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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.

JAEA Reports

None

*

JNC TN1400 2000-003, 252 Pages, 2000/07

JNC-TN1400-2000-003.pdf:13.33MB

None

Journal Articles

Development of fast neutron radiography imaging technique using imaging plate

Matsubayashi, Masahito; Yoshii, Koji*; Hibiki, Takashi*; Mishima, Kaichiro*

Kashika Joho Gakkai-Shi, 20(Suppl.1), p.325 - 328, 2000/07

no abstracts in English

JAEA Reports

Irradiation test of HAFM and tag gas samples at the standard neutron field of "YAYOI"

*

PNC TJ9602 96-004, 49 Pages, 1996/03

PNC-TJ9602-96-004.pdf:1.53MB

To check the accuracy of helium accumulation neutron fluence monitoring (HAFM) technique and the applicability of tag gas activation analysis to fast reactor failed fuel detection, these samples were irradiated at the standard neutron field of the fast neutron source reactor "YAYOI" (Nuclear Engineering Research Laboratory, University of Tokyo). The HAFM samples of 93% enriched B powder of 1 mg contained in a V capsule were set up in the reactor core center (Glory hole :Gy) and another samples including V encapsulated natural B powder of 10 mg, natural B chips and 96% enriched $$^{6}$$LiF thermoluminescence dosimeters were in the leakage neutron field from the reactor core (Fast column :FC). These neutron fields were monitored by the activation foils consisting of Al, Fe, Co, Ni, Cu, Ti, In, Au, $$^{235}$$U, $$^{237}$$Np etc., which were used to derive the neutron flux and spectrum. At the end of March in 1996, the irradiated neutron fluence in the energy more than 0.1Mev reached up to $$sim$$ 1.1$$times$$10$$^{17}$$ n/cm$$^{2}$$ at Gy and $$sim$$5.4$$times$$10$$^{14}$$ n/cm$$^{2}$$ at FC, respectively. Two kinds of tag gas samples, which are the mixed gases of isotipically adjusted Xe and Kr contained in stainless steel (SUS) capsules, were irradiated twice at Gy; one is up to $$sim$$9kWh and the other $$sim$$7kWh, and after the irradiation, $$gamma$$-ray spectra were measured for each sample. Through comparison with the $$gamma$$-ray spectrum from dummy capsule of no tag gas, the $$gamma$$-ray peaks of $$^{79}$$Kr, $$^{125}$$Xe etc., which would be produced from tag gas activation, were able to be clearly identified.

Journal Articles

Journal Articles

Verification experiment of threshold detector $$^{1}$$$$^{0}$$$$^{7}$$Ag(n,n')$$^{1}$$$$^{0}$$$$^{7}$$$$^{m}$$Ag on YAYOI standard neutron field

; Kondo, I.; Nakazawa, Masaharu*

Journal of Nuclear Science and Technology, 18(12), p.949 - 956, 1981/00

no abstracts in English

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