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Journal Articles

Measurements of neutron capture cross section of $$^{237}$$Np for fast neutrons

Harada, Hideo; Nakamura, Shoji; Hatsukawa, Yuichi; Toh, Yosuke; Kimura, Atsushi; Ishiwatari, Yuki*; Yasumi, Atsushi*; Mabuchi, Yukio*; Nakagawa, Tsutomu*; Okamura, Kazuo*; et al.

Journal of Nuclear Science and Technology, 46(5), p.460 - 468, 2009/05

 Times Cited Count:4 Percentile:30.49(Nuclear Science & Technology)

The neutron capture cross section of $$^{237}$$Np has been measured for fast neutrons supplied at the center of the core in the Yayoi reactor. The activation method was used for the measurement, in which the amount of the product $$^{238}$$Np was determined by $$gamma$$-ray spectroscopy using a Ge detector. The representative neutron energy and the corresponding capture cross section of $$^{237}$$Np in the experiment were analytically deduced as 0.80 $$pm$$ 0.04 b at 0.214 $$pm$$ 0.009 MeV from the measured reaction rate by combining the energy dependence of the cross section in the nuclear data library ENDF/VII.0. The deduced cross section of $$^{237}$$Np at the representative neutron energy agrees with the evaluated data of ENDF/B-VII.0, but shows 15% larger value than that of JENDL-3.3 and 13% larger value than that of JENDL/AC-2008.

JAEA Reports

Fracture toughness test of 9Cr type steel at elevated temperature (No.1)

*; *; Kano, Shigeki; *; *; *; *

PNC TN9410 89-096, 105 Pages, 1989/05

PNC-TN9410-89-096.pdf:2.31MB

A series of high temperature fracture toughness tests of 9Cr type steel was put in practice on a three-year scheme in 1988, In this experimental study, Mod.9Cr-1Mo steel, 9Cr-2Mo steel and TEMPALOY SW-9(9Cr-1Mo-Nb-V) steel are tested, and fracture toughness (J$$_{Q}$$) of base metal (As-received, SR-treated, Aged) and weldment (weld metal, HAZ) of these three types of steel are investigated. In a first year, fracture toughness tests of base metal (As-received, SR-treated) of Mod.9Cr-1Mo steel were carried out at RT, 400$$^{circ}$$C, 500$$^{circ}$$C, 550$$^{circ}$$C and 600$$^{circ}$$C, respectively. In this report, the test results in the first year are shown. Fracture toughness tests were performed using R-curve method and unloading compliance method according to ASTM E813. The fracture toughness value was the lowest at 400$$^{circ}$$C. Even at 400$$^{circ}$$C, however, Mod.9Cr-1Mo steel showed enough high fracture toughness (J$$_{c}$$$$>$$ 350kJ/m$$^{2}$$), In the fracture toughness test, tearing modurous T$$_{mat}$$ was also measured.

Journal Articles

Preparation of uranium-233

; ; *; ; Saeki, Masakatsu; ; Asano, Masaharu; ; B.Leugger*

Journal of Nuclear Science and Technology, 9(12), p.716 - 720, 1972/12

no abstracts in English

Oral presentation

Study on fast-neutron capture cross section by an activation method

Nakamura, Shoji; Toh, Yosuke; Kimura, Atsushi; Hatsukawa, Yuichi; Harada, Hideo; Ishiwatari, Yuki*; Saito, Isao*; Yasumi, Atsushi*; Mabuchi, Yukio*; Nakagawa, Tsutomu*; et al.

no journal, , 

no abstracts in English

Oral presentation

Measurement of fast-neutron capture cross-section of $$^{99}$$Tc

Nakamura, Shoji; Hatsukawa, Yuichi; Toh, Yosuke; Kimura, Atsushi; Harada, Hideo; Ishiwatari, Yuki*; Yasumi, Atsushi*; Nakagawa, Tsutomu*; Mabuchi, Yukio*; Saito, Isao*; et al.

no journal, , 

Technetium-99 samples were irradiated by fast neutrons at YAYOI reactor. The fast-neutron capture cross-section was measured by the activation method.

Oral presentation

Measurement of fast-neutron capture cross-section of $$^{237}$$Np, 2; Irradiation in the Gz hole of YAYOI reactor

Nakamura, Shoji; Hatsukawa, Yuichi; Toh, Yosuke; Kimura, Atsushi; Harada, Hideo; Ishiwatari, Yuki*; Yasumi, Atsushi*; Nakagawa, Tsutomu*; Mabuchi, Yukio*; Saito, Isao*; et al.

no journal, , 

The $$^{237}$$Np sample was irradiated at the Gz hole of YAYOI reactor, and the fast-neutron capture cross-section was obtained by an activation method. The production amount of $$^{238}$$Np was measured by $$gamma$$-ray spectroscopy. The neutron flux at the irradiation position was monitored by a gold foil. It was found that the present result of the fast-neutron capture cross-section was 15% larger than that in JENDL-3.3.

Oral presentation

Measurement of fast-neutron capture cross-section of $$^{129}$$I

Nakamura, Shoji; Toh, Yosuke; Hatsukawa, Yuichi; Kimura, Atsushi; Harada, Hideo; Yasumi, Atsushi*; Nakagawa, Tsutomu*; Mabuchi, Yukio*; Saito, Isao*; Ishiwatari, Yuki*

no journal, , 

The fast-neutron capture cross section of $$^{129}$$I was measured at the YAYOI reactor by the activation method. The amount of $$^{130}$$I was obtained by measuring $$gamma$$-rays emitted from $$^{130}$$I. The neutron flux was monitored by a piece of gold foil. The fast-neutron capture cross section was derived from the information of the production amount of $$^{130}$$I and the neutron flux. This work found that the evaluated data might be overestimated by about 10% and more.

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