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Shibano, Koya; Abe, Katsuo; Tsukasa, Kazuo*; Hosogane, Tatsuya; Kayano, Masashi; Sumi, Mika; Fujiwara, Hideki*; Yamaguchi, Kazuya*; Motoki, Chika*
Dai-41-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2020/11
Large-sized dried spikes, called LSD spike, are used as reference material for accountancy analysis for Plutonium and Uranium by Isotope Dilution Mass Spectrometry. LSD spikes preparation is performed each steps as followed (1) Preparing Plutonium and Uranium mix solution, (2) Aliquoting mix solution to vials, and (3) Drying. J-MOX have planned prepared in-house LSD spike and utilized it for accountancy analysis. If LSD spikes are stored for long term, dried material peel off from bottom of vial and it may affect analytical results. In this study, LSD spikes, which have composition suitable for accountancy analysis in J-MOX, had been stored for about 2 years, then long-term stability of LSD spikes had been evaluated.
Tsuji, Hiroshi; Okuno, Kiyoshi*; Thome, R.*; Salpietro, E.*; Egorov, S. A.*; Martovetsky, N.*; Ricci, M.*; Zanino, R.*; Zahn, G.*; Martinez, A.*; et al.
Nuclear Fusion, 41(5), p.645 - 651, 2001/05
Times Cited Count：57 Percentile：83.02(Physics, Fluids & Plasmas)no abstracts in English
Hosogane, Tatsuya
no journal, ,
no abstracts in English
Hosogane, Tatsuya; Ishikawa, Fumitaka; Kageyama, Tomio; Nakazawa, Hiroaki
no journal, ,
Applicability of CR-39, a plastic detector has been examined to apply for the alpha autoradiograph method to determine Pu spot diameter and its Pu concentration in the MOX fuel pellet, that traditionally determined with nitratecellulose film (Pu spot; where segregated Pu locates). This paper reports the results of performance evaluation test of determination of Pu concentration of Pu spot of a MOX fuel pellet by using the CR-39
Ishikawa, Fumitaka; Hosogane, Tatsuya; Sato, Mitsuhiro; Nakazawa, Hiroaki
no journal, ,
Pu spot diameter and Pu concentration in the MOX fuel pellet has been determined by alpha autoradiograph method with nitratecellulose film (Pu spot: where segregated Pu locates). This paper reports the results of comparative test by measuring MOX pellet with nitratecellulose film and CR-39, a plastic detector by Nagase-Landaue, to apply CR-39 for Pu spot determination.
Kodaira, Satoshi*; Yasuda, Nakahiro*; Hosogane, Tatsuya; Ishikawa, Fumitaka; Kageyama, Tomio; Sato, Mitsuhiro
no journal, ,
The plutonium-thermal use is expected as one of the approach for reuse of spent uranium fuel in nuclear power generation. On the other hand, many kinds of nuclides including Pu with extremely long half-lives are generated in the used fuels, which would be problems for storage and control of radioactive waste. The MOX (Mixed Oxide) consisting of plutonium dioxide enriched with 4-9% Pu and uranium oxide from spent uranium fuel would allow to reduce half-lives of radioactive waste significantly through the nuclear fission. The quality of MOX pellet depends on the homogeneous dispersion of Pu. The region of highly concentrated Pu is sometimes observed as "Pu spot" in the pellet, which has the potential of anomalous combustion localized at that region. The detection of Pu spot and evaluation of its size and concentration are one of the important quality assurance of MOX pellet for the safety use in the nuclear power plant. We have applied CR-39 plastic nuclear track detectors for the measurement of Pu spot inside MOX pellet. CR-39 can image a cross-section of MOX pellet by recording 
-particle tracks from Pu in the pellet, like autoradiography. The Pu spot is visibly imaged as a "black spot" due to the dense tracks compared to homogeneously dispersed region. Conventionally, the Pu spot measurement has been carried out with manual scanning, which takes much longer times and huge amount of human work. We have developed the automatic detection and measurement system of Pu spot recorded on CR-39 by the image processing with filtering and clustering algorithms. The detection efficiency with CR-39 is achieved to be almost 100% compared with conventional manual scanning result. It provides more information about the number, size and position of Pu spot.
Hosogane, Tatsuya; Ishikawa, Fumitaka; Kageyama, Tomio; Kayano, Masashi; Kodaira, Satoshi*; Kurano, Mieko*
no journal, ,
For the safe design of MOX fuel, plutonium (Pu) spot analysis is an important control point, thus maximum diameter and Pu content of the Pu spot is defined as MOX fuel specification. Diameter and Pu content of the Pu spot has been analyzed by detecting Pu spot from pictures taken by alpha-autoradiography using commercial imaging analysis software and measure its diameter and content by hand work. Because this method requires a lot of work, automatic detection and measurement system for the Pu spot diameter and Pu content was developed to save workload.
Tazawa, Yuto; Hosogane, Tatsuya; Ishikawa, Fumitaka; Kayano, Masashi; Matsuyama, Kazutomi; Saito, Kosuke; Oishi, Shinichi*; Nakajima, Hiroshi*
no journal, ,
no abstracts in English
