JOPSS - Search Results

Search Results: Records 1-20 displayed on this page of 91

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

JAEA Reports

Development of the desalting method for gross alpha activity determination (Contract research)

Koike, Yuko; Yamada, Ryohei; Nagaoka, Mika; Nakano, Masanao; Ono, Yosuke; Suitsu, Yuichi

JAEA-Technology 2021-011, 39 Pages, 2021/08

JAEA-Technology-2021-011.pdf:1.56MB

In the Analyzed Liquid Treatment Facility of Japan Nuclear Fuel Co., Ltd. (JNFL) MOX Fuel Fabrication Plant (J-MOX), the interfere by salts with the analysis of gross alpha activity concentration analysis will be caused during the treatment process. Therefore, JNFL devised the desalting method using a solid-phase extraction chromatography. Japan Atomic Energy Agency carried out the experimental study to confirm the validity of this desalting method for the treatment liquid based on the contract with JNFL. This study consists of three experiments as follows: Step 1 - Selection of an optical solid-phase extraction agent, Step 2 - Evaluation of variation optical solid-phase extraction agent, and Step 3 - Application of the imitation liquid waste. The result of Step 1 determined the solid-phase extraction agent (InertSep ME-2) and the optimum condition (aspiration method by manifold (about 5-10 mL/min), 3M nitric acid as eluent, pH: 5, and no adjustment of ionic valence). Then, the result of Step 2 and 3 made sure the validation of this method by obtaining over 70% recovery for the imitation liquid waste sample of the Analyzed Liquid Treatment Facility of J-MOX.

Journal Articles

Online solid-phase extraction-inductively coupled plasma-quadrupole mass spectrometry with oxygen dynamic reaction for quantification of technetium-99

Matsueda, Makoto; Yanagisawa, Kayo*; Koarai, Kazuma; Terashima, Motoki; Fujiwara, Kenso; Abe, Hironobu; Kitamura, Akihiro; Takagai, Yoshitaka*

ACS Omega (Internet), 6(29), p.19281 - 19290, 2021/07

https://doi.org/10.1021/acsomega.1c02756

Times Cited Count：2 Percentile：14.88(Chemistry, Multidisciplinary)

Online solid-phase extraction-inductively coupled plasma-quadrupole mass spectrometry with oxygen dynamic reaction cell (online SPE-ICP-MS-DRC) was shown to be a thorough automatic analytical system, circumventing the need for human handling. At three stepwise separations (SPE-DRC-Q mass filters), we showed that interference materials allowed the coexistence of abundance ratios of 1.510 $^{-13}$ for $^{99}$ Tc/Mo. Using this optimized system, a detection limit of $^{99}$ Tc was 9.3 pg/L (5.9 mBq/L) for a 50 mL injection and sequential measurements were undertaken at a cycle of 24 min/sample.

Journal Articles

Separation technique using column chromatography for safeguards verification analysis of uranium and plutonium in highly-active liquid waste by isotope dilution mass spectrometry

Yamamoto, Masahiko; Taguchi, Shigeo; Horigome, Kazushi; Kuno, Takehiko

Proceedings of IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 8 Pages, 2018/11

In this study, the single-column extraction chromatographic separation has been developed for analysis of U and Pu in highly active liquid waste by isotope dilution mass spectrometry (IDMS). The commercially available TEVA $^{textregistered}$ resin is selected as an extraction chromatography resin. The U is chromatographically separated from fission products (FP) elements by nitric acid while Pu(IV) is adsorbed on the resin. After that, Pu is eluted by reducing to Pu(III). The method has been successfully achieved the separation with yielding the enough recovery and sufficient decontamination factors for subsequent IDMS analysis. The column dose rate after the FP removal is decreased to the background. The analytical results obtained by the developed method are in a good agreement with those of the conventional method. It provides simple and rapid separation and expected that the method can be applied to join IAEA/Japan on-site analytical laboratory.

Journal Articles

Preparation of solid phase extraction cartridges for trace analysis of radionuclides

Asai, Shiho; Saito, Kyoichi*

Biomedical Research on Trace Elements, 28(1), p.1 - 10, 2017/04

Radionuclides are commonly determined with radiometry and mass spectrometry. For -emitting nuclides, the activities can be measured without chemical separation due to the strong penetration ability. In contrast, the measurements of alpha and beta-emitting nuclides are generally associated with tedious and time-consuming chemical separation procedures to remove concomitants. Thus, an adsorbent that achieves rapid separation is desirable to reduce separation time and workload. Our research team has developed compact cartridge-type solid phase extraction materials which enable to facilitate separation procedures. In this review, basic separation performances of the developed cartridges were overviewed along with two application examples to radionuclide-containing samples.

Journal Articles

Observation of iron silicide formation by plan-view transmission electron microscopy

Igarashi, Shinichi*; Haraguchi, Masaharu*; Aihara, Jun; Saito, Takeru*; Yamaguchi, Kenji; Yamamoto, Hiroyuki; Hojo, Kiichi

Journal of Electron Microscopy, 53(3), p.223 - 228, 2004/08

https://doi.org/10.1093/jmicro/53.3.223

Times Cited Count：4 Percentile：24.19(Microscopy)

no abstracts in English

Journal Articles

Synthesis of Al $_{x}$ Ga $_{1-x}$ N alloy by solid-phase reaction under high pressure

Saito, Hiroyuki; Utsumi, Wataru; Kaneko, Hiroshi*; Aoki, Katsutoshi

Japanese Journal of Applied Physics, Part 2, 43(7B), p.L981 - L983, 2004/07

https://doi.org/10.1143/JJAP.43.L981

Times Cited Count：5 Percentile：23.97(Physics, Applied)

Bulk specimens of Al $_{x}$ Ga $_{1-x}$ N alloys covering a composition range of 01 were synthesized by a solid-phase reaction under high pressure. X-ray diffraction profiles were measured to observe the alloying process, which began at around 800 $^{circ}$ C under 6.0 GPa. SEM observation and X-ray analysis of the recovered specimen indicated a uniform distribution of Al and Ga and continuous variations of the lattice constants against the composition, which implies that a solid solution of AlN and GaN is formed regardless of atomic composition.

Journal Articles

Absence of recombination of neighboring H atoms in highly purified solid parahydrogen; Electron spin resonance, electron-nuclear double resonance, and electron spin echo studies

Kumada, Takayuki; Sakakibara, Masahiro*; Nagasaka, Toshimitsu*; Fukuta, Hiroya*; Kumagai, Jun*; Miyazaki, Tetsuo*

Journal of Chemical Physics, 116(3), p.1109 - 1119, 2002/01

https://doi.org/10.1063/1.1426410

Times Cited Count：44 Percentile：77.99(Chemistry, Physical)

We have studied diffusion and recombination of H atoms in solid hydrogen using ESR, ENDOR, and ESE spectrometer. The rate constant for recombination of H atoms in highly purified parahydrogen was found to be much smaller than that expected by diffusion coefficient. This result indicates that the H atoms do not recombine in the absence of energy dispersion path in highly purified parahydrogen.

Journal Articles

Effect of flow field on colloid deposition in filtration process of polystyrene latex particles through columns packed glass beads

Chinju, H.*; Nagasaki, Shinya*; Tanaka, Satoru*; Sakamoto, Yoshiaki; Takebe, Shinichi; Ogawa, Hiromichi

Journal of Nuclear Science and Technology, 38(8), p.645 - 654, 2001/08

https://doi.org/10.3327/jnst.38.645

Times Cited Count：3 Percentile：27.1(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

Koshizuka, Seiichi*; *; Okano, Yasushi; *; Yamaguchi, Akira

JNC TY9400 2000-012, 91 Pages, 2000/03

JNC-TY9400-2000-012.pdf:2.82MB

no abstracts in English

JAEA Reports

Modification of the evaluation model for Pu redistribution phenomena

; *;

JNC TN9400 2000-045, 64 Pages, 2000/03

JNC-TN9400-2000-045.pdf:2.47MB

During the irradiation, the Pu redistribution phenomena would occur in the FBR MOX fuel pellets. The phenomena would considerably affect on the thermal properties of the fuels, therefore, it is need to establish the evaluation method for Pu redistribution phenomena. ln JNC, the efforts for development of the evaluation model for the phenomena had been continued and the simple evaluation model was constructed in 1992. In this work, the modification of the simple model developed in JNC has been done and the following results were obtained. (1)Based on the recent data of the MOX fuel irradiation tests, the evaluation model for Pu redistribution phenomena constructed in l992 is modified. And the model is included into the fuel performance analysis code "CEDAR". (2)To calibrate the modified CEDAR code, it is confirmed that the uncertainty in the Pu concentration evaluation for the center of the fuel pellet at EOL is about 3wt.%. (3)Based on the results of the evaluations using the modified CEDAR code, it is found that, in the early stage of the irradiation, the Pu redistribution is controlled by the vapor transportation mechanism via pores, and after that, the Pu redistribution is kept in progress due to the thermal diffusion mechanism with the change of the Pu concentration due to the degradation of U and Pu by fissions. And it is also found that the O/M ratio dependence of the U-Pu inter diffusion coefficients would affect on the Pu redistribution mechanisms, in especial, in the early stage of the irradiation.

Journal Articles

Crosslinking of poly(-caprolactone) by radiation technique and its biodegradability

Yoshii, Fumio; Darwis, D.*; Mitomo, Hiroshi*; Makuuchi, Keizo

Radiation Physics and Chemistry, 57(3-6), p.417 - 420, 2000/03

https://doi.org/10.1016/S0969-806X(99)00449-1

Times Cited Count：63 Percentile：95.73(Chemistry, Physical)

no abstracts in English

JAEA Reports

None

; *; Tokizawa, Takayuki; *

JNC TY6400 2000-013, 102 Pages, 2000/02

JNC-TY6400-2000-013.pdf:2.45MB

None

JAEA Reports

Extrusion analysis of buffer using diffusion model

Sugino, Hiroyuki; *

JNC TN8400 99-040, 75 Pages, 1999/11

JNC-TN8400-99-040.pdf:9.08MB

The buffer material that will be buried as a component of the engineered barriers system swells when saturation by groundwater. As a result of this swelling, buffer material may penetrate into the peripheral rock zone surrounding the buffer through open fractures. If sustained for extremely in long-period of time, The buffer material extrusion could lead to reduction of buffer density, which may in turn degrade the assumed performance assessment properties (e.g., permeability, diffusion coefficient) JNC has been conducted the study of bentonite extrusion into fractures of rock mass as a part of high level waste research. In 1997, JNC has reported the test results concerning buffer material extrusion and buffer material erosion. These tests have been done using test facilities in Geological Isolation Basic Research Facility. After 1997, JNC also conducted analytical study of buffer material extrusion. This report describes the analysis results of this study which are reflected to the H12 report. In this analysis, The diffusion coefficient was derived as a function of the swelling pressure and the viscosity resistance of the buffer materials. Thus, the reduction in density of buffer materials after emplacement in saturated rock was assessed. The assessment was made assuming parallel-plate radial fractures initially filled by water only. Because fractures in natural rock masses inevitably have mineral inclusions inside of them and fractures orientation leads to fractures intersecting other fractures, this analysis gives significantly conservative conditions with respect to long-term extrusion of buffer and possible decrease in buffer density.

JAEA Reports

Sorption and Diffusion Behavior of Palladium in Bentonite, Granodiorite and Tuff

; ; Sato, Haruo; Shibata, Masahiro

JNC TN8400 99-088, 58 Pages, 1999/06

JNC-TN8400-99-088.pdf:3.87MB

Sorption and diffusion behavior of palladium, which has been identified as one of the hazardous radionuclides in performance assessment of HLW disposal, in bentonite, granodiorite and tuff was studied in order to make reliable data set for the performance assessment. Sorption experiments of Pd on bentonite, granodiorite and tuff were conducted as functions of pH, ionic strength and liquid to solid ratio by batch method under aerobic conditions at room temperature. The distribution coefficients (K $_{d}$ ) of Pd on these solids were almost in the range of 10 $^{-1}$ to 10 $^{2}$ m $^{3}$ /kg and were in the order of bentonite granodiorite tuff. The sorption trends with change in PH, ionic strength and liquid to solid ratio are very similar between three solids. The K $_{d}$ values were the highest at pH5 and decreased with increasing pH between 5 and 11. The effect of ionic strength on K $_{d}$ was not found in a range of 10 $^{-2}$ to 10 $^{-1}$ , but K $_{d}$ values increased with increasing liquid to solid ratio. The width of variation in K $_{d}$ was one order of magnitude in a liquid to solid ratio of 0.1 to 1 m $^{3}$ /kg. Sorption behavior of Pd is different from that of divalent metal ions such as Ni and Co etc. and chemical analogy may be inappropriate. The dominant aqueous species of Pd in the expermental conditions studied is estimated to be neutral species, Pd(OH) $_{2}$ (aq) by the thermodynamic calculations. The K $_{d}$ values of Pd on three solids were relatively high and uncharged complexes may be more strongly sorbed. The pH dependency of K $_{d}$ values suggests that Pd sorption is most likely to be occurring onto positively charged S-OH $_{2}$ type site which are progressively removed (to from SOH and SO $_{-}$ sites) at higher pH values. Diffusion behavior of Pd in bentonite was also studied by in-diffusion method as a function of dry density. The D $_{a}$ values obtained based on the instantaneous planar source model were in the orders of ...