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Journal Articles

20 years of achievement and future challenge for international capacity building regardings safeguards and SSAC at Japan Atomic Energy Agency (JAEA)

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.

Journal Articles

Evaluating methods to improve safeguards training courses of ISCN

Okumura, Yukiko; Nakamura, Yo; Kawata, Norio

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2015/01

Although questionnaires were used to receive feedbacks from participants at the end of each training course, Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of Japan Atomic Energy Agency (JAEA) did not establish a structured evaluation method. To this end, ISCN has started to study on methods to accurately evaluate the courses since April and started to introduce the evaluation method on trial, according to the Donald Kirkpatrick's Four-Level Training Evaluation Model, so as to better develop and conduct more effective courses. This paper will focus on how ISCN has modified the Kirkpatrick's Four-level to adapt to its safeguards training courses. This will then be followed by two particular cases of how the evaluation method functioned for the Additional Protocol training courses held in Malaysia in 2014, and the feedbacks received to improve future training courses.

Journal Articles

Japan Atomic Energy Agency (JAEA)'s international capacity building regarding safeguards and SSAC; 20 years of achievement and future challenges

Senzaki, Masao; Naoi, Yosuke; Kuribayashi, Toshihiro; Hamada, Kazuko; Okumura, Yukiko

Proceedings of INMM 55th Annual Meeting (Internet), 10 Pages, 2014/07

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 U.S. 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.

Journal Articles

Infrastructure development support for safeguard implementation; Focusing on the capacity building of Integrated Support Center for Nuclear Nonproliferation and Nuclear Security

Okumura, Yukiko

Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-34-Kai Nenji Taikai Rombunshu (Internet), 6 Pages, 2013/10

NPT obligates non-nuclear-weapon State Party to it to verify treaty compliance through safeguards and authorizes the IAEA to its implementation. In 1972, the Model Protocol of CSA was adopted. An new legal authority was required, however, when the shortcoming of the safeguards implementation was highlighted in early 1990s in Iraq. So as to confirm the non-existence of the undeclared nuclear material and nuclear activity the AP was adopted by the IAEA Board of Governors in 1997. In order to support international safeguards activities conducted by the IAEA, the ISCN of JAEA has been conducting international cooperation, through seminars and training courses, targeted mainly on Asian countries. We have been supporting the countries to enable the enhancement of ratification and effective implementation. This paper will be focusing on how ISCN is contributing to the Asian countries as well as the IAEA's infrastructure development support for safeguard implementation.

Journal Articles

Isotope dilution inductively coupled plasma mass spectrometry for determination of $$^{126}$$Sn content in spent nuclear fuel sample

Asai, Shiho; Toshimitsu, Masaaki; Hanzawa, Yukiko; Suzuki, Hideya; Shinohara, Nobuo; Inagawa, Jun; Okumura, Keisuke; Hotoku, Shinobu; Kimura, Takaumi; Suzuki, Kensuke*; et al.

Journal of Nuclear Science and Technology, 50(6), p.556 - 562, 2013/06

 Times Cited Count:11 Percentile:64.2(Nuclear Science & Technology)

The $$^{126}$$Sn content in a spent nuclear fuel solution was determined by ICP-MS for its inventory estimation in high-level radioactive waste. An irradiated UO$$_{2}$$ fuel was used as a sample to evaluate the reliability of the methodology. Prior to the measurement, Sn was separated from $$^{126}$$Te, which causes major isobaric interference in the determination of $$^{126}$$Sn content, along with highly radioactive coexisting elements using an anion-exchange column. The absence of counts attributed to Te in the Sn-containing effluent indicates that Te was completely removed. After washing, Sn retained on the column was readily eluted with 1 M HNO$$_{3}$$. The isotope ratios of Sn were successfully determined and showed good agreement with those obtained through ORIGEN2 calculations. The results reported in this paper are the first experimental values of $$^{126}$$Sn content in the spent nuclear fuel solution originating in spent nuclear fuel irradiated at a nuclear power plant in Japan.

Journal Articles

Simple cation-exchange separation for ICP-MS measurement of $$^{79}$$Se in spent nuclear fuel sample

Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Okumura, Keisuke; Shinohara, Nobuo; Kimura, Takaumi; Inagawa, Jun; Suzuki, Kensuke*; Kaneko, Satoru*

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12

Journal Articles

New ORIGEN2 libraries based on JENDL-4.0 and their validation for long-lived fission products by post irradiation examination analyses of LWR spent fuels

Kojima, Kensuke; Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Okamoto, Tsutomu; Toshimitsu, Masaaki; Inagawa, Jun; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of International Conference on Toward and Over the Fukushima Daiichi Accident (GLOBAL 2011) (CD-ROM), 5 Pages, 2011/12

Accurate inventory estimation of long-lived fission products (LLFPs) in LWR spent fuels is important for the quality management and for long-term safety assessment of high-level radioactive vitrified wastes. In Japan, ORIGEN2 has been widely used to estimate the fuel compositions. However, equipped library data in the original ORIGEN2 are old and are not validated enough for LLFPs, such as $$^{79}$$Se, $$^{99}$$Tc, $$^{126}$$Sn and $$^{135}$$Cs, because available post irradiation examination (PIE) data are limited for these nuclides, which have difficulties in radiochemical analyses. For more accurate the estimation, new ORIGEN2 libraries are developed from the latest nuclear data library JENDL-4.0 for cross sections and fission yields, and from other libraries for half-lives, and so on. The new libraries are validated by PIE analyses of the sample fuels irradiated in Cooper, Calvert-Cliffs-1, H. B. Robinson-2, and Ohi-1. As a result, it was found that the new library gives good results for the estimation.

Journal Articles

Analyses of assay data of LWR spent nuclear fuels with a continuous-energy Monte Carlo code MVP and JENDL-4.0 for inventory estimation of $$^{79}$$Se, $$^{99}$$Tc, $$^{126}$$Sn and $$^{135}$$Cs

Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Okamoto, Tsutomu; Shinohara, Nobuo; Kaneko, Satoru*; Suzuki, Kensuke*

Progress in Nuclear Science and Technology (Internet), 2, p.369 - 374, 2011/10

For accurate inventory estimation of long-lived fission products in LWR spent fuels, a new burn-up chain model and decay data based on the latest nuclear data such as JENDL-4.0 was developed. MVP-BURN with the latest nuclear data was applied to several post irradiation examinations including inventory measurements of $$^{79}$$Se, $$^{99}$$Tc, $$^{126}$$Sn and $$^{135}$$Cs. One of them is a new measurement by JAEA. From the PIE analyses, it is found that the new PIE data obtained by JAEA is consistent with the other PIE data by different laboratory with different techniques. It is also confirmed that the present calculation results show good agreements with experimental ones within about 10% for productions of $$^{79}$$Se and $$^{135}$$Cs. In contrast, amounts of $$^{99}$$Tc and $$^{126}$$Sn are overestimated by about 50%. These discrepancies are likely due to the effect of insoluble residue produced during sample dissolution and/or errors of fission yields in the analyses.

Journal Articles

Validation of correlations between Nd isotopes and difficult-to-measure nuclides predicted with burn-up calculation code by post irradiation examination

Asai, Shiho; Okumura, Keisuke; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of 14th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2011) (CD-ROM), p.1437 - 1442, 2011/09

Journal Articles

Computational study for inventory estimation of Se-79, Tc-99, Sn-126, and Cs-135 in high-level radioactive wastes from spent nuclear fuels of light water reactors

Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Okamoto, Tsutomu; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Kimura, Takaumi; Suzuki, Kensuke*; Kaneko, Satoru*

Proceedings of 14th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2011) (CD-ROM), p.1443 - 1450, 2011/09

Inventory estimation of long-lived fission products (LLFPs) in high-level radioactive wastes (HLW) from spent nuclear fuels of light water reactors is important for a safety assessment of their disposal. In order to develop an inventory estimation method of difficult-to-measure LLFPs (Se-79, Tc-99, Sn-126, and Cs-135), a parametric study was carried out by using a sophisticated burnup calculation code and data. In the parametric study, fuel specifications and irradiation conditions are changed in the conceivable range. The considered parameters are fuel assembly types (PWR / BWR), U-235 enrichment, moderator temperature, void fraction, power density, and so on. From the calculated results, we clarify the burnup characteristics of the target LLFPs and their possible ranges of generations. Finally, candidates of the key nuclide are proposed for the scaling factor method of HLW.

Journal Articles

Determination of $$^{79}$$Se and $$^{135}$$Cs in spent nuclear fuel for inventory estimation of high-level radioactive wastes

Asai, Shiho; Hanzawa, Yukiko; Okumura, Keisuke; Shinohara, Nobuo; Inagawa, Jun; Hotoku, Shinobu; Suzuki, Kensuke*; Kaneko, Satoru*

Journal of Nuclear Science and Technology, 48(5), p.851 - 854, 2011/05

 Times Cited Count:25 Percentile:86.49(Nuclear Science & Technology)

Journal Articles

Comparison of post-irradiation experimental data and theoretical calculations for inventory estimation of long-lived fission products in spent nuclear fuel

Asai, Shiho; Hanzawa, Yukiko; Okumura, Keisuke; Suzuki, Hideya; Toshimitsu, Masaaki; Shinohara, Nobuo; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of 13th International Conference on Environmental Remediation and Radioactive Waste Management (ICEM 2010) (CD-ROM), p.261 - 264, 2010/10

Journal Articles

Post irradiation examination analyses with a continuous-energy Monte Carlo code MVP for long-lived fission products in LWR spent fuels

Okumura, Keisuke; Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Katakura, Junichi; Shinohara, Nobuo; Kaneko, Satoru*; Suzuki, Kensuke*

Proceedings of Joint International Conference of 7th Supercomputing in Nuclear Application and 3rd Monte Carlo (SNA + MC 2010) (USB Flash Drive), 5 Pages, 2010/10

For accurate inventory estimation of long-lived fission products in LWR spent fuels, a new burn-up chain model and decay data based on the latest nuclear data were developed for MVP-BURN. They were applied to three post irradiation examinations including inventory measurements of $$^{79}$$Se, $$^{99}$$Tc, $$^{126}$$Sn and $$^{135}$$Cs. One of them is new measurements performed by JAEA. From the PIE analyses, it is found that the new measurements by JAEA are consistent with the other PIE data obtained by different laboratory with different techniques. It is also confirmed that the present calculation results show good agreements with experimental ones for $$^{79}$$Se and $$^{135}$$Cs within about 10%. In contrast, amounts of $$^{99}$$Tc and $$^{126}$$Sn are overestimated by about up to 50%. These discrepancies are likely due to the effect of insoluble residue in the measurements and/or errors of fission yields in the analyses.

Oral presentation

Post irradiation examination for inventory estimation of $$^{79}$$Se and $$^{135}$$Cs in high-level radioactive wastes

Asai, Shiho; Hanzawa, Yukiko; Okumura, Keisuke; Inagawa, Jun; Hotoku, Shinobu; Shinohara, Nobuo; Suzuki, Kensuke*; Kaneko, Satoru*

no journal, , 

Oral presentation

Determination of long-lived radionuclide in spent nuclear fuel; Simple and rapid sample preparation for determination of $$^{79}$$Se

Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Toshimitsu, Masaaki; Inagawa, Jun; Okumura, Keisuke; Shinohara, Nobuo; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

no journal, , 

no abstracts in English

Oral presentation

Determination of long-lived radionuclide in spent nuclear fuel; Anion-exchange separation of tin for $$^{126}$$Sn determination

Toshimitsu, Masaaki; Asai, Shiho; Hanzawa, Yukiko; Suzuki, Hideya; Inagawa, Jun; Okumura, Keisuke; Shinohara, Nobuo; Kimura, Takaumi; Kaneko, Satoru*; Suzuki, Kensuke*

no journal, , 

no abstracts in English

Oral presentation

Continuing efforts to strengthen the IAEA's safeguard framework; Focusing on the infrastructure development support through capacity building

Okumura, Yukiko

no journal, , 

NPT obligates non-nuclear-weapon State Part to it to verify treaty compliance through safeguards and authorizes the IAEA to its implementation. In 1972, the Model Protocol of Comprehensive Safeguards Agreements (CSA) was adopted. A new legal authority was required, however, when the shortcoming of the safeguards implementation was highlighted in arly1990s. So as to confirm the non-existence of the undeclared nuclear material and nuclear activity the Additional Protocol was adopted by the IAEA Board of Governors in 1997. In order to support international safeguards activities conducted by the IAEA, the ISCN of the JAEA has been conducting international cooperation, through seminars and training courses. We have been supporting the countries to enable the enhancement of ratification and effective implementation. This paper will be focusing on how ISCN is contributing to the IAEA's infrastructure development support for safeguards implementation.

Oral presentation

Capacity building in safeguards implementation focusing on the support to the small quantities protocols states

Okumura, Yukiko

no journal, , 

The Small Quantities Protocol (SQP), which has the effect of holding in abeyance the implementation of most of the safeguards measures listed on the Comprehensive Safeguards Agreement, was drafted by the IAEA secretariat in order to lighten the burden of NNWS who have littled burden of non-nuclear material. Due to the few inspection rights, however, the SQP was modified in 2005. Today there are 48 NNWS that have lost their status of the SQP, but still have not concluded declaration under the CSA. This presentation will first enlighten the issue that arose from the modification of the SQP, followed by the measurements that should be taken and the contribution of ISCN to the IAEA's infrastructure development support for safeguards implementation.

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