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Journal Articles

Thermal-neutron capture cross-section measurement of tantalum-181 using graphite thermal column at KUR

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

Journal of Nuclear Science and Technology, 58(10), p.1061 - 1070, 2021/10

 Times Cited Count:0 Percentile:0.01(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: $$^{197}$$Au, $$^{59}$$Co, $$^{45}$$Sc, $$^{63}$$Cu, and $$^{98}$$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 $$^{181}$$Ta(n,$$gamma$$)$$^{182m+g}$$Ta reaction was measured using the graphite thermal column, and then derived to be 20.5$$pm$$0.4 barn, which supported the evaluated value of 20.4$$pm$$0.3 barn. The $$^{181}$$Ta nuclide could be useful as a flux monitor that complements the sensitivity between $$^{197}$$Au and $$^{98}$$Mo monitors.

JAEA Reports

Study on residual radioactive inventory estimation in reactor decommissioning program (Contract research)

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.

JAEA Reports

Measurement of two-dimensional thermal neutron flux in a water phantom and evaluation of dose distribution characteristics

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

Journal Articles

Measurement of low energy neutron spectrum below 10keV with the slowing down time method

Maekawa, Fujio; Oyama, Yukio

Nuclear Instruments and Methods in Physics Research A, 372, p.262 - 274, 1996/00

 Times Cited Count:4 Percentile:44.03(Instruments & Instrumentation)

no abstracts in English

JAEA Reports

Measurement of thermal neutron flux for BNCT in JRR-2

; Torii, Yoshiya; ; Ichimura, Shigeju; *; Sasajima, Fumio; *; *; *; Takahashi, Hidetake

JAERI-M 94-058, 45 Pages, 1994/03

JAERI-M-94-058.pdf:1.25MB

no abstracts in English

Journal Articles

Comparison of JRR-4 core neutronic performance between silicide fuel and TRIGA fuel

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

Journal Articles

JRR-3 neutron radiography facility

Matsubayashi, Masahito; Tsuruno, Akira

Neutron Radiography,4, p.415 - 422, 1993/00

no abstracts in English

JAEA Reports

JAEA Reports

JAEA Reports

Correspondence on JMTR and JMTRC (No.34cy.Experiments)

; ; ; ; Kondo, I.

JAERI-M 6688, 43 Pages, 1976/08

JAERI-M-6688.pdf:1.47MB

no abstracts in English

Journal Articles

Standardization of $$^{2}$$H(d,n)$$^{3}$$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:0

no abstracts in English

Journal Articles

Experimental calibration of matching foils for avoiding thermal neutron flux perturbation

;

Journal of Nuclear Science and Technology, 5(9), p.447 - 451, 1968/00

 Times Cited Count:0

no abstracts in English

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