Refine your search:     
Report No.
 - 
Search Results: Records 1-16 displayed on this page of 16
  • 1

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

Measurement of radionuclide production probabilities in negative muon nuclear capture and validation of Monte Carlo simulation model

Yamaguchi, Yuji; Niikura, Megumi*; Mizuno, Rurie*; Tampo, Motonobu*; Harada, Masahide; Kawamura, Naritoshi*; Umegaki, Izumi*; Takeshita, Soshi*; Haga, Katsuhiro

Nuclear Instruments and Methods in Physics Research B, 567, p.165801_1 - 165801_11, 2025/10

 Times Cited Count:2 Percentile:62.61(Instruments & Instrumentation)

As part of the development of a sample radioactivity calculation program, we have measured radionuclide production probabilities in negative muon nuclear capture to update experimental data and to validate a calculation dataset obtained by a Monte Carlo simulation code. The probabilities have been obtained by an activation experiment on $$^{27}$$Al, $$^mathrm{nat}$$Si, $$^{59}$$Co, and $$^mathrm{nat}$$Ta targets. The obtained probabilities expand the validation scope to the radionuclide production processes outside of the existing data coverage. By comparing the resultant probabilities with the calculated dataset, it has been revealed that the dataset is generally on the safe side in radioactivity estimation and needs to be corrected in the following three cases: (i) isomer production; (ii) radionuclide production by the multiple neutron emission; (iii) radionuclide production by particle emissions involving a proton. The present probabilities and the new findings on the correction provide valuable clues to improvements of the simulation models.

Journal Articles

Calculation of gamma and neutron emission characteristics emitted from fuel debris of Fukushima Daiichi Nuclear Power Station

Riyana, E. S.; Okumura, Keisuke; Terashima, Kenichi

Journal of Nuclear Science and Technology, 56(9-10), p.922 - 931, 2019/09

 Times Cited Count:11 Percentile:63.60(Nuclear Science & Technology)

Journal Articles

Measurement of the $$^{77}$$Se($$gamma$$, n) cross section and uncertainty evaluation of the $$^{79}$$Se(n, $$gamma$$) cross section

Kitatani, Fumito; Harada, Hideo; Goko, Shinji*; Iwamoto, Nobuyuki; Utsunomiya, Hiroaki*; Akimune, Hidetoshi*; Toyokawa, Hiroyuki*; Yamada, Kawakatsu*; Igashira, Masayuki*

Journal of Nuclear Science and Technology, 53(4), p.475 - 485, 2016/04

 Times Cited Count:5 Percentile:36.22(Nuclear Science & Technology)

Journal Articles

JAEA-ISCN development programs of advanced NDA technologies of nuclear material

Seya, Michio; Kobayashi, Naoki; Naoi, Yosuke; Hajima, Ryoichi; Soyama, Kazuhiko; Kureta, Masatoshi; Nakamura, Hironobu; Harada, Hideo

Book of Abstracts, Presentations and Papers of Symposium on International Safeguards; Linking Strategy, Implementation and People (Internet), 8 Pages, 2015/03

JAEA-ISCN has been implementing basic development programs of the advanced NDA technologies for nuclear material (NM) since 2011JFY (Japanese Fiscal Year), which are (1) NRF (Nuclear resonance fluorescence) NDA technology using laser Compton scattered (LCS) $$gamma$$-rays (intense mono-energetic $$gamma$$-rays), (2) Alternative to $$^{3}$$He neutron detection technology using ZnS/B$$_{2}$$O$$_{3}$$ ceramic scintillator, and (3) NRD (Neutron resonance densitometry) using NRTA (Neutron resonance transmission analysis) and NRCA (Neutron resonance capture analysis). These programs are going to be finished in 2014JFY and have demonstration tests in February - March 2015.

Journal Articles

Minor actinide neutron capture cross-section measurements with a 4$$pi$$ Ge spectrometer

Koizumi, Mitsuo; Osa, Akihiko; Toh, Yosuke; Kimura, Atsushi; Mizumoto, Motoharu; Oshima, Masumi; Igashira, Masayuki*; Osaki, Toshiro*; Harada, Hideo*; Furutaka, Kazuyoshi*; et al.

Nuclear Instruments and Methods in Physics Research A, 562(2), p.767 - 770, 2006/06

 Times Cited Count:6 Percentile:42.51(Instruments & Instrumentation)

In order to measure the neutron capture cross section of minor actinides, we have proposed the use of a 4$$pi$$ Ge spectrometer. A Time-of-Flight neutron beam line for the experiment has been constructed at the KURRI electron LINAC. The assembling of the 4$$pi$$ Ge spectrometer is in progress. We are also developing a new data acquisition system based on a digital processing technique.

Journal Articles

Radioisotope production

Sekine, Toshiaki

Radioisotopes, 46(9), p.670 - 674, 1997/09

no abstracts in English

Journal Articles

Measurement of the thermal neutron cross section of the $$^{90}$$Sr(n,$$gamma$$)$$^{91}$$Sr reaction

Harada, Hideo*; Sekine, Toshiaki; ; Ishioka, Noriko; Kobayashi, Katsutoshi; Otsuki, Tsutomu*; Kato, Toshio*

Journal of Nuclear Science and Technology, 31(3), p.173 - 179, 1994/03

 Times Cited Count:25 Percentile:86.44(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of thermal neutron cross section and resonance integral of the reaction $$^{137}$$Cs(n,$$gamma$$)$$^{138}$$Cs

Sekine, Toshiaki; ; Kobayashi, Katsutoshi; Harada, Hideo*; Watanabe, Hisashi*; Kato, Toshio*

Journal of Nuclear Science and Technology, 30(11), p.1099 - 1106, 1993/11

 Times Cited Count:30 Percentile:90.97(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Measurement of the thermal neutron cross section and resonance integral of the reaction $$^{137}$$Cs(n,$$gamma$$)$$^{138}$$Cs

Sekine, Toshiaki; ; Kobayashi, Katsutoshi; Harada, Hideo*; Watanabe, Hisashi*; Kato, Toshio*

Proc. of the Nuclear Data for Science and Technology, p.57 - 58, 1992/00

no abstracts in English

Journal Articles

Simplified method for calculation of neutron capture transformation effects of fission products on decay power

Tasaka, Kanji;

Journal of Nuclear Science and Technology, 23(10), p.914 - 925, 1986/00

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of molybdenum-99 to nuclear medicine and Its production

;

Nihon Genshiryoku Gakkai-Shi, 26(8), p.662 - 670, 1984/00

 Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Reactor-neutron-capture cross sections of $$^{1}$$$$^{6}$$$$^{5}$$Dy isomers

;

Journal of Inorganic and Nuclear Chemistry, 43, p.1107 - 1113, 1981/00

 Times Cited Count:5 Percentile:25.15(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Nuclear resonant scattering of 6734keV lead capture gamma rays from tin

;

Journal of the Physical Society of Japan, 26(5), P. 1319, 1969/00

no abstracts in English

Journal Articles

Nuclear photo-excitation of the 7368 keV level of $$^{6}$$$$^{6}$$Zn by lead capture gamma rays

;

Nuclear Physics A, 118, p.114 - 128, 1968/00

 Times Cited Count:36

no abstracts in English

Journal Articles

The Behavior of fission products captured in graphite powder by nuclear recoil, 3; Diffusion of iodine-133 and tellurium-132 in graphite at high temperatures

; ; ; Shiba, Koreyuki

Bulletin of the Chemical Society of Japan, 34(4), p.493 - 497, 1961/00

 Times Cited Count:14

no abstracts in English

Journal Articles

The Behavior of fission products captured in grahite power by nuclear recoil, 4; Further studies on the diffusion of xenon-133 in graphite

; ; ; Shiba, Koreyuki; Masaharu Kori*

Bulletin of the Chemical Society of Japan, 34(5), p.697 - 701, 1961/00

 Times Cited Count:20

no abstracts in English

16 (Records 1-16 displayed on this page)
  • 1