $$^{233}$$Pa, and then the thermal-neutron capture cross section of $$^{237}$$Np was derived.

Journal Articles

Simultaneous determination of neutron-induced fission and radiative capture cross sections from decay probabilities obtained with a surrogate reaction

P$'e$rez S$'a$nchez, R.*; Jurado, B.*; M$'e$ot, 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:13 Percentile:70.32(Physics, Multidisciplinary)

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:11.15(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 the $$^{133}$$Cs(n,$$gamma$$) cross-section using a New DAQ System at ANNRI

Hales, B. P.; Nakamura, Shoji; Kimura, Atsushi; Iwamoto, Osamu

J-PARC 17-07; J-PARC MLF Annual Report 2016, p.88 - 89, 2017/03

Journal Articles

Search for neutron resonances of $$^{106}$$Pd

Nakamura, 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 $$^{106}$$Pd. The prompt $$gamma$$ rays due to capture reaction of $$^{106}$$Pd were clearly observed at the $$gamma$$-ray energy at 115 kev and around 300 keV. When a TOF spectrum was extracted by gating at the prompt $$gamma$$ ray around 300 keV, the small resonance peaks were revealed at the neutron energy of 146 and 156 eV.

Journal Articles

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

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.

Journal Articles

Simulation of 4$$pi$$ Ge spectrometer by Geant4

Goto, 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

Journal Articles

Neutron capture cross section to $$^{186}$$Re isomeric state

Hayakawa, Takehito; Shizuma, Toshiyuki; Yamauchi, Toshihiko; Minehara, Eisuke; Arisawa, Takashi

Nuclear Physics A, 718, p.665c - 667c, 2003/05

no abstracts in English

JAEA Reports

Maxwellian-averaged cross sections calculated from JENDL-3.2

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

Journal Articles

Neutron resonances in $$^{133}$$Cs

Nakajima, 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:40.4(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Neutron capture cross section measurements of $$^{155}$$Gd and $$^{157}$$Gd from 1.1 to 235 keV

Nakajima, Yutaka; *; Mizumoto, Motoharu; *; ; Sugimoto, Masayoshi; Kawarasaki, Yuki

Annals of Nuclear Energy, 16(11), p.589 - 597, 1989/00

 Times Cited Count:8 Percentile:67.28(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

JAEA Reports

A Computer Program for Calculating Effective Capture Cross Section

;

JAERI-M 8724, 44 Pages, 1980/03

JAERI-M-8724.pdf:1.21MB

no abstracts in English

Journal Articles

Average neutron capture cross sections of $$^{1}$$$$^{5}$$$$^{1}$$Eu and $$^{1}$$$$^{5}$$$$^{3}$$Eu from 3 to 100keV

; ; ; ; Fuketa, Toyojiro;

Journal of Nuclear Science and Technology, 16(10), p.711 - 719, 1979/10

 Times Cited Count:11

no abstracts in English

JAEA Reports

Oral presentation

Simultaneous measurement of fission and capture cross sections for minor actinide nuclei

Tamura, Nobuyuki; Nishio, Katsuhisa; Hirose, Kentaro; Nishinaka, Ichiro; Makii, Hiroyuki; Kimura, Atsushi; Ota, Shuya*; Andreyev, A. N.; Vermeulen, M.*; Gillespire, S.*; et al.

no journal, , 

no abstracts in English

Oral presentation

Accuracy improvement of thermal-neutron capture cross-section for Np-237

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

no journal, , 

As a part of the AIMAC Project, our group have measured the cross sections for Minor Actinides by an activation method with research reactors. In this presentation, we will clear up the cause of discrepancies among reported data for Np-237 in terms of the $$gamma$$-ray emission probability, experimental method and so on.

33 (Records 1-20 displayed on this page)