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Nakamura, Shoji; Shibahara, Yuji*; Endo, Shunsuke; Kimura, Atsushi
Journal of Nuclear Science and Technology, 58(10), p.1061 - 1070, 2021/10
Times Cited Count：5 Percentile：64.12(Nuclear Science & Technology)In a well-thermalized neutron field, it is principally possible to drive a thermal-neutron capture cross-section without considering an epithermal neutron component. This was demonstrated by a neutron activation method using the graphite thermal column (TC-Pn) of the Kyoto University Research Reactor. First, in order to confirm that the graphite thermal column was a well-thermalized neutron field, neutron irradiation was performed with neutron flux monitors: 
Au, 
Co, 
Sc, 
Cu, and 
Mo. The TC-Pn was confirmed to be extremely thermalized on the basis of Westcott's convention, because the thermal-neutron flux component took a constant value regardless of the sensitivity of each flux monitor to epithermal neutrons. Next, as a demonstration, the thermal-neutron capture cross section of 
Ta(n,
)
Ta reaction was measured using the graphite thermal column, and then derived to be 20.5
0.4 barn, which supported the evaluated value of 20.40.3 barn. The Ta nuclide could be useful as a flux monitor that complements the sensitivity between Au and Mo monitors.
Sukegawa, Takenori; Hatakeyama, Mutsuo; Yanagihara, Satoshi
JAERI-Tech 2001-058, 81 Pages, 2001/09
JAERI-Tech-2001-058.pdf:5.98MB
In general, neutron transport and activation calculation codes are used for residual radioactive inventory estimation; however, it is essential to verify calculations by measurement results because of geometrical complexity of the reactor and so on. The comparison between measured and calculated radioactivity in the JPDR core components showed a relatively good agreement (factor of 2), and it was cleared that water content and weight ratio of steel bars to concrete materials significantly influenced the neutron flux distribution in the biological shield (factor of 2-10 error). The measured radioactivity inside of the reactor pressure vessel wall and at the inner part of the biological shield was compared in detail with the calculations to verify the methodology applied to calculations of radioisotope production. Then it was found that the radioactive inventory could be estimated accurately with combination of calculations and measurement of radioactivity in samples and dose rate distribution for planning of dismantling activities.
Yamamoto, Kazuyoshi; Kumada, Hiroaki; Torii, Yoshiya; Kishi, Toshiaki; Horiguchi, Yoji
JAERI-Tech 2001-015, 43 Pages, 2001/03
JAERI-Tech-2001-015.pdf:4.95MB
no abstracts in English
Maekawa, Fujio; Oyama, Yukio
Nuclear Instruments and Methods in Physics Research A, 372, p.262 - 274, 1996/00
Times Cited Count：4 Percentile：43.42(Instruments & Instrumentation)no abstracts in English
; Torii, Yoshiya; ; Ichimura, Shigeju; *; Sasajima, Fumio; *; *; *; Takahashi, Hidetake
JAERI-M 94-058, 45 Pages, 1994/03
no abstracts in English
Nakano, Yoshihiro; Ichikawa, Hiroki; Nakajima, Teruo
Proc. of the 16th Int. Meeting on Reduced Enrichment for Research and Test Reactors, 0, p.313 - 320, 1994/03
no abstracts in English
Matsubayashi, Masahito; Tsuruno, Akira
Neutron Radiography,4, p.415 - 422, 1993/00
no abstracts in English
JAERI-M 87-063, 133 Pages, 1987/04
no abstracts in English
; ; ; ;
JAERI-M 85-047, 81 Pages, 1985/04
no abstracts in English
; ; ; ; Kondo, I.
JAERI-M 6688, 43 Pages, 1976/08
no abstracts in English
H(d,n)
He neutron source by total absorption method using water bath; ; ;
Journal of Nuclear Science and Technology, 12(8), p.491 - 501, 1975/08
Times Cited Count：0no abstracts in English
;
Journal of Nuclear Science and Technology, 5(9), p.447 - 451, 1968/00
Times Cited Count：0no abstracts in English
