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JAEA Reports

Final report on feasibility study of Pu monitoring and solution measurement of high active liquid waste containing fission product at Reprocessing Facility

Sekine, Megumi; Matsuki, Takuya; Suzuki, Satoshi*; Tsutagi, Koichi; Nishida, Naoki; Kitao, Takahiko; Tomikawa, Hirofumi; Nakamura, Hironobu; LaFleur, A.*; Browne, M.*

JAEA-Technology 2019-023, 160 Pages, 2020/03

JAEA-Technology-2019-023.pdf:9.43MB

The International Atomic Energy Agency (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 a part of an advanced approach to effective and efficient safeguards for reprocessing facilities. To address this, Japan Atomic Energy Agency (JAEA) has been tackling development of a new detector to enable monitoring of Pu in solutions with numerous FPs as a joint research program with U.S. DOE to cover whole reprocessing process. In this study, High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant was used as the test field. At first, the design information of HALW storage tank and radiation (type and intensity) were investigated to develop a Monte Carlo N-Particle Transport Code (MCNP) model. And then, dose rate distribution outside/ inside of the concrete cell where the HALW tank is located was measured to design new detectors and check MCNP model applicability. Using the newly designed detectors, gamma rays and neutron were continuously measured at the outside/ inside of the concrete cell to assess the radiation characteristics and to optimize detector position. Finally, the applicability for Pu monitoring technology was evaluated based on the simulation results and gamma-ray/neutron measurement results. We have found that there is possibility to monitor the change of Pu amount in solution by combination both of gamma-ray and neutron measurement. The results of this study suggested the applicability and capability of the Pu motoring to enhance safeguards for entire reprocessing facility which handles Pu with FP as a feasibility study. This is final report of this project.

Journal Articles

Effective capacity-building development based on good practices from the additional protocol implementation

Rodriguez, P.; Senzaki, Masao; Sekine, Megumi

Proceedings of INMM 60th Annual Meeting (Internet), 9 Pages, 2019/07

The ISCN of the JAEA has been providing assistance, specifically to Asian countries, for the past 8 years, since its establishment in 2010. The ratification of the Protocol Additional (AP) to the safeguards agreement, had involved some changes in the Asian countries resource infrastructures to adhere with the respective States obligations on nuclear non-proliferation. During the 7th FNCA workshop held in Mito, Japan in September 2017, under the Nuclear Security and Safegaurds Project (NSSP), a 3-year plan on the formulation of a generic set of Fundamentals on the Implementation of the Additional Protocol was proposed. To formulate this set of fundamentals, there was a need to prepare a set of Examples of good practices on the implementation of the AP based on the FNCA members experience. The ISCN was tasked to prepare the template and conduct the needed survey among the FNCA members of the project on nuclear security and safeguards. This paper provides a preliminary summary and analysis of the responses received. This paper presents the analysis of the good practices that were implemented in order for the States to satisfy the requirements of the IAEA, as stipulated in the AP. The nuclear fuel cycle characteristics of the involved Asian countries are quite different in several aspects, thus entailing a diverse strategy in resource infrastructure development. This paper describes how every country may have different approaches towards achieving the same objectives. It is worthwhile to look into these various practices, find commonality and share the experience. The objective of formulating a set of fundamentals on AP implementation will be achieved through a compilation and analysis of good practices and shared experiences among its members. The preliminary result on this project was introduced at the 8th FNCA workshop held in Beijing, China in September 2018.

Journal Articles

Feasibility study result of advanced solution measurement and monitoring technology for reprocessing facility

Sekine, Megumi; Matsuki, Takuya; Suzuki, Satoshi*; Tsutagi, Koichi; Tomikawa, Hirofumi; Nakamura, Hironobu; LaFleur, A.*; Browne, M.*

Proceeding 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, $$gamma$$-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 $$gamma$$-ray/neutron measurement results. We have found that there is a possibility to monitor the change of Pu amount in solution by combination of $$gamma$$-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.

Journal Articles

Demonstration of $$gamma$$-ray pipe-monitoring capabilities for real-time process monitoring safeguards applications in reprocessing facilities

Rodriguez, D.; Tanigawa, Masafumi; Nishimura, Kazuaki; Mukai, Yasunobu; Nakamura, Hironobu; Kurita, Tsutomu; Takamine, Jun; Suzuki, Satoshi*; Sekine, Megumi; Rossi, F.; et al.

Journal of Nuclear Science and Technology, 55(7), p.792 - 804, 2018/07

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

Nuclear material in reprocessing facilities is safeguarded by random sample verification with additional continuous monitoring applied to solution masses and volume in important tanks to maintain continuity-of-knowledge of process operation. Measuring the unique $$gamma$$ rays of each solution as the material flows through pipes connecting all tanks and process apparatuses could potentially improve process monitoring by verifying the compositions in real time. We tested this $$gamma$$ ray pipe-monitoring method using plutonium-nitrate solution transferred between tanks at the PCDF-TRP. The $$gamma$$ rays were measured using a lanthanum-bromide detector with a list-mode data acquisition system to obtain both time and energy of $$gamma$$-ray. The analysis and results of this measurement demonstrate an ability to determine isotopic composition, process timing, flow rate, and volume of solution flowing through pipes, introducing a viable capability for process monitoring safeguards verification.

Journal Articles

Feasibility study of technology for Pu solution monitoring including FP; Development of gamma spectra detector for high active liquid waste

Sekine, Megumi; Matsuki, Takuya; Tokoro, Hayate; Tsutagi, Koichi; Kitao, Takahiko; Nakamura, Hironobu; Tomikawa, Hirofumi

Proceedings of INMM 59th Annual Meeting (Internet), 10 Pages, 2018/07

In a reprocessing facility, it is necessary to develop a detector which can measure plutonium (Pu) content in the Pu solutions containing fission products (FP) in order to expand the application of Pu monitoring. In order to establish this technology, JAEA has studied a system measure $$gamma$$-rays was utilized since it applicable for Pu monitoring. Ce:GAGG (Ce:Gd$$_{3}$$Al$$_{2}$$Ga$$_{3}$$O$$_{12}$$) scintillator detector can measure a wide energy range in a high-dose environment and has reasonable resolution. $$gamma$$-ray measurements were performed inside of the concrete cell containing the High Active Liquid Waste tank at the Tokai reprocessing plant. In the spectra, the two significant peaks were measured by the GAGG above 800 keV and were considered to be from Eu-154. There $$gamma$$-ray measurements will be combined with previous neutron measurements and both will be compared to MCNP models for future Pu monitoring technology. This presentation will describe the detector selection, the design system, the results of $$gamma$$-ray spectral measurements and the applicability for Pu monitoring. This project has been carried out under the support of the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of the Japanese government.

Journal Articles

Feasibility study of technology for Pu solution monitoring including FP; Design of GAGG detector and gamma spectrum measurement

Sekine, Megumi; Matsuki, Takuya; Tokoro, Hayate; Tsutagi, Koichi; Tomikawa, Hirofumi; Nakamura, Hironobu

Nihon Kaku Busshitsu Kanri Gakkai Dai-38-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2018/04

In a reprocessing facility, it is necessary to develop a detector which is measurable plutonium (Pu) amount in the Pu solution containing the Fission Product (FP) in order to expand the application of Pu monitoring. To investigate $$gamma$$ rays which is applicable for Pu monitoring, Ce:GAGG (Ce: Gd$$_{3}$$Al$$_{2}$$Ga$$_{3}$$O$$_{12}$$) scintillator which can measure a wide range of energy at high dose and has high resolution (Target: High Active Liquid Waste (HALW)) was newly designed and developed in deal with aim for Pu quantitativeness. $$gamma$$ ray measurement was performed to the HALW in the concrete cell using the detector, and it was confirmed that high energy $$gamma$$ rays (9.5 MeV) could be measured and high energy $$gamma$$ rays spectra over 3 MeV without deriving from FP at the first time. In this presentation, detector design, results of $$gamma$$ ray spectra measurement, applicability evaluation to Pu monitoring and the future plan are presented. This project has been carried out under the support of the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of the Japanese government.

Journal Articles

New approach for monitoring of nuclear material in nitric acid solution using $$^{14}$$N(n,$$gamma$$)$$^{15}$$N reaction

Sekine, Megumi; Tomikawa, Hirofumi

Energy Procedia, 131, p.274 - 278, 2017/12

 Times Cited Count:0 Percentile:100

The IAEA has proposed in its long-term R&D plan, development of real-time measurement technology for monitoring and verifying nuclear material movement continuously. At a PULEX reprocessing facility, HNO$$_{3}$$ solution with dissolved spent fuel, such as FPs and nuclear materials, flows in pipes and stores in tanks. In order to detect and deter nuclear material being stolen from the process, measuring the 10.8 MeV $$gamma$$ rays emitted by $$^{14}$$N(n,$$gamma$$)$$^{15}$$N reaction activated by spontaneous neutrons might be useful for continuous monitoring of liquid flow. In general, since high dose $$gamma$$ rays emitted from FPs are dominant below 3 MeV, it is expected that the 10.8 MeV peak would not be affected by the FP peaks. As the first step, some kinds of detectors and measurement configuration were analyzed through MCNP based on 10.8 MeV $$gamma$$ rays activated by neutrons from a $$^{252}$$Cf source.

Journal Articles

Feasibility study of advanced measurement technology for solution monitoring at reprocessing plant; Dose rate measurement for the solution including Pu with FP

Matsuki, Takuya; Yamanaka, Atsushi; Sekine, Megumi; Suzuki, Satoshi*; Yasuda, Takeshi; Tsutagi, Koichi; Tomikawa, Hirofumi; Nakamura, Hironobu; LaFleur, A. M.*; Browne, M. C.*

Proceedings of INMM 58th Annual Meeting (Internet), 8 Pages, 2017/07

The Tokai Reprocessing Plant (TRP) has been developing a new detector from 2015 to 2017 for purpose to monitor Pu amount in High Active Liquid Waste (HALW) containing FP. It can make a contribution to an advanced approach to effectively and efficiently conduct safeguards for reprocessing facilities because it becomes available to monitor and verify nuclear material movement continuously by a new detector, which has proposed by IAEA. For the second step of this project, we conducted dose rate measurement on the guide rail installing in the cell storing the HALW tank and comparison between measured dose rate distribution and calculation result by MCNP simulation in order to investigate the dose rate distribution which is needed for shielding design of a new detector that is used for radiation (neutron/$$gamma$$ spectrum) measurement in the cell and inquest on the monitoring position of the detector for Pu monitoring. In this paper, we report the result of the dose rate measurement in the cell, improvement of the simulation model which is cleared by comparison between measurement result and calculation result and our future plan.

Journal Articles

Feasibility study of advanced technology for Pu with FP solution monitoring; Overview of research plan and modelling for simulation

Sekine, Megumi; Matsuki, Takuya; Suzuki, Satoshi; Tanigawa, Masafumi; Yasuda, Takeshi; Yamanaka, Atsushi; Tsutagi, Koichi; Nakamura, Hironobu; Tomikawa, Hirofumi; LaFleur, A. M.*; et al.

EUR-28795-EN (Internet), p.788 - 796, 2017/00

The IAEA has proposed in its long-term R&D plan, the development of technology to enable real-time flow measurement of nuclear material as a part of an advanced approach to effective and efficient safeguards for reprocessing facilities. To address this, JAEA has designed and developed a neutron coincidence based nondestructive assay system to monitor Pu directly in solutions which is after purification process and contains very little fission products (FPs). A new detector to enable monitoring of Pu in solutions with numerous FPs is being developed as a joint research program with U.S. DOE at the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant. As the first step, the design information of HALW tank was investigated and samples of HALW was taken and analyzed for Pu concentration and isotope composition, density, content of dominant nuclides emitting $$gamma$$ ray or neutron, etc. in order to develop a Monte Carlo N-Particle Transport Code (MCNP) of the HALW tank. In addition, $$gamma$$ ray source spectra simulated by Particle and Heavy Ion Transport code System (PHITS) was developed by extracting peaks from the analysis data with germanium detector. These outputs are used for the fundamental data in the MCNP model which is then used to evaluate the type of detector, shielding design and measurement positions. In order to evaluate available radiations to measure outside the cell wall, continuous $$gamma$$ ray and neutron measurement were carried out and the results were compared to the simulation results. The measurement results showed that there are no FP peaks above 3 MeV. This paper presents an overview of the research plan, characteristics of HALW, development of source term for MCNP, simulation of radiation dose from the HALW tank and radiation measurement results at outside of cell wall.

JAEA Reports

Study of transparency in the field of nuclear nonproliferation conducted at JAEA

Kawakubo, Yoko; Sekine, Megumi; Tomikawa, Hirofumi

JAEA-Review 2016-017, 57 Pages, 2016/10

JAEA-Review-2016-017.pdf:7.73MB

Nuclear transparency is recognized as essential to provide additional assurance and enhance confidence building in the Asia-Pacific as this region has a broad spectrum of nuclear development underway and planned in the future. It is expected that elevated nuclear transparency should also supplement and reinforce International Atomic Energy Agency (IAEA) safeguards. With this recognition, Japan Atomic Energy Agency (JAEA) has committed various studies and activities for enhancing regional transparency mainly with U.S. Department of Energy (DOE) and its national laboratories. The efforts include transparency concept study, development of the remote monitoring system at the Experimental Fast Reactor JOYO, cooperation to Council for Security and Cooperation in Asia Pacific (CSCAP) to develop internet-based transparency tools, establishment of Information Sharing Framework (ISF), and the hosting of a series of workshops. Based on all the achievements of the past efforts, JAEA is now moving from "study phase" toward the "implementation phase" of information sharing for enhancing its nuclear transparency. The ISF website was opened in 2015 as a part of Asia Pacific Safeguards Network (APSN) website for JAEA to provide relevant information to APSN members. This report summarizes the past studies and activities performed in JAEA for almost 20 years to enhance regional nuclear transparency and discusses the future prospect.

Journal Articles

Feasibility study of technology for Pu solution monitoring including FP; Composition research of high active liquid waste and radiation measurement results on the surface of cell

Matsuki, Takuya; Masui, Kenji; Sekine, Megumi; Tanigawa, Masafumi; Yasuda, Takeshi; Tsutagi, Koichi; Ishiyama, Koichi; Nishida, Naoki; Horigome, Kazushi; Mukai, Yasunobu; et al.

Proceedings of INMM 57th Annual Meeting (Internet), 9 Pages, 2016/07

The International Atomic Energy Agency (IAEA) has proposed in its long-term research and development (R&D) plan, development of a real-time measurement technology to monitor and verify nuclear material movement continuously as part of an advanced approach to effectively and efficiently conduct safeguards for reprocessing facilities. Since the Tokai Reprocessing Plant (TRP) has solutions containing both Pu and fission products (FP), a new detector development project to monitor Pu with FP is being carried out from 2015 to 2017. This project is mainly conducted in the High Active Liquid Waste Storage (HALWS) in the TRP. For the first step of this project, as the confirmation of composition of high active liquid waste (HALW) to evaluate neutron/$$gamma$$-ray emitted from solution in the selected HALW tank which has the most amount of Pu in HALW tanks at the TRP, we took HALW sample and conducted $$gamma$$-ray spectrum measurement for HALW. As a study of detector setting location, to survey the available neutron/$$gamma$$-ray (i.e. intensity) at the outside surface of the cell where HALW tank is located, we implemented continuous measurement by neutron/$$gamma$$-ray detector. In this paper, we report three $$gamma$$-ray peaks related with $$^{238}$$Pu and $$^{239}$$Pu measured in the composition research of HALW, which is needed to identify Pu amount by the new detector that we are developing and the result of radiation measurement on the surface of the cell.

Journal Articles

Feasibility study of technology for Pu solution monitoring including FP; Overview and research plan

Sekine, Megumi; Matsuki, Takuya; Tanigawa, Masafumi; Tsutagi, Koichi; Mukai, Yasunobu; Shimizu, Yasuyuki; Nakamura, Hironobu; Tomikawa, Hirofumi

Proceedings of INMM 57th Annual Meeting (Internet), 9 Pages, 2016/07

The International Atomic Energy Agency (IAEA) has proposed in its long-term research and development plan, development of a real-time measurement technology to monitor and verify nuclear material movement continuously as part of an advanced approach to effectively and efficiently conduct safeguards for reprocessing facilities. In the reprocessing plant, since solutions containing both Pu and FP exist, a new detector development project to monitor Pu with FP is being carried out from 2015 to 2017. This project is mainly conducted in the High Active Liquid Waste Storage (HALWS) in Tokai Reprocessing Plant (TRP). In this paper, an overview of the technology development, simulation results of preliminary evaluation of the characteristics of radiation emitted from the HALW tank at TRP, and the future research plan are presented.

Journal Articles

Development of active neutron NDA techniques for nuclear nonproliferation and nuclear security, 7; Measurement of DG from MOX and Pu liquid samples for quantification and monitoring

Mukai, Yasunobu; Ogawa, Tsuyoshi; Nakamura, Hironobu; Kurita, Tsutomu; Sekine, Megumi; Rodriguez, D.; Takamine, Jun; Koizumi, Mitsuo; Seya, Michio

Proceedings of INMM 57th Annual Meeting (Internet), 7 Pages, 2016/07

The development of Delayed Gamma-ray Spectroscopy (DGS) for analyzing the composition ratio of fissile nuclides ($$^{239}$$Pu, $$^{241}$$Pu, $$^{235}$$U) focused on the Delayed Gamma-ray having energy over 3 MeV has been performed for the development of active neutron non-destructive assay techniques. In PCDF, measurement tests of Delayed Gamma-ray using Pu solution and MOX powder samples to prove the DGS technique is planned to be performed in following 4 stages. (1) Measurements for Delayed Gamma-ray originated from spontaneous fission nuclide (Passive), (2) Measurements for the Delayed Gamma-ray with fast neutron (Active), (3) DGSI (DGS combined with self-interrogation) measurements (Passive), (4) Measurements for the Delayed Gamma-ray with thermal neutron (Active) In this paper, the plan of measurement tests for nuclear material samples with use of DGS is presented.

Oral presentation

Feasibility study of Pu monitoring technology for Pu solution with FP; Overview and research plan

Sekine, Megumi; Ishiyama, Koichi; Nakamura, Hironobu; Tomikawa, Hirofumi

no journal, , 

Plutonium (Pu) solution and solid waste containing fission products (FP) are stored in a reprocessing plant as inventory or retained waste. It is difficult to access the Pu with FP since it has an extremely high radiation dose rate, and there is no direct Pu continuous monitoring/verification technology. From a viewpoint of ensuring nuclear transparency, Japan Atomic Energy Agency (JAEA) has started to develop a new technology using non-destructive assay to measure and monitor Pu solution with FP since JFY 2015. The technology could be applicable to Pu concentration monitoring throughout the reprocessing process. In the poster presentation, an overview of the technology development, simulation results of preliminary evaluation of the characteristics of radiation emitted from the high level radioactive liquid waste tank at Tokai Reprocessing Plant, where the test field is located, and the future research plan are presented.

Oral presentation

Feasibility study of Pu monitoring technology for Pu solution with FP; Optimization of $$gamma$$ rays measurement at the inside of the concrete cell

Suzuki, Satoshi; Sekine, Megumi; Matsuki, Takuya; Yamanaka, Atsushi; Nakamura, Hironobu; Tomikawa, Hirofumi

no journal, , 

From a viewpoint of effective and efficient safeguards, JAEA has started to develop a new technology using non-destructive assay to measure and monitor Pu solution with fission products stored at reprocessing facility since JFY 2015. In JFY 2016, we are planning to measure $$gamma$$ rays and neutron emitted from high radioactive liquid waste (HALW) tank at the inside of the concrete cell and consider whether it has a relationship with Pu amount. In this poster presentation, the detector selection to measure high dose rate at the inside of the concrete cell, optimization of detector system by shielding material and measurement place to prevent high dead time, and the thruster optimization to insert using penetration pipe through the 1.7 m thickness concrete wall are presented as an evaluation of radiation from HALW at Tokai Reprocessing Facility. This project has been carried out under the support of the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of the Japanese government.

Oral presentation

Feasibility study of Pu monitoring technology for Pu solution with FP; Evaluation of $$gamma$$ rays spectrum by simulation at the concrete cell

Sekine, Megumi; Matsuki, Takuya; Yamanaka, Atsushi; Nakamura, Hironobu; Tomikawa, Hirofumi

no journal, , 

Plutonium (Pu) solution and solid waste containing fission products (FP) are stored in a reprocessing plant as inventory or retained waste. It is difficult to access the Pu solution with FP since it has an extremely high radiation dose rate, and there is no direct Pu solution continuous monitoring /verification technology. From a viewpoint of ensuring nuclear transparency, Japan Atomic Energy Agency (JAEA) has started to develop a new technology using non-destructive assay to measure and monitor Pu solution with FP since JFY 2015. In this poster presentation, model of storage tank/concrete cell for high radioactive liquid waste (HALW), and evaluation of $$gamma$$ ray spectra and the distribution of radiation dose rate based on actual HALW analysis results are presented. This project has been carried out under the support of the Ministry of Education, Culture, Sports, Science and Technology (MEXT) of the Japanese government.

Oral presentation

Feasibility study of technology for Pu solution monitoring including FP, 4; Comparison between dose rate measurement result and simulation result

Matsuki, Takuya; Nishida, Naoki; Horigome, Kazushi; Sekine, Megumi; Kitao, Takahiko; Nakamura, Hironobu

no journal, , 

To inquest the measurement point of the detector which can conduct the Pu monitoring in the high active liquid waste at Tokai reprocessing plant, we have made the simulation model which can calculate the radiation distribution in the cell storing HALW. Comparing the dose rate distribution between calculation result and actual measurement result, we evaluated the validity of the current simulation model.

Oral presentation

Feasibility study of technology for Pu solution monitoring including FP, 2; Dose rate distribution measurement test inside the cell storing HAW tank

Tokoro, Hayate; Suzuki, Satoshi*; Miyoshi, Ryuta; Sakurai, Yasuhiro; Matsuki, Takuya; Tsutagi, Koichi; Sekine, Megumi; Shimizu, Yasuyuki; Nakamura, Hironobu

no journal, , 

We inserted a newly designed and manufactured thruster into the guide tube of the high active liquid waste storage cell for inspection in the Tokai Reprocessing Plant and measured the dose rate inside the cell. The dose rate distribution measurements using thruster is an unprecedented experiment, we checked job safety, operability of an equipment and relationship between insert distance of dosimeter and measurement position by using isometric scale mock-up equipment in advance. As a result, we implemented dose rate distribution measurement test inside the cell.

Oral presentation

Feasibility study of technology for Pu solution monitoring including FP, 1; Overview

Sekine, Megumi; Suzuki, Satoshi*; Matsuki, Takuya; Tsutagi, Koichi; Tanigawa, Masafumi; Ishiyama, Koichi; Nakamura, Hironobu; Tomikawa, Hirofumi

no journal, , 

JAEA is being conducted feasibility study of technology for Pu solution monitoring including fission products (FPs) as a joint research program with U.S. DOE at the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant to address effective and efficient safeguards for reprocessing facilities. As the first step, the design information of HALW tank was investigated and measurement test at the out of the concrete cell was conducted in order to confirm whether qualitative evaluation is possible by a simple method. As the second step, gamma dose rate was measured at the inside of the concrete cell which is necessary to optimize the MCNP model for the design and location of the detector at the inside of the concrete cell. As the third step, measureable radiations were investigated at the inside of the concrete cell by the detector which is designed and fabricated based on these outputs. As the final step measurement and simulation results will be evaluated for Feasibility study of the technology for Pu monitoring. This time, an overview and radiation measurement results at outside of cell wall will be reported.

Oral presentation

Feasibility study of technology for Pu solution monitoring including FP, 3; Result of $$gamma$$-ray dose rate measurement inside the cell

Sekine, Megumi; Suzuki, Satoshi*; Tokoro, Hayate; Sakurai, Yasuhiro; Miyoshi, Ryuta; Matsuki, Takuya; Yasuda, Takeshi; Tsutagi, Koichi; Nakamura, Hironobu; Tomikawa, Hirofumi

no journal, , 

JAEA is being conducted feasibility study of technology for Pu solution monitoring including fission products (FPs) as a joint research program with U.S. DOE at the High Active Liquid Waste (HALW) Storage Facility in Tokai Reprocessing Plant to address effective and efficient safeguards for reprocessing facilities. This time, calibration for Ion chamber, measurement results of $$gamma$$ ray dose rate with Ion chamber and applicability to monitoring technology will be reported.

Oral presentation

Measurement technology and development results for material accountancy in the reprocessing facility

Tanigawa, Masafumi; Matsuki, Takuya; Yasuda, Takeshi; Tsutagi, Koichi; Samoto, Hirotaka; Sekine, Megumi; Suzuki, Satoshi*; Kitao, Takahiko; Nakamura, Hironobu; Isomae, Hidemi

no journal, , 

no abstracts in English

21 (Records 1-20 displayed on this page)