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Nagai, Takayuki; Hasegawa, Takehiko*
JAEA-Research 2023-008, 41 Pages, 2023/12
JAEA-Research-2023-008.pdf:7.52MB
To reduce the risks posed by stored the high-level radioactive liquid waste (HAW), Tokai Vitrification Facility (TVF) is working to produce the HAW into vitrified bodies. With the aim of steady vitrification of HAW in TVF, the vitrification technology section has manufactured a new 3rd melter with an improved bottom structure and is working to verify the performance of this melter. In this study, solidified glass samples were taken from simulated vitrified bodies produced by flowing molten glass during the bottom drain-out test in the operation confirmation of the TVF 3rd melter. And the properties of the surface layer and fracture surface of the vitrified bodies were evaluated by using Raman spectroscopy, synchrotron radiation XAFS measurement, and laser ablation inductively coupled plasma atomic emission spectroscopy (LA ICP-AES) analysis. As a result of measuring the surface layer and fracture surface of the solidified samples produced on an actual scale, a slight difference was confirmed between the properties of the surface layer and those of the fracture surface. Since the chemical composition of these simulated vitrified bodies does not contain platinum group elements, it is expected that the glass structure of solidified glass samples is different from that of the actual vitrified body. However, this sample measuring was a valuable opportunity to evaluate samples produced by using the direct energized joule heating method. The properties of cullet used the operation confirmation of the TVF 3rd melter and the cullet of another production lot were measured and analyzed in the same manner under the measuring conditions of solidified glass samples. As a result, it was confirmed that cullet with different producing histories have different glass structures even with the same chemical composition, and that differences in glass structures remain in the glass samples after melting these cullet.
Nagai, Takayuki; Okamoto, Yoshihiro; Shiwaku, Hideaki; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*; Hirono, Kazuya*; Homma, Masanobu*; Kobayashi, Hiromi*; Takahashi, Tomoe*; et al.
JAEA-Research 2018-007, 87 Pages, 2018/11
JAEA-Research-2018-007.pdf:61.21MB
To select the chemical composition of a glass frit which can increase the waste content, the simulated waste glass samples prepared from a borosilicate glass frit including vanadium (V) were investigated by using Laser Ablation (LA) ICP-AES analysis, Raman spectrometry, and synchrotron XAFS measurement in this study on foundation business of the Agency for Natural Resources and Energy.
Hidaka, Akihide; Kudo, Tamotsu; Fuketa, Toyoshi
Transactions of the American Nuclear Society, 91, p.499 - 500, 2004/12
The radionuclides release from MOX under severe accident conditions was investigated in the VEGA program to prepare the technical bases for safety evaluation including PSA for LWR using MOX. The MOX specimen irradiated at ATR Fugen was heated up to 3123K in He at 0.1MPa. The Cs release started at about 1000K and was enhanced below 2200K compared with that of UO
. The possible reason is due to the formation of cracks connected to the high burn-up Pu spots. The total fractional releases were evaluated by alpha-ray, gamma-ray and ICP-AES and compared with the ORNL-Booth model. Although the model was prepared based on the tests with UO, the predictions are in reasonable agreement with the measurements. The VEGA test showed that the total releases from MOX are almost the same as those from UO under extremely severe accident conditions. This indicates that the consequences of LWR using MOX are mostly equal to those using UO. The effect of difference between MOX and UO on the consequences will be systematically investigated using the JAERI's source term code, THALES-2.
Kanazawa, Toru*; Hidaka, Akihide; Kudo, Tamotsu; Nakamura, Takehiko*; Fuketa, Toyoshi
JAERI-Tech 2004-050, 53 Pages, 2004/06
JAERI-Tech-2004-050.pdf:4.35MB
As a part of release evaluation in VEGA program, the mass balances of released and deposited FP onto the test apparatus are estimated from gamma ray measurement for acid solution leached from the apparatus, but short-life or radionuclides without emitting 
rays and very small quantity of elements cannot be quantified. Therefore, a microanalysis by ICP-AES is planed for acid solution leached from apparatuses. Since Cs have strong ray spectrum, they have to be removed from solution in advance to avoid contamination of ICP system and to decrease exposure to ray. The method for Cs separation using inorganic ion exchanger, AMP was applied to the test solutions. The results showed that more than 99.9% of Cs could be removed from test solution, and once removed Sb by AMP was recovered by using a complexing agent such as citric acid. The ICP-AES analysis showed that amount of U, Sr and Zr were successfully quantified. The release and deposition will be quantified through ICP-AES analysis for acid solutions from which Cs is separated by AMP or other precipitation method.
Ito, Mitsuo; Obara, Kazuhiro; Toida, Yukio*; Suzuki, Daisuke; Gunji, Katsubumi*; Watanabe, Kazuo
JAERI-Review 2004-007, 65 Pages, 2004/03
JAERI-Review-2004-007.pdf:5.53MB
no abstracts in English
Shibata, Yasushi*; Matsumura, Akira*; Yamamoto, Tetsuya*; Akutsu, Hiroyoshi*; Yasuda, Susumu*; Nakai, K.*; Nose, Tadao*; Yamamoto, Kazuyoshi; Kumada, Hiroaki; Hori, Naohiko; et al.
Proceedings of 9th International Symposium on Neutron Capture Therapy for Cancer, p.145 - 146, 2000/10
no abstracts in English
Bamba, Tsunetaka; *; Tamura, Yukito; *; Yonezawa, Chushiro; Carter, P.*
Analytical Sciences, 14, p.389 - 394, 1998/04
Times Cited Count：11 Percentile：38.78(Chemistry, Analytical)no abstracts in English
Watanabe, Kazuo; Inagawa, Jun
Analyst, 121, p.623 - 625, 1996/05
Times Cited Count：10 Percentile：41.42(Chemistry, Analytical)no abstracts in English
Watanabe, Kazuo; ;
Bunseki Kagaku, 44(1), p.19 - 23, 1995/00
no abstracts in English
Sumiya, Shuichi; Hayashi, Naomi; ; Narita, Osamu
PNC TN8430 91-001, 45 Pages, 1990/12
A radioanalytical method for low level samarium-151(Sm-151) and promethium-147(Pm-147) in environmental samples has been studied for the environmental assessment around nuclear facilities. In this study, we use the separation method with high performance liquid chromatography (HPLC) to determine Sm-151 and Pm-147 in environmental samples such as sea sediments and marine organisms. Samarium-151 and Pm-147 in environmental samples are coprecipitated with other lanthanoids after adding neodymium(Nd). These nuclides are purified by anion exchange methods in methanol-mineral acid media. After the purification, Sm-151 and Pm-147 are separated with HPLC in lactic acid-sodium hydroxide media, and determined with liquid scintillation counting, respectively. The Nd is determined by inductively coupled plasma atomic emission spectrometry (ICP-AES) to correct chemical recoveries of these nuclides. The detection limits for Sm-151 and Pm-147 in this method are about 0.01Bq/sample.
Kato, Kaneharu
Bunseki Kagaku, 39(8), p.439 - 444, 1990/08
no abstracts in English
Kato, Kaneharu;
Bunseki Kagaku, 39, p.139 - 143, 1990/00
no abstracts in English
; Kato, Kaneharu
Bunseki Kagaku, 39, p.533 - 538, 1990/00
no abstracts in English
At.Spectrosc., 7(5), p.129 - 147, 1986/05
no abstracts in English
Inose, Takehiko*; Nishizawa, Daiji*; Miyauchi, Atsushi; Oyama, Koichi; Yamakawa, Atsushi*; Nagai, Takayuki
no journal, ,
no abstracts in English
Sekine, Naoki; Eda, Takashi; Takasaki, Kazuyuki*; Kawasaki, Takahiro*; Inagawa, Takumu*; Kayano, Masashi
no journal, ,
Japan Atomic Energy Agency's Plutonium Fuel Development Center is considering introducing ICP-AES as a new method for analyzing the metal impurity content in MOX samples. The emission spectra of Pu and U, the main components of MOX samples, are extremely complex, resulting in continuous background increases and spectral interferences. Therefore, in order to accurately quantify the metal impurity elements in the MOX sample, it is necessary to remove Pu and U as a pretreatment for analysis. In this presentation, we will report on the outline and results of experiments related to this pretreatment.
