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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
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.
Miyaji, Noriko; Vidaurre, J.; Hori, Masato; Rodriguez, P.; Robertson, K.*
Proceedings of IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 5 Pages, 2018/11
Rodriguez, D.; Tanigawa, Masafumi; Seya, Michio; Nakamura, Hironobu
Proceedings of IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 6 Pages, 2018/11
Sekine, Megumi; Matsuki, Takuya; Suzuki, Satoshi*; Tsutagi, Koichi; Tomikawa, Hirofumi; Nakamura, Hironobu; LaFleur, A.*; Browne, M.*
Proceedings of IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 8 Pages, 2018/11
The IAEA has proposed, in its Research and Development plan (STR-385), the development of technology to enable real-time flow measurement of nuclear material as part of an advanced approach to effective and efficient safeguards for reprocessing facilities. To address this, JAEA and JNFL had previously designed and developed a neutron coincidence based non-destructive assay system to monitor Pu in solution directly after a purification process. To enhance this technology for entire reprocessing facilities, as a feasibility study, JAEA has been tackling development of a new detector to enable monitoring of Pu in solutions with numerous fission products (FPs) as a joint research program with the U.S. DOE. In this study, the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant (TRP) was used as the test bed. The design information of the HALW storage tank and radiation (type and intensity) were investigated, to develop a Monte Carlo N-Particle Transport Code (MCNP) model. Then, dose rate distribution inside the concrete cell where the HALW tank is located was measured, to enable design of new detectors and check the integrity of the MCNP model and its applicability. Using the newly-designed detectors, 
-rays and neutrons could be measured continuously at the outside/inside of the concrete cell, to optimize detector position and the radiation characteristics. The applicability as a Pu-monitoring technology was evaluated, based on the simulation results and -ray/neutron measurement results. We have found that there is a possibility to monitor the change of Pu amount in solution by combination of -ray and neutron measurements. The results of this study suggest a feasibility study into the applicability and capability of Pu monitoring to enhance the entire reprocessing facility handling Pu with FPs. In this paper, a summary of the project will be presented.
Shiba, Tomooki; Tomikawa, Hirofumi; Hori, Masato
Proceedings of IAEA Symposium on International Safeguards; Building Future Safeguards Capabilities (Internet), 6 Pages, 2018/11
Nagatani, Taketeru; Nakajima, Shinji; Kawakubo, Yoko; Shiromo, Hideo; Asano, Takashi; Marlow, J.*; Swinhoe, M. T.*; Menlove, H.*; Rael, C.*; Kawasue, Akane*; et al.
Book of Abstracts, Presentations and Papers of Symposium on International Safeguards; Linking Strategy, Implementation and People (Internet), 8 Pages, 2015/03
Senzaki, Masao; Naoi, Yosuke; Kuribayashi, Toshihiro; Okumura, Yukiko
Book of Abstracts, Presentations and Papers of Symposium on International Safeguards; Linking Strategy, Implementation and People (Internet), 8 Pages, 2015/03
JAEA has supported to HRD of mainly Asian countries in the field of SGs and SSAC, and works closely with governmental organizations in Japan, and with the IAEA, the US DOE, EC, the flame work of FNCA, APSN. This paper presents the efforts, contributions and future challenges of JAEA to HRD regarding SGs and SSAC, through international cooperation, which have been taking place for around 20 years.
Seya, Michio; Kobayashi, Naoki; Naoi, Yosuke; Hajima, Ryoichi; Soyama, Kazuhiko; Kureta, Masatoshi; Nakamura, Hironobu; Harada, Hideo
Book of Abstracts, Presentations and Papers of Symposium on International Safeguards; Linking Strategy, Implementation and People (Internet), 8 Pages, 2015/03
JAEA-ISCN has been implementing basic development programs of the advanced NDA technologies for nuclear material (NM) since 2011JFY (Japanese Fiscal Year), which are (1) NRF (Nuclear resonance fluorescence) NDA technology using laser Compton scattered (LCS) -rays (intense mono-energetic -rays), (2) Alternative to 
He neutron detection technology using ZnS/B
O
ceramic scintillator, and (3) NRD (Neutron resonance densitometry) using NRTA (Neutron resonance transmission analysis) and NRCA (Neutron resonance capture analysis). These programs are going to be finished in 2014JFY and have demonstration tests in February - March 2015.
Nakamura, Hironobu; Mukai, Yasunobu; Kurita, Tsutomu
Book of Abstracts, Presentations and Papers of Symposium on International Safeguards; Linking Strategy, Implementation and People (Internet), 8 Pages, 2015/03
The Distributed Source-Term Analysis (DSTA) technique has been used in a variety of safeguards applications to determine location and quantity of material contained within large sample volumes. By applying this method, JAEA developed and applied two different neutron measurement techniques in order to improve own MC&A. The first advanced technique is a Glove Box Cleanout Assistance Tool (BCAT). It is used by operator during cleanout just before PIT to increase recovered material, to decrease unmeasured inventory, and to perform the cleanout activity effectively. The BCAT is being introduced to the actual cleanout since 2011. The second advanced technique is a dynamic cross-talk correction (DCTC) method. The DCTC can obtain actual doubles signal cross-talk between multiple gloveboxes. In order to assay Pu amount in the holdup correctly, we implemented an improved HBAS system using DCTC. Two advanced holdup measurement technologies provide appropriate safety and safeguards environment to conduct nuclear cycle with operator and inspector.
Nakamura, Hironobu; Beddingfield, D. H.*; Nakamichi, Hideo; Mukai, Yasunobu; Yoshimoto, Katsunobu
IAEA-CN-184/59 (Internet), 7 Pages, 2010/11
In order to reduce radioactivity of liquid waste generated at PCDF, a neutralization precipitation processes by sodium hydroxide precipitation is used. We call the precipitate after calcining as Sludge. The Pu amount in the sludge sample is normally determined by sampling and DA. The sludge contains many chemical components. For example, Pu, U, Am, SUS components, halogens, NaNO (main component), residual NaOH, and moisture. They are mixed together as an impure heterogeneous sludge sample. As a result, there is a large uncertainty in the sampling and DA that is currently used at PCDF. In order to improve the material accounting in PCDF, we performed a feasibility study using neutron multiplicity assay for impure sludge samples. We have measured selected sludge samples using a commercial multiplicity counter which is called FCAS (Fast Carton Assay System) which was designed by JAEA and Canberra. For unknown samples, using 14-hour measurements, we could obtain quite low statistical uncertainty on Doublesand Triples count rate although the alpha value is extremely high and FCAS efficiency is relatively low for typical multiplicity counters. Despite the detector efficiency challenges and the material challenges, we have been able to obtain assay results that greatly exceed the accountancy requirements for retained waste materials.
Miyaji, Noriko; Kawakami, Yukio; Koizumi, Atsuhiro; Otsuji, Ayako*; Sasaki, Keiichi*
IAEA-CN-184/60 (Internet), 6 Pages, 2010/11
FMF at Oarai Research and Development Center (JNC-2 site) conducts post irradiation examinations (PIE) of fuel assemblies irradiated in Joyo. After the PIEs, the tested material is shipped back to a Joyo spent fuel pond. For the IAEA to apply the integrated safeguards approach (ISA) to the FMF, a new verification system on material transfer between Joyo and the FMF has been established. Gross defect verification of the nuclear material contained in the cask is performed at the time of short notice random interim inspections (RIIs) by measuring the surface neutron dose rate of the cask, filled with water to reduce radiation. As the result of performing a series of preliminary tests, this system could be used for the verification purpose under the ISA. It is clear that application of the system under the ISA provides the transparency of the material shipping and receiving process would be improved.
Suzuki, Mitsutoshi; Izumi, Yoshinori; Kimoto, Toru; Naoi, Yosuke; Inoue, Takeshi; Hoffheins, B.
IAEA-CN-184/64 (Internet), 8 Pages, 2010/11
In support of the 3S initiative, Japan Atomic Energy Agency (JAEA) has been conducting detailed analyses of the R&D programs and cultures of each of the S areas to identify overlaps where synergism and efficiencies might be realized, to determine where there are gaps in the development of a mature 3S culture, and to coordinate efforts with other Japanese and international organizations. Lessons learned in these activities can be applied to developing more efficient and effective 3S infrastructures for incorporating into Safeguards by Design methodologies. In this presentation, a risk-informed approach regarding integration of 3S will be introduced. An initial examination of incident probability and postulated consequence analyses, which are tools familiar to the nuclear safety culture, will be applied to predict and evaluate inherent uncertainties of proliferation and security risks.
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.
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
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
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 
U and 
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.
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.
; ; Hosoma, Takashi
Proceedings, 0 Pages, 2002/00
None
Adachi, Takeo; Usuda, Shigekazu; Watanabe, Kazuo; Sakurai, Satoshi; Magara, Masaaki; Hanzawa, Yukiko; Esaka, Fumitaka; Yasuda, Kenichiro; Saito, Yoko; Takahashi, Masato; et al.
IAEA-SM-367/10/02 (CD-ROM), 8 Pages, 2001/00
no abstracts in English
; ; Hosoma, Takashi
P292, 292 Pages, 2001/00
None
