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Journal Articles

Development of correction method for sample density effect on PGA

Maeda, Makoto; Segawa, Mariko; Toh, Yosuke; Endo, Shunsuke; Nakamura, Shoji; Kimura, Atsushi

Journal of Radioanalytical and Nuclear Chemistry, 332(8), p.2995 - 2999, 2023/08

 Times Cited Count:0 Percentile:0.01(Chemistry, Analytical)

Journal Articles

Challenges for enhancing Fukushima environmental resilience, 3; Development of measurement and evaluation techniques for the environmental radiation monitoring

Sanada, Yukihisa

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 59(7), p.418 - 422, 2017/07

no abstracts in English

Journal Articles

Introduction to development of advanced safeguards and security NDA technologies by JAEA-ISCN

Seya, Michio; Kureta, Masatoshi; Soyama, Kazuhiko; Nakamura, Hironobu; Harada, Hideo; Hajima, Ryoichi

Proceedings of INMM 55th Annual Meeting (Internet), 10 Pages, 2014/07

JAEA has been implementing development programs of basic technologies of the following advanced NDA (non-destructive assay) of nuclear material (NM) for nuclear safeguards and security. (1) Alternative to $$^{3}$$He neutron detection using ZnS/B$$_{2}$$O$$_{3}$$ ceramic scintillator, (2) NRD (neutron resonance densitometry) using NRTA (neutron resonance transmission analysis) and NRCA (neutron resonance capture analysis), (3) NRF (nuclear resonance fluorescence)-NDA using laser Compton scattered (LCS) $$gamma$$-rays (intense mono-energetic $$gamma$$-rays). The development program (1) is for NDA systems that use ZnS/B$$_{2}$$O$$_{3}$$ ceramic scintillator as alternative neutron detector to $$^{3}$$He for coming shortage of its supply. The program (2) is for a NDA system of isotopic composition measurement (non-destructive mass spectroscopy) in targets such as particle-like melted fuel debris using NRTA and NRCA. The program (3) is for NDA systems using a specific NRF reaction of certain Pu/U isotope caused by mono-energetic LCS $$gamma$$-ray with energy tuned to the specific excited state of the isotope. This paper introduces above three programs.

JAEA Reports

Measurements of power profile in TRACY supercritical experiment by detecting epithermal neutrons

Nakajima, Ken; Yanagisawa, Hiroshi; Miyoshi, Yoshinori

JAERI-Tech 2003-028, 31 Pages, 2003/03

JAERI-Tech-2003-028.pdf:1.38MB

We have tried to measure the power profile in the TRACY supercritical experiment with high accuracy by detecting epithermal neutrons. In order to measure the epithermal neutrons, a cadmium covered $$^{235}$$U fission chamber was used, and polyethylene, a neutron moderator, was set inside the cadmium to enhance the neutron detection efficiency. In addition, a lead shield was used to reduce the noise current due to gamma-rays. The measured results were compared with the ones using a thermal neutron detector, and it was found that the time delay effect in the thermal neutron detection, which was caused by the flight time of neutrons to reach the detector, distorted the power profile and reduced its peak value. The reduction ratio of peak power was about 4% for the relatively slow power change with the inserted reactivity of 1.5$, but it became over than 40% for the rapid power change with the reactivity of about 3$.

Journal Articles

Gamma-ray measurements in JT-60U ICRF heated plasma

Kondoh, Takashi; Kimura, Haruyuki; Kusama, Yoshinori; Morioka, Atsuhiko; Moriyama, Shinichi; Saigusa, Mikio; Nagashima, Keisuke; Yoshino, Ryuji; Harano, Hideki*

Purazuma, Kaku Yugo Gakkai-Shi, 72(12), p.1397 - 1405, 1996/12

no abstracts in English

Journal Articles

Irradiation and ESR analysis temperature dependence of the gamma-ray response of alanine-polystyrene dosimeters

Kojima, Takuji; Morishita, Norio; Ito, Hisayoshi; S.Biramontri*

Applied Radiation and Isotopes, 47(4), p.457 - 459, 1996/00

 Times Cited Count:4 Percentile:39.38(Chemistry, Inorganic & Nuclear)

no abstracts in English

Journal Articles

Measurement techniques for fusion blanket neutronics experiments

Oyama, Yukio; Konno, Chikara; Ikeda, Yujiro; Maekawa, Fujio; Maekawa, Hiroshi; ; ; Nakamura, Tomoo; M.A.Abdou*; Bennett, E. F.*; et al.

Fusion Engineering and Design, 28, p.716 - 723, 1995/00

 Times Cited Count:5 Percentile:49.46(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Determination of Pu amount in a waste carton by gamma-ray measurement

J.Inst.Nucl.Mater.Manage., 10(4), p.22 - 29, 1981/00

no abstracts in English

Journal Articles

Non-destructive gamma-ray spectrometry on spent fuels of a boiling water reactor

Matsuura, Shojiro; ; ; ; Umezawa, Hirokazu;

Journal of Nuclear Science and Technology, 12(1), p.24 - 34, 1975/01

 Times Cited Count:23

no abstracts in English

Journal Articles

Computer Network For Radiation Measurement

; ; ; ;

Dai-16-Kai Puroguramingu Shimpojiumu Hokokushu, p.283 - 297, 1975/00

no abstracts in English

10 (Records 1-10 displayed on this page)
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