Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 34

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 ...

Save select records

Journal Articles

Doppler-free ablation fluorescence spectroscopy of Ca for high-resolution remote isotopic analysis

Miyabe, Masabumi; Kato, Masaaki*; Hasegawa, Shuichi*

Journal of Analytical Atomic Spectrometry, 38(2), p.347 - 358, 2023/02

 Times Cited Count:0 Percentile:0.02(Chemistry, Analytical)

To develop remote isotopic analysis for the nuclids with small isotope shifts, Doppler-free fluorescence spectroscopy of Ca was performed using laser ablation plume. Counter-propagating laser beams from two external cavity diode lasers were used to irradiate the plume in order to excite the ground-state Ca atoms to the $$^{1}$$D$$_{2}$$ state through a double resonance scheme of $$^{1}$$S$$_{0}$$ $$rightarrow$$ $$^{1}$$P$$_{1}$$ $$rightarrow$$ $$^{1}$$D$$_{2}$$. Subsequently, we measured fluorescence spectra associated with the relaxation from the $$^{1}$$D$$_{2}$$ to $$^{1}$$P$$_{1}$$ states. The linewidth measured at 1 ms delay after ablation under helium gas pressure of 70 Pa was found to be less than 70 MHz, which was about 1/30 of the linewidth of the Doppler-limited fluorescence spectrum. A broad Gaussian pedestal was observed at less than 600 micro-second delay in the temporal variation in fluorescence spectra, and it was most likely due to the velocity-changing collision. Additionally, the pressure broadening rate coefficient for the second-step $$^{1}$$P$$_{1}$$$$rightarrow$$ $$^{1}$$D$$_{2}$$ transition was determined to be 46.0 MHz/torr from the spectra measured under various gas pressures. We evaluated analytical performances such as linearity of the calibration curve, limit of detection, and measurement accuracy using fluorescence signals of three naturally occurring Ca isotopes (i.e., $$^{40}$$Ca, $$^{42}$$Ca, and $$^{44}$$Ca). The limit of detection of isotopic abundance was estimated to be 0.09% from the 3-sigma criteria of the background. These results suggest that this spectroscopic technique is promising for remote isotopic analysis of nuclides with small isotope shifts.

Journal Articles

Radiochemical analysis of the drain water sampled at the exhaust stack shared by Units 1 and 2 of the Fukushima Daiichi Nuclear Power Station

Shimada, Asako; Taniguchi, Yoshinori; Kakiuchi, Kazuo; Ohira, Saki; Iida, Yoshihisa; Sugiyama, Tomoyuki; Amaya, Masaki; Maruyama, Yu

Scientific Reports (Internet), 12(1), p.2086_1 - 2086_11, 2022/02

 Times Cited Count:1 Percentile:31.61(Multidisciplinary Sciences)

no abstracts in English

Journal Articles

Construction of a laser Compton scattered photon source at cERL

Nagai, Ryoji; Hajima, Ryoichi; Mori, Michiaki; Shizuma, Toshiyuki; Akagi, Tomoya*; Honda, Yosuke*; Kosuge, Atsushi*; Urakawa, Junji*

Proceedings of 5th International Particle Accelerator Conference (IPAC '14) (Internet), p.1940 - 1942, 2014/07

In order to demonstrate required accelerator and laser technologies for a high intensity $$gamma$$-ray source from the laser Compton scattering (LCS), an LCS photon source and the peripheral equipment are under construction at the Compact ERL (cERL) at High Energy Accelerator Research Organization (KEK). The LCS photon source by an electron beam in the energy-recovery linac (ERL) is a key technology for a nondestructive assay system to identify nuclear species. The LCS photon source and the peripheral equipment consist of a mode-locked fiber laser, laser enhancement cavity, beamline, and experimental hatch. The commissioning of the LCS photon source will be started in February 2015.

Journal Articles

Analysis of nuclear fuel cycle related materials

Sato, Soichi*; Suzuki, Toru*; Hiyama, Toshiaki*; Watanabe, Kazuo

Bunseki, 2005(8), p.451 - 457, 2005/08

no abstracts in English

JAEA Reports

Radiation control on wastes recovery work in wastes storage pit

Ito, Yasuhisa; Noda, Kimio; ;

JNC TN8410 2001-018, 67 Pages, 2001/04

JNC-TN8410-2001-018.pdf:2.96MB

There are waste storage pits where non-radioactive wastes generated from plutonium fuel facilities were stored in JNC Tokai Works. But radioactive wastes were found in one of the pit during wastes arrangement works. Therefore we set the pit temporary controlled area and recovered wastes from it. This report describes the radiation control technique of recovery work in detail.

JAEA Reports

None

PNC TJ1309 98-001, 161 Pages, 1998/02

PNC-TJ1309-98-001.pdf:5.01MB

no abstracts in English

JAEA Reports

Development of accurate CP distribution measurement FBR plant using a plastic scintillation fiber detector

Sumino, Kozo; Aoyama, Takafumi; Emoto, Takehiko

PNC TN9410 96-233, 27 Pages, 1996/08

PNC-TN9410-96-233.pdf:0.96MB

It is important to accurately evaluate Corrosion Products (CPs) behavior in a FBR plant to reduce the personnel exposure due to CP deposition. A series of measurements of the gamma-ray dose rate distribution has been carried out in the Experimental Fast Reactor JOYO to characterize the CP behavior in the primary coolant system. The Plastic Scintillation Fiber (PSF), which is a position sensitive radiation detector that can detect the radiation dose rate at the relevant position in the fiber, was introduced to upgrade the gamma-ray distribution measurement in JOYO. In order to apply the PSF for the JOYO environment, the specification of the fiber was modified to obtain a wide range of sensitivity from about 0.01mSv/h up to 10mSv/h. This range covers the gamma-ray dose rate in the JOYO primary coolant system. In higher gradients of dose rate distribution than that of the PSF's position resolution, the measured data were unfolded by using the response matrix with a successive approximation method to reproduce the narrow distribution. As a result of the study on PSF, the continuous gamma-ray dose rate distribution was able to be measured by PSF in a few minutes, whereas point data at 1 m intervals were laboriously obtained by a set of Thermo-luminescence Dosimeters (TLDs). It was confirmed that the measurement of CP behavior upgraded significantly by using a detailed gamma-ray dose rate distribution.

JAEA Reports

Realistic contamination control methods at $$alpha$$ and $$beta$$($$gamma$$) nuclide coexistence facilities

Ando, Hideki;

PNC TN9100 96-007, 32 Pages, 1996/03

PNC-TN9100-96-007.pdf:1.09MB

At the light water reactors with no fuel failure, radioactive contamination control is needed for $$beta$$($$gamma$$) nuclides such as $$^{60}$$Co and $$^{54}$$Mn. On the other hand, at the nuclear facilities where irradiated fuels (spent fuels) are handred, contamination control is needed for many kinds of $$alpha$$ and $$beta$$($$gamma$$) nuclides. There are three facilities where destructive testing of irradiated fuels and materials is done at Oarai Engineering Center. The ratios of the nuclidc composition are considerably stable at these facilities. Therefore, daily contamination control is cxecuted by measuring total (gross) $$beta$$($$gamma$$) activity with paying attention to the representative nuclides such as $$^{239}$$Pu, $$^{241}$$Pu and $$^{90}$$Sr. The investigation about the ratios of the nuclide composition, the basic idea of the contamination control, and the reality of the contamination control in the facilities are reported.

Journal Articles

Analytical chemistry for the environmental monitoring techniques for safeguards applications(1),(2)

Watanabe, Kazuo

Kaku Busshitsu Kanri Senta Nyusu, 25,26(12,1), p.5 - 6, 1996/00

no abstracts in English

JAEA Reports

None

PNC TJ1678 95-003, 97 Pages, 1995/02

PNC-TJ1678-95-003.pdf:2.59MB

None

JAEA Reports

Visualization of atmospheric diffusion with Mathematica

Shinohara, Kunihiko

PNC TN9410 92-339, 47 Pages, 1992/11

PNC-TN9410-92-339.pdf:18.25MB

The calculation of atmospheric concentrations of radionuclides discharged from nuclear facilities is the first step for environmental dose assessment. Gaussian diffusion equation is usually used for the calculation. Computer programs such as ANDOSE and ORION-II have been developed by using of the equation and applied with meteorological data to evaluuate dose equivalents in the environment. results are shown numerically by the computer codes. However, if the results are shown in visualized form, it may be very useful to understand the diffusion phenomena and will also be helpful for beginners of the environmental dose assessment In the report, atmospheric diffusions and depositions by Gaussian equation have been visualized with mathematica. Almost text and graphics in the report are the direct print of mathematica's Note Book.

JAEA Reports

Summary report on the environmental monitoring around O-arai area following the accident at chernobyl atomic power station

*; Shindo, Katsutoshi*; *

PNC TN9410 86-117, 145 Pages, 1986/10

PNC-TN9410-86-117.pdf:20.03MB

An accident has occurred at the Chernobyl atomic power station, USSR on April 26, 1986. By this accident, a lot of radioactive debris was released into the atomosphere, and in all parts of Japan, as well as European countries, that debris was observed in the rain, airborne just and other environmental samples. This report presents a summary of the environmental monitoring performed at O-arai Engineering Center for the period of April 30 - July 4, 1986. Furthermore, preliminary estimation of commited dose equivalent to the public in O-arai area is included.

Journal Articles

Separation of zinc-65 by the dithizone-chloroform extraction

Dai-8-Kai Nihon Aisotopu Kaigi Hobunshu, B-(2)-4, p.260 - 262, 1965/00

no abstracts in English

Oral presentation

Development of multiple prompt $$gamma$$-ray analysis by using a pulsed neutron beam at J-PARC

Toh, Yosuke; Ebihara, Mitsuru*; Huang, M.; Segawa, Mariko; Kimura, Atsushi; Nakamura, Shoji; Furutaka, Kazuyoshi

no journal, , 

no abstracts in English

Oral presentation

Feasibility of time-of-flight prompt $$gamma$$-ray analysis of a radionuclide sample

Toh, Yosuke; Huang, M.; Ebihara, Mitsuru*; Segawa, Mariko; Kimura, Atsushi; Nakamura, Shoji

no journal, , 

no abstracts in English

Oral presentation

Next-generation techniques of non-destructive elemental analysis in ANNRI

Toh, Yosuke

no journal, , 

no abstracts in English

Oral presentation

Nondestructive analysis of radioactive nuclides in J-PARC ANNRI

Toh, Yosuke; Ebihara, Mitsuru*; Huang, M.; Kimura, Atsushi; Nakamura, Shoji; Segawa, Mariko

no journal, , 

no abstracts in English

Oral presentation

Development of multiple prompt $$gamma$$-ray analysis by using a pulsed neutron beam at J-PARC ANNRI

Toh, Yosuke; Ebihara, Mitsuru*; Huang, M.; Segawa, Mariko; Kimura, Atsushi; Nakamura, Shoji

no journal, , 

no abstracts in English

Oral presentation

Development of time of flight prompt $$gamma$$-ray analysis in J-PARC ANNRI and its application

Toh, Yosuke; Huang, M.; Ebihara, Mitsuru*; Segawa, Mariko; Tsuchiya, Harufumi; Maeda, Makoto; Kimura, Atsushi; Nakamura, Shoji

no journal, , 

no abstracts in English

34 (Records 1-20 displayed on this page)