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Journal Articles

Promotion for establishing and maintaining appropriate responses in the safeguards activities, 2; Case study activities

Shirafuji, Masaya; Hasegawa, Rie; Akutsu, Narumi*; Maruyama, Hajime; Miyaji, Noriko

Dai-44-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2023/11

To maintain transparency in the use of nuclear materials in Japan, it is important for operators to appropriately respond to safeguards activities conducted by the IAEA/Japan. Failure to appropriately respond to these activities could have significant impacts, such as raising suspicion from the international community about the misuse of nuclear materials by not only the operators but also Japan. To appropriately respond to safeguards activities, JAEA has conducted some activities such as education on safeguards for all employees and case study activities for the employees engaged in responding to safeguards activities. This paper focused on case study activities that started in FY2022. In FY2022, we created documents based on scenarios with problems in safeguards responses in order to promote understanding among participants. We also conducted a questionnaire survey for participants, and we evaluated the result of the questionnaire. The evaluation results showed that the case study activities contributed to raising awareness of safeguards responses, although there were improvements. After making improvements, we are conducting these activities again in FY2023. Since case study activities are expected to be effective if carried out continuously, we plan to continue them in combination with other activities.

Journal Articles

Physical protection corrective action program activities in JAEA

Shibata, Ryodai; Amano, Tsukasa; Yamada, Hiroyuki; Miyaji, Noriko; Nakamura, Hironobu

Dai-44-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2023/11

In April 2020, JAEA has been introduced Physical Protection Corrective Action Program (PPCAP) with full-scale. It was needed to introduce unified operation for six sites with different business scales, and headquarters developed the common guideline. There was an impression that physical protection activities were carried out by a limited number of employees. Therefore, a problem was to root and activate PPCAP activities among all employees in order to make them effective. Five activities were implemented to solve this problem. As a result, more than 3,700 condition reports (CR) have been collected for 4 years. This paper reports on the activities related to the PPCAP that have been implemented at JAEA.

Journal Articles

Efforts for appropriate responses to safeguards activities, 1; Overview

Aoki, Rie; Shirafuji, Masaya; Nozaki, Teo; Akutsu, Narumi*; Miyaji, Noriko; Nakamura, Hironobu

Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 7 Pages, 2023/05

Journal Articles

Promotion for establishing and maintaining appropriate responses in the safeguards activities

Shirafuji, Masaya; Nozaki, Teo; Akutsu, Narumi*; Miyaji, Noriko; Nakamura, Hironobu

Dai-43-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2022/11

In order to maintain transparency in the peaceful use of nuclear materials in Japan, it is important to appropriately respond to safeguards activities conducted by the IAEA/Japan. Failure to respond appropriately to these activities could have significant impacts, such as raising suspicion from the international community about the misuse of nuclear materials by not only the operators but also by Japan. In order to strengthen activities to appropriately respond to safeguards activities, JAEA has started (I) education on safeguards for all employees directly employed by JAEA, (II) lectures, (III) case studies, and (IV) standardization of procedures related to safeguards response since FY2020, following the methods used to foster nuclear security culture in the past. This report describes these specific activities.

Journal Articles

Efforts of procurement and quality managements for physical protection system in JAEA

Shibata, Ryodai; Yamazaki, Katsuyuki; Yamada, Hiroyuki; Miyaji, Noriko; Nakamura, Hironobu

Dai-42-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2021/11

Physical protection systems (PPS) operated for security in nuclear facilities uses computer-controlled systems. If malicious peoples change program or install computer virus to PPS, they are invalidated. Due to insufficient surveillance etc., and then unauthorized removal and sabotage may be caused. This paper introduces efforts of necessary procurement and quality managements etc., for decreasing there affect, and their details.

Journal Articles

APSN surveys for the coordination of training efforts in Asia; Results and challenges

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

Journal Articles

Addressing training needs of security and safeguards implementation officers at nuclear facilities

Vidaurre, J.; Noro, Naoko; Matsuzawa, Reina; Miyaji, Noriko

Proceedings of INMM 56th Annual Meeting (Internet), 10 Pages, 2015/07

Officers at nuclear facilities have substantial responsibilities in the management of nuclear materials: They have to assure that nuclear material is properly controlled and accounted for; they need to detect and deter unauthorized access and removal of nuclear material and protect it from an insider or an outsider threat. At the same time, they need to comply with their State's commitments on nuclear nonproliferation that uses nuclear material accountancy as a fundamental verification measure. To perform such a variety of tasks, facility officers responsible for safeguards and security require a set of Skills, Knowledge and Attitudes commensurate with their responsibilities and tasks. To address this needs, the IAEA and its Member States have conducted a series of training courses, the vast majority of which were targeted to regulatory authorities on safeguards or nuclear material accountancy topics. There are few courses dedicated to facility officers or operators addressing holistically their security and safeguards requirements. This paper analyses the evolution of training courses for authorities and facility personnel in a changing environment from nuclear nonproliferation focused-era to the current broader approach encompassing safeguards and security. Then it recalls some conceptual developments of the recent past and attempts to justify a change in direction on the focus of Member State's training. Finally, it brings some specific proposals towards strengthening and increasing security and safeguards training in Nuclear Material Accountancy and Control relevant to the tasks and responsibilities of safeguards and security practitioners at the facility level.

Journal Articles

The Impact of advanced technologies on the efficiencies of safeguards and facility operations

Hoffheins, B.; Miyaji, Noriko; Asano, Takashi; Nagatani, Taketeru; Ishiyama, Koichi; Kimura, Takashi; Kodani, Yoshiki

Proceedings of INMM 52nd Annual Meeting (CD-ROM), 10 Pages, 2011/07

Following Japan's conclusion of the Additional Protocol and the IAEA's broader conclusion regarding the peaceful nature of Japan's nuclear activities, the Japan government and facility operators have worked with the IAEA to apply integrated safeguards to increase inspection efficiency and to ensure verification correctness and completeness. These safeguards approaches rely heavily on the implementation of advanced technologies such as unattended surveillance and non-destructive assay measurement, automated nuclear material accounting, solution monitoring and remote monitoring. These technologies have enabled random interim inspections; they have also reduced the level of effort required for nuclear material accounting and inspection activities. A more comprehensive understanding of the impact of advanced technologies on operation and inspection processes would be useful for developing methodologies to support better system design and evaluation of existing systems.

Journal Articles

Integrated safeguards approach for large-scale hot cell laboratory

Miyaji, Noriko; Katsumura, Soichiro; Kawakami, Yukio

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 7 Pages, 2010/12

A large-scale hot cell laboratory named FMF is located by the experimental fast reactor Joyo in Oarai Research and Development Center (JNC-2 site), Japan Atomic Energy Agency (JAEA). FMF conducts post irradiation examinations (PIE) of irradiated fuels in Joyo such as assemblies and pins. To the JNC-2 site, in the Integrated Safeguards (IS) approach, which treats FMF and Joyo as one sector, was applied in December, 2010. For this, a new verification system for the material transfer between Joyo and FMF has been developed. The system includes the followings: (1) surveillance system remotely monitoring movements of a declared transport cask, (2) random verifications for the nuclear material contained in the cask by measuring the neutron dose rate. The implementation of the IS incorporating the developed verification system to the JNC-2 site would strengthen effectiveness and efficiency of safeguards.

Journal Articles

Experience of integrated safeguards approach for large-scale hot cell laboratory

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.

Journal Articles

Development of an eddy current testing technique for inspecting inner corrosion of cladding

Miyaji, Noriko; Katsuyama, Kozo; Nagamine, Tsuyoshi

Proceedings of 46th Annual Meeting of "Hot Laboratories and Remote Handling" Working Group (HOTLAB 2009) (CD-ROM), 5 Pages, 2009/09

An eddy current testing (ECT) technique was developed to check the soundness of irradiated fuel pins non-destructively. Here, the technique was applied to detect the decrease in wall thickness of the fuel pin cladding due to corrosion occurrence which had been irradiated in the experimental fast reactor Joyo. Dummy cladding provided with simulated inner corrosion was used to ascertain the technique applicability. This test confirmed that the decrease in wall thickness with simulated inner corrosion exceeding 30 $$mu$$m in depth could be detected. In the case of irradiated fuel pins, the decrease in wall thickness due to corrosion occurrence was not detected because the depth was too small; the maximum depth of the inner corrosion was 14 $$mu$$m. In addition, it should be noted that the physical changes on the cladding due to irradiation might have an influence on the signal.

JAEA Reports

Development of eddy current testing technique for irradiated fuel pins, 2; ECT results of irradiated fuel pins of high burn up

Miyaji, Noriko; Nagamine, Tsuyoshi; Katsuyama, Kozo

JAEA-Technology 2006-036, 41 Pages, 2006/06

JAEA-Technology-2006-036.pdf:3.91MB

Eddy current testing (ECT) technique has been developed in order to check the soundness of irradiated fuel pins non-destructively. This paper describes the results that it was examined if corrosions were detected using an imitation fuel pin, made of 15Ni-15Cr-Ti and same type of the fuel pins irradiated in JOYO. As the results of experimental for an imitation pin, ECT detected the corrosions using frecquency 32kHz. And, the signal of eddy current became larger as the thickness of the cladding became smaller, because there was some correlation between the signal and thickness. As for the irradiated fuel pins, inner corrosions were not recognized from the signal because their sizes were too small. However, outside corrosions by sodium as coolant might have an influence on the signal. And, as well as a change of the electromagnetic characteristics of cladding by irradiation, inner pressure by FP gas and PCMI might have an influence on the signal.

JAEA Reports

Development of Eddy Current Testing Technique for Irradiated Fuel Pins; ECT results of irradiated fuel pins of PFC030

Miyaji, Noriko; Nagamine, Tsuyoshi; Katsuyama, Kozo; Kikuchi, Shin; Matsumoto, Shinichiro

JNC TN9410 2003-012, 45 Pages, 2004/03

JNC-TN9410-2003-012.pdf:1.84MB

Post irraiated fuel pins which irradiated in JOYO PFC030 by eddy current test (ECT) were carried out. The results of the tests, we have some possibility to find FCCI points using gamma scanning result Cs137. And thecorrelation between FCCI quantity and eddy current signal was within that of trial FCCI.

Oral presentation

Development of eddy current testing technique for fast reactor fuel pins; ECT results of irradiated fuel pins

Miyaji, Noriko; Katsuyama, Kozo; Nagamine, Tsuyoshi; Nakamura, Yasuo; Otani, Akira*

no journal, , 

no abstracts in English

Oral presentation

Focusing NMA&C training on the precise group of practitioners

Vidaurre, J.; Miyaji, Noriko; Hirai, Mizuki

no journal, , 

The purpose of this paper is to quantify the training effort deployed by the IAEA and several countries with advanced power and nuclear fuel cycle facilities to the different segments of safeguards and security practitioners in charge of implementing safeguards and security measures in the field and to judge if this effort is commensurate with the actual requirements and needs. The paper focuses on Nuclear Material Accountancy and Control (NMA&C), as this is one of the most important disciplines encompassing both safeguards and security.

Oral presentation

Characterization study of candidate technologies for nuclear material quantification in fuel debris at Fukushima Daiichi Nuclear Power Station, 2-1; General outline

Nagatani, Taketeru; Komeda, Masao; Shiba, Tomooki; Nauchi, Yasushi*; Sagara, Hiroshi*; Kosuge, Yoshihiro*; Miyaji, Noriko; Okumura, Keisuke

no journal, , 

no abstracts in English

Oral presentation

Study on nuclear material management for fuel debris

Miyaji, Noriko; Takada, Akira*; Iwafuchi, Junichi; Tomikawa, Hirofumi; Shiba, Tomooki; Okumura, Keisuke; Nagatani, Taketeru; Nauchi, Yasushi*

no journal, , 

Nuclear materials in fuel debris need to be properly managed in order to assure to the international and national communities that no nuclear materials have been diverted. In order to provide this assurance, specific measures appropriate to the characteristics of the fuel debris are required. There is experience at managing fuel debris in similar situations, as it was the case of the partial meltdown at the TMI-2 in the US. The nuclear material in the fuel debris retrieved from the reactor was quantified in order to fulfill domestic law requirements in the US. NDA, DA, and visual observation were applied to the residual fuel in the reactor. On that specific accident, IAEA safeguards were not applied because the USA is a nuclear weapon state and therefore this power plant was not inspected by the IAEA. Nuclear material accounting (NMA)is an important measure to manage nuclear materials for states under IAEA safeguards. In this presentation a report on NMA as a measure to manage fuel debris will be discussed.

Oral presentation

Safeguards guidelines for post-accident facilities and associated waste management facilities

Nakamura, Hironobu; Takeda, Seiichi; Shimizu, Yasuyuki; Takeda, Hideyuki; Aoki, Rie; Shirafuji, Masaya; Kitao, Takahiko; Miyaji, Noriko

no journal, , 

In the consultancy meeting "Safeguards Guidelines for post-accident facilities and associated waste management facilities" held in IAEA, decommissioning activities, and the relevant safeguards activities in TRP/PCDF are reported. In general, the facility after accident with access limitation, operator decides to conduct decommissioning. Therefore, our report regarding the decommissioning plan and the relevant safeguards activities are very helpful to be considered. The nuclear material remove and waste management (storage/treatment) are essential work in the normal accessible facility as well as post-accident facility. Otherwise, in the case of post accident facility, alternative safeguards measures is required according to the access situation because normal safeguards activities might not be taken appropriately. In this report, we would present that outline of decommissioning plan in the TRP/PCDF and the relevant safeguards and nuclear material accountancy.

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