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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.
; ; Hosoma, Takashi
P292, 292 Pages, 2001/00
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Yoshida, Mika; ; Kobayashi, Hideo;
PP 71-73, p.71 - 73, 2001/00
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; Sato, Soichi; ; Kuno, Yusuke; Masui, Jinichi
1994 IAEA Symposium on International Safeguards, ,
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; Abe, Katsuo; ; Kuno, Yusuke; Masui, Jinichi
1994 IAEA Symposium on International Safeguards, ,
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