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Journal Articles

Establishment of a Laboratory for $$gamma$$-ray Spectrometry of Environmental Samples Collected in Fukushima

Saegusa, Jun; Yoda, Tomoyuki; Maeda, Satoshi; Okazaki, Tsutomu; Otani, Shuichi; Yamaguchi, Toshio; Kurita, Yoshiyuki; Hasumi, Atsushi; Yonezawa, Chushiro*; Takeishi, Minoru

Proceedings of 14th International Congress of the International Radiation Protection Association (IRPA-14), Vol.3 (Internet), p.1078 - 1085, 2017/11

After the nuclear accident at the Fukushima Daiichi Nuclear Power Plant in March 2011, the Japan Atomic Energy Agency has newly set up a laboratory for radioactivity analysis in Fukushima. At the laboratory, radioactivity concentrations of environmental samples such as soil, water, dust filter, plant, etc., approximately 1,000 samples in a month, are measured with high-resolution $$gamma$$-ray spectrometry systems. The systems employ n-type HPGe detectors from Ortec. Since September 2012, characterization and upgrade of the systems have been performed aimed at enhancing reliability of analysis and convenience of customers. Resolving both systematic and technical issues, the laboratory has been accredited the ISO/IEC 17025 standard as a testing laboratory for radioactivity analysis.

JAEA Reports

Study on the evaluation method to determine the radioactivity concentration waste generated from post-irradiation examination facilities

Hoshino, Yuzuru; Sakamoto, Yoshiaki; Muroi, Masayuki*; Mukai, Satoru*

JAEA-Technology 2015-015, 96 Pages, 2015/07

JAEA-Technology-2015-015.pdf:20.34MB

In order to dispose of the radioactive waste which generates from post-irradiation examination (PIE) facilities, the common evaluation method of radioactivity in wastes from PIE should be established by the actual data such as radioactivity values and the theoretical calculation. In this study, the radioactivity concentrations of 17 nuclides (H-3, C-14, Co-60, Ni-63, Sr-90, Tc-99, Cs-137, Eu-154, U-234, U-235, U-238, Pu-238, Pu-239, Pu-240, Pu-241, Am-241, Cm-244) in combustible wastes stored in NUCLEAR DEVELOPMENT CORPORATION were measured from 3 samples and the radioactivity was calculated by ORIGEN-2 based on initial contents and operation record of the spent fuel. From the comparison of the obtained data by the radiological measurement with the calculated values, the subject to be solved for establishment of the radioactivity evaluation method for PIE was extracted.

JAEA Reports

Consecutive determination of pentavalent neptunium by spectrophotometric method

Tanaka, Tadao; Kamiyama, Hideo

JAERI-M 93-035, 22 Pages, 1993/03

JAERI-M-93-035.pdf:0.54MB

no abstracts in English

Journal Articles

Inherent isotope dilution analysis of $$^{2}$$$$^{3}$$$$^{7}$$Np in spent nuclear fuels

; K.Kammerichs*; L.Koch*

Journal of Radioanalytical and Nuclear Chemistry, Letters, 117(4), p.233 - 241, 1987/04

no abstracts in English

Journal Articles

Low level $$alpha$$ activity measurements with pulse shape discrimination(I),(II)

; *; *

Radioisotopes, 33(12), p.835 - 840, 1984/00

no abstracts in English

Journal Articles

Radioactivity analysis

; ; ; ; ; *; *; *; *; *

Bunseki Kagaku, 16(13), p.96R - 122R, 1967/00

no abstracts in English

Oral presentation

Outline of Sasakino Analytical Laboratory, Fukushima Environmental Safety Center of JAEA

Saegusa, Jun; Yanagisawa, Kayo; Yamaguchi, Toshio; Manabe, Sachi; Yoda, Tomoyuki; Maeda, Satoshi; Utsumi, Azusa; Shibamichi, Masaru; Ejiri, Akira; Kurita, Yoshiyuki; et al.

no journal, , 

no abstracts in English

Oral presentation

Advancement of $$gamma$$-spectrometry with Ge semiconductor detectors for the analysis of environmental soil samples

Saegusa, Jun; Maeda, Satoshi; Kurita, Yoshiyuki; Yoda, Tomoyuki; Takeishi, Minoru

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

$$alpha$$-emitting nuclides analysis of the stagnant water including sediments in Fukushima Daiichi NPS, 8; Behavior of moving to sediment of Pu and Am

Nitta, Ayako; Hinai, Hiroshi; Kitawaki, Shinichi; Koma, Yoshikazu

no journal, , 

no abstracts in English

Oral presentation

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