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-ray spectrometry; Application of 
pre-concentration from large volume of water sample using Powdex resin and barium sulfate coprecipitation of radium isotopesTomita, Jumpei; Abe, Takuya
JAEA-Research 2016-026, 12 Pages, 2017/03
JAEA-Research-2016-026.pdf:1.15MB
An analytical method of low-level Ra isotopes in freshwater samples with combination of pre-concentration from large volume of water sample (
170 L) using Powdex resin and -ray spectrometry followed by simple coprecipitation of Ra was developed. 
pre-concentration of Ra by batch method using Powder resin was examined, and it was shown that the amount of the resin required collecting Ra in the water sample could be determined by measuring the electric conductivity (EC) of water sample. It was found that coprecipitation of Ra with barium sulfate could remove more than 96% of potassium that increases the background. The validation of this method was confirmed by the analyses of 170 L of water sample containing the known amount of Ra isotopes with different EC. Among the analyses, the recovery of Ra was 98% in average and detection limits of 
Ra and 
Ra were achieved to be approximately 0.3 and 0.5 mBq L
, respectively.
Ishihara, Keisuke; Yokota, Akira; Kanazawa, Shingo; Iketani, Shotaro; Sudo, Tomoyuki; Myodo, Masato; Irie, Hirobumi; Kato, Mitsugu; Iseda, Hirokatsu; Kishimoto, Katsumi; et al.
JAEA-Technology 2016-024, 108 Pages, 2016/12
JAEA-Technology-2016-024.pdf:29.74MB
Radioactive isotope, nuclear fuel material and radiation generators are utilized in research institutes, universities, hospitals, private enterprises, etc. As a result, various low-level radioactive wastes (hereinafter referred to as non-nuclear radioactive wastes) are produced. Disposal site for non-nuclear radioactive wastes have not been settled yet and those wastes are stored in storage facilities of each operator for a long period. The Advanced Volume Reduction Facilities (AVRF) are built to produce waste packages so that they satisfy requirements for shallow underground disposal. In the AVRF, low-level beta-gamma solid radioactive wastes produced in the Nuclear Science Research Institute are mainly treated. To produce waste packages meeting requirements for disposal safely and efficiently, it is necessary to cut large radioactive wastes into pieces of suitable size and segregate those depending on their types of material. This report summarizes activities of pretreatment to dispose of non-nuclear radioactive wastes in the AVRF.
Manabe, Sachi; Matsubara, Natsumi; Saegusa, Jun; Takeishi, Minoru
KEK Proceedings 2016-8, p.281 - 285, 2016/10
no abstracts in English
C collected by precipitation and gas-strip methods for dating groundwaterNakata, Kotaro*; Hasegawa, Takuma*; Iwatsuki, Teruki; Kato, Toshihiro
Radiocarbon, 58(3), p.491 - 503, 2016/09
Times Cited Count：5 Percentile：21.51(Geochemistry & Geophysics)Dissolved inorganic carbon (DIC) for C analysis of groundwater is usually extracted by a gas-strip or precipitation method. In this study, the certainty of the two methods for C dating were confirmed. DIC and C concentrations obtained by the gas-strip method were close to the theoretically predicted C value. Conversely, the C value obtained by the precipitation method always showed higher values than the predicted values. The difference in C value between gas-strip and precipitation methods was assumed to arise owing to contamination of modern carbon used in the precipitation method. The applicability of the precipitation method for groundwater should be considered carefully according to the DIC, C concentration of groundwater and purpose of the study being conducted.
Minami, Masayo*; Takahashi, Hiroshi*; Aramaki, Takafumi*; Kokubu, Yoko; Ito, Shigeru*; Nakamura, Toshio*
Nagoya Daigaku Kasokuki Shitsuryo Bunsekikei Gyoseki Hokokusho, 26, p.132 - 137, 2015/03
We have started a Radiocarbon Intercomparison on Chemical Experiments, Water series (RICE-W) program to examine whether carbon isotopic fractionation and carbon contamination occur or not on C analysis of dissolved inorganic carbon (DIC) in water by different sample preparation and storage methods. Eight water samples of four kinds (surface seawater, ground water, hot spring water, and sodium bicarbonate solution) have already analyzed by six AMS laboratories in Japan, and the results obtained are gradually being published. Here, we report the progress of RICE-W program briefly, and then give consideration to the result using the precipitation method, by which DIC is precipitated into SrCO
or BaCO, and then oxidized with HPO
to extract CO
.
Seko, Noriaki; Kasai, Noboru; Tamada, Masao; Hasegawa, Shin; Katakai, Akio; Sugo, Takanobu*
JAERI-Tech 2004-076, 78 Pages, 2005/01
JAERI-Tech-2004-076.pdf:17.11MB
In September 1999, we have soaked 200 kg of fibrous amidoxime adsorbents, synthesized by radiation-induced graft polymerization, into seawater to evaluate their performance. Fractional elution facility was set effectively to elute the rare metals on adsorbents in Mutsu-Establishment. This facility consists of two parts of pre-washing and elution. The present report dealt with planning, manufacture and setting of fractional facility. Marine organism and slime on adsorbent cassette (290
290160 mm) were washed out and every 72 cassettes were set in elution unit (12101210H1460 mm) with nonwoven materials as a packing to avoid elution loss. In the elution process alkaline and alkaline earth metals were eluted with low concentration hydrochloric acid (0.01M) and rare metals were eluted with high concentration (0.5M) after the packing of elution unit into fractional elution facility.
Shiraishi, Tomoyuki*; Tamada, Masao; Saito, Kyoichi*; Sugo, Takanobu
Radiation Physics and Chemistry, 66(1), p.43 - 47, 2003/01
Times Cited Count：50 Percentile：93.91(Chemistry, Physical)no abstracts in English
; Murata, Eiichi*; Sawahata, Yoshikazu*; Saito, Akira*
JNC TN8430 2001-002, 43 Pages, 2001/02
JNC-TN8430-2001-002.pdf:1.98MB
Japan Nuclear Cycle Development Institute (JNC) is designing the Low level radioactive Waste Treatment Facility (LWTF) in the Tokai Reprocessing Plant (TRP). The low level liquid waste generated the TRP is separated salt (NaNO, etc) and radionuclide in liquid treatment process of LWTF. The process can get higher volume reduction than previous bituminization. Based on the engineering tests equal to the liquid treatment process of LWTF, the validity of operational condition in LWTF is evaluated. As the results, it is confirmed that all operational condition in the processes which is Iodine immobilization, Pre-filter filtration, Pre-treatment, Coprecipitation and Ultrafiltration are available.
Osoda, Tsutomu*; Maruyama, Kunihide*; Washio, Takumi*; Doi, Shun*; Yamada, Susumu
Joho Shori Gakkai Rombunshi, 41(SIG8), p.92 - 100, 2000/11
no abstracts in English
*; *
JNC TJ7400 2000-001, 79 Pages, 2000/02
JNC-TJ7400-2000-001.pdf:3.07MB
no abstracts in English
*; Yokokawa, Mitsuo;
Keisan Kogaku Koenkai Rombunshu, 1(1), p.377 - 380, 1996/05
no abstracts in English
; Miyazaki, Hitoshi; ; Tanimoto, Kenichi; Terunuma, Seiichi
PNC TN9420 94-010, 103 Pages, 1994/04
None
; ; ; ; ; ;
PNC TN8520 93-003, 410 Pages, 1994/01
This manual includes the standard procedures for analysis of radioactive materials and chemical polluants in liquid and gaseous waste elluent discharged into the environment from the nuclear facilities of Tokai Works of PNC. The third edition, PNC N852-84-06 was published in 1984. Almost all analytical procedures have been modified and new technique has been used for nine years, so the forth edition revised entirely was to be published this time. And most of analytical procedures will be revised with the point of improving of reliabiliy.
K.-W.Kim*; J.-D.Kim*; Aoyagi, Hisao; ; Yoshida, Zenko
Journal of Nuclear Science and Technology, 30(6), p.554 - 559, 1993/06
Times Cited Count：6 Percentile：55.97(Nuclear Science & Technology)no abstracts in English
Kurosawa, A.; Abe, Katsuo; Kaminaga, Kazuhiro; Kuno, Yusuke; ;
PNC TN8410 93-031, 191 Pages, 1993/03
So far, samples have been taken by both Japan Government and the International Atomic Energy Agency (IAEA) from the feed accounting tank of the Reprocessing Plant. Upon transporting the samples, one A-type transport container per batch sample has been required. To simplify the transport of samples, the resin bead technique requiring the trace amounts of samples (several mg for uranium and for plutonium) has been developed with the Oak Ridge National Laboratory, USA being the center. This technique was introduced into the Power Reactor and Nuclear Fuel Development Corporation (PNC) as part of the TASTEX project, and then has been incorporated into the JASPAS project as one of the joint researches between the PNC and the IAEA, in which the PNC has played a leading role. Up to now, joint experiments have been performed seven times, and the resin bead technique may have reached a certain technical level with a few technical problems. In these joint experiments, the PNC prepared and transported samples, whereas the IAEA analysed them. In addition, the PNC has investigated the resin bead technique independently. As mentioned above, the most outstanding merit of the resin bead technique lies in the simplified transport of samples. The technique is also provided with another merit by which uranium and plutonium can be measured without separating them from each other, leading to the necessity of research and development of it on the part of the Reprocessing Plant. This paper describes the results of investigation on the measurement technique of uranium and plutonium by means of the resin bead technique, together with the results from the 3rd to 7th PNC-IAEA joint experiments.
Hayashi, Koji
JAERI-M 93-041, 152 Pages, 1993/03
no abstracts in English
