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Journal Articles

Development of safeguards environmental sample analysis techniques at JAEA as a network laboratory of IAEA

Sakurai, Satoshi; Magara, Masaaki; Esaka, Fumitaka; Hirayama, Fumio; Lee, C. G.; Yasuda, Kenichiro; Inagawa, Jun; Suzuki, Daisuke; Iguchi, Kazunari; Kokubu, Yoko; et al.

STI/PUB/1298 (CD-ROM), p.791 - 799, 2007/08

no abstracts in English

Journal Articles

Safeguards improvement for the Tokai Reprocessing Plant (TRP)

Onizawa, Toshikazu; Kimura, Takashi; Kurosu, Kazutoshi; Hayakawa, Tsuyoshi; Fukuhara, Junichi; Yatsu, Shoichi*

STI/PUB/1298 (CD-ROM), p.739 - 745, 2007/08

no abstracts in English

Journal Articles

Particle-chemical analysis of uranium and plutonium

Shinonaga, Taeko*; Donohue, D.*; Klose, D.*; Kuno, Takehiko*; Kuno, Yusuke*; Esaka, Fumitaka; Esaka, Konomi; Magara, Masaaki; Sakurai, Satoshi; Usuda, Shigekazu

STI/PUB/1298 (CD-ROM), p.525 - 531, 2007/08

More precise, accurate and prompt analyses of uranium and plutonium in various types of environmental samples are increasingly requested from the Clean Laboratory Unit, Safeguards Analytical Laboratory of IAEA in recent years. Particles show unique information and up to now, the secondary ion mass spectrometry (SIMS) has been employed for the uranium and plutonium particle analysis. The SIMS that is the most rapid method for particle analysis has, however, disadvantages for the analysis of the minor isotopes like $$^{234}$$U and $$^{236}$$U, i.e., not precise enough. The SIMS measurement also has a difficulty on Pu determination because of the interference of U-based isobaric signals. In this study, a combination of techniques, picking-up particles by a manipulator attached to a scanning electron microscope (SEM), followed by uranium and plutonium chemical purification and measurement by an inductively coupled plasma mass spectrometer (ICP-MS) and thermal ionization mass spectrometer (TIMS), was demonstrated for particle analysis using standard materials (NBS U500 and NBS 947) to develop a particle-chemical analysis.

Journal Articles

Improvement of analytical activities in the Tokai reprocessing plant, Japan, by measuring destructive and non-destructive assays

Surugaya, Naoki; Taguchi, Shigeo; Kurosawa, Akira; Watahiki, Masaru

STI/PUB/1298 (CD-ROM), p.673 - 679, 2007/08

We have been analyzing nuclear materials at the Tokai pilot reprocessing plant, Japan, since 1977. To obtain reliable measurements for nuclear material such as uranium and plutonium, we have developed various kinds of measurement techniques and implemented effective ones for accountability and verification analyses in a nuclear material accountancy system. One of our role as a pilot plant has been successfully accomplished with the effort put into various analytical activities. Now, it is time to transfer the experience gained with our technology to the next large-scale commercial plant in Rokkasho. This paper presents our analytical methods and their results obtained using analytical techniques we have applied over recent years.

Journal Articles

Reduction of fluctuation and small bias observed in continuous volume monitoring taken in an annular tank for plutonium nitrate

Hosoma, Takashi; Mukai, Yasunobu; Tanaka, Hideki

STI/PUB/1298 (CD-ROM), p.699 - 705, 2007/08

Accurate measurement of density and volume by dip-tubes in an annular tank for plutonium nitrate solution is indispensable for material accountancy and safeguards in a reprocessing and conversion plant. The principle of this method is to measure true hydrostatic pressure at the tip of the tube, which postulates that solution in a tank is motionless during measurement. Such condition is satisfied by short time measurement for material accountancy. However, solution is normally being agitated continuously for safety reasons. Therefore, the solution flows and causes some fluctuation and possibly some small bias on hydrostatic pressure measurement. Continuous volume monitoring data is very important information for safeguards, but some apparent change in volume is observed due to the above situation. The reason of fluctuation and small bias is estimated that the effect of solution flow on pressure measurement is not compensating between the density tube (several millimeter higher than the bottom) and the level tube (close to the bottom where solution flow is stagnated), thus measured density fluctuates. In principle, measured volume decreases when measured density increases. We focused attention to the solution mass simply calculated by volume multiplied by density measured coincidentally. As a result, fluctuation and small bias is significantly reduced in mass monitoring.

Oral presentation

Recent experiences of analytical activities with DA and NDA measurements in the Tokai reprocessing plant

Surugaya, Naoki; Taguchi, Shigeo; Kurosawa, Akira; Watahiki, Masaru

no journal, , 

The Tokai Reprocessing Plant (TRP) as the first pilot plant in Japan started a series of operational testing for spent fuel reprocessing of light water reactor in 1977. In the meantime with over 30 years, we have developed a lot of measurement techniques to establish a precise and effective accountability analysis as well as a safeguards analysis for use in the national and international verification on nuclear materials. This paper will describe the details based on the recent results in overall activities at the TRP.

Oral presentation

A Demonstration of advanced nuclear fuel cycle transparency concepts

Inoue, Naoko; Irie, Tsutomu; Kitabata, Takuya; Rochau, G.*; York, D.*; Mendez, C.*

no journal, , 

Japan Atomic Energy Agency (JAEA) and Sandia National Laboratories (SNL) have entered cooperative program, in 2005, to demonstrate a methodology capable assessing proliferation risk in support of overall plant transparency. Earlier, both organizations have preliminary discussion to develop the methodology. The Advanced Fuel Cycle Transparency Framework Concept is being implemented at the Fuel Handling Training Model designed for "Monju", prototype Fast Reactor at the International Nuclear Information and Training Center (ITC) of Tsuruga Head Office, the Japan Atomic Energy Agency (JAEA). "Monju" is fully automated facility and the training model reproducts the entire Monju fuel handling process. The training model is used to generate and transmit information to a secure database at ITC located by Monju site. A computer syncronized to the visible movements in the model mimicking process data supply data. The database is accessible to analyst at SNL via encryption and virtual private network (VPN). The data stream is fed into the "Transparency Software" for real time analysis when the model is being exeicised. "Transparency Software" is expected to monitor the information from the model and to calcurate the prolifearation risk by compared with expected values. This concept will be able to expamd the ability to enable effective transparency system in the aspect of safety and lagitmate use of nuclear material and technology, to contribute the transparency concept among international communities or between a state and IAEA, for the future nuclear fuel cycles. This paper will describe the concept, implememtation plan and status of the demonstration project, and progress toward the first demonstration of the system.

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