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Journal Articles

Experimental studies of passive neutron measurement for fuel debris at Fukushima Daiichi Nuclear Power Plants

Nagatani, Taketeru; Shirato, Atsuhiko*; Kosuge, Yoshihiro*; Sato, Takashi*; Kawakubo, Yoko; Shiromo, Hideo; Asano, Takashi

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

As one of the candidate material accountancy technologies for the fuel debris at Fukushima Daiichi Nuclear Power Plants (1F), we propose the application of a passive neutron technique. The applicability of the new concept to the fuel debris at 1F was evaluated by simulation and the results were presented at the last INMM annual meeting. As the next phase, we conducted experimental tests to confirm the validity of the simulation results. Because actual fuel debris or irradiated fuel cannot be handled at our facility due to a licensing limitation, un-irradiated MOX samples, neutron absorbers and Cf-252 sources were utilized as the best available material to imitate the property of the fuel debris and various configurations were measured using an Epithermal Neutron Multiplicity Counter. The fissile mass in the samples, neutron absorber mass surrounding the samples and intensity of Cf-252 source were varied to confirm the correlation between DDSI response and the leakage multiplication. Test results agreed well with the trend of the simulation results. This indicates that DDSI has sufficient capability to evaluate the leakage multiplication of a sample which includes an unknown amount of fissile material and neutron absorber such as the fuel debris at 1F. This paper provides experimental studies of passive neutron measurement based on the combination of DDSI technique and coincidence counting for fuel debris at 1F.

Journal Articles

Simulation study on non-destructive assay for fuel debris by using Fast Neutron Direct Interrogation (FNDI) method

Maeda, Makoto; Furutaka, Kazuyoshi; Kureta, Masatoshi; Ozu, Akira; Tobita, Hiroshi; Komeda, Masao; Hattori, Kentaro

Proceedings of INMM 56th Annual Meeting (Internet), 8 Pages, 2015/07

In Japan Atomic Energy Agency (JAEA), it has been started that investigation on applicability of Fast Neutron Direct Interrogation (FNDI) method to fuel debris. FNDI method is expected to be promising non-destructive Assay (NDA) technique which measures total amounts of fissile materials. In this presentation, we report on basic model of non-destructive measurement system designed by using Monte Carlo Code PHITS, the effect of the matrix in debris canister on FNDI method evaluated by using Monte Carlo Code MVP and four dimensional (4 D) visualization results of neutron flux obtained by using visualization tool we have newly developed.

Journal Articles

Development of prototype national nuclear forensics library at Japan Atomic Energy Agency

Kimura, Yoshiki; Shinohara, Nobuo; Funatake, Yoshio

Proceedings of INMM 56th Annual Meeting (Internet), 8 Pages, 2015/07

Journal Articles

Development of active neutron NDA techniques for nuclear non-proliferation applications

Kureta, Masatoshi; Koizumi, Mitsuo; Ozu, Akira; Furutaka, Kazuyoshi; Tsuchiya, Harufumi; Seya, Michio

Proceedings of INMM 56th Annual Meeting (Internet), 9 Pages, 2015/07

The new program "Development of active neutron NDA techniques" has started for non-proliferation applications. The final purpose of this program is to establish the measurement techniques for the high radioactive special nuclear material such as MA-Pu fuel for transmutation of minor actinide. In this program, the JAEA will conduct the R&D on active neutron non-destructive measurement techniques, DDA, NRTA, PGA/NRCA and DGS in collaboration with EC-JRC.

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

Current activities and future challenges of FNCA's nuclear security and safeguards project

Senzaki, Masao

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

The presentation outlines the role and objectives of Nuclear Security and Safeguards Project (NSSP) as well as FNCA framework and provides activity examples of how NSSP member countries work together to strengthen nuclear security and enhance safeguards effectiveness and raise awareness.

Journal Articles

Conceptual proposal of new detection method for unauthorized removal from glovebox

Nakamura, Hironobu; Tanigawa, Masafumi; Mukai, Yasunobu; Nakamichi, Hideo; Umino, Yoshinori; Fujisaku, Sakae; Kimura, Takashi; Kurita, Tsutomu

Proceedings of INMM 56th Annual Meeting (Internet), 8 Pages, 2015/07

In the MOX handling facilities, many types and amount of nuclear materials (NM) that are relatively easy to access are used in a GB. In order to prevent unauthorized removal of NM from the GB by an insider, based on the Japanese regulation which was referred from INFCIRC/225 Rev.5, the 2 person rule are being introduced at the area where NM handling GB are installed. As an example of usage of the security counterplan for the detection of unauthorized removal of NM, a new proposal of detection concept for the unauthorized removal by operators were investigated with implementation of several experiments considering actual GB operation. In general, it is considered that normal concept is to use radiation monitor ($$gamma$$ or neutron) to detect the event by checking the variation of monitoring data. However, it is thought that distinguish between authorized NM movement during operation and the unauthorized removal (sample bag-out from GB) is very difficult. To solve this subject, JAEA studied and proposes a new concept about negative pressure monitoring in the GB in addition to the radiation monitoring. It is thought that the hybrid monitoring concept between pressure and radiation provides the detection alarm for it with central alarm station (CAS) accurately and rapidly with high integrity, and helps to complement current 2 person rule.

Journal Articles

Preliminary delayed $$gamma$$-ray spectroscopy for non-destructive analysis of fissionable material

Rodriguez, D.; Heyse, J.*; Koizumi, Mitsuo; Mondelaers, W.*; Pedersen, B.*; Schillebeeckx, P.*; Seya, Michio; Takamine, Jun

Proceedings of INMM 56th Annual Meeting (Internet), 8 Pages, 2015/07

There is a growing interest regarding how to effectively safeguard NM, specifically how to efficiently determine the composition of mixed materials. Currently researchers of the JAEA and JRC are discussing the development of a NDA system using a pulsed DT neutron source. The system will utilize a combination of DDA, NRTA, PGA, and DGS techniques. Of specific interest is applying this system toward determining the Pu/U composition of purified MOX fuel and non-purified NM. The DGS technique has the potential to establish fissionable material ratios to relatively high precision. These fission products generate time-dependent $$gamma$$-ray energy spectra that extend well above 3 MeV, a benefit when applied to the NM of interest that have high passive emissions. This presentation will describe initial studies regarding the precision that the DGS portion of this system can obtain and how it will be used in conjunction with the other techniques to analyze the composition of the NM of interest.

Journal Articles

Investigation into cause of increasing count rate on PIMS at RRP, 1; Search of potential causes

Mukai, Yasunobu; Nakamura, Hironobu; Nakamichi, Hideo; Kurita, Tsutomu; Noguchi, Yoshihiko*; Tamura, Takayuki*; Ikegame, Ko*; Shimizu, Junji*

Proceedings of INMM 56th Annual Meeting (Internet), 9 Pages, 2015/07

The PIMS used at Rokkasho Reprocessing Plant can quantify plutonium amount in each process vessel located inside glovebox by means of neutron measurement. Since the PIMS is not used for the neutron coincidence counting, it is very important to maintain that those constants meet the actual process condition. PIMS was calibrated in 2006, and then JNFL has been started to measure the Pu amount directly in each glovebox for the purpose of facility NMA. However, it was found that PIMS counting was unexpectedly and continuously increased during long time of inter-campaign. In order to find out the main cause, JAEA and JNFL jointly conducted several investigations. In the investigations, correctness of system parameters and relevant constants, behavior of the neutron generation when MOX powder is stored in actual glovebox for a long time (to see O/M and moisture change) and the behavior focused on the relation between MOX powder and light element using inside glovebox (fluorine is included in the PTFE which is used in many gloveboxes as packing of instruments) were experimentally confirmed using MOX powder in PCDF. As a result, since the same behavior happened in the actual PIMS was confirmed in the testing environment in which MOX powder coexists with fluorine, it is concluded that the main potential cause of PIMS is the increasing of the probability of ($$alpha$$, $$n$$) reactions by a contact between PTFE and MOX powder.

Journal Articles

Overview of JAEA-ISCN's NDA development programs (for INMM)

Seya, Michio; Koizumi, Mitsuo; Tomikawa, Hirofumi; Naoi, Yosuke; Kureta, Masatoshi; Harada, Hideo; Hajima, Ryoichi; Nakamura, Hironobu

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

ISCN of JAEA has conducted (with collaborations with JAEA other centers) the following development programs of advanced NDA technologies since its establishment. (1) Measurement test of the using PNAR-NDA system for Fugen spent fuel assemblies, (2) Basic development of NRF-NDA technologies using LCS $$gamma$$-rays, (3) Development of alternative to $$^{3}$$He neutron detection technology, (4) Development of neutron resonance densitometry. ISCN has just started the following new programs (also with collaborations with JAEA other centers). (5) Demonstration of NRF-non-destructive detection technology for nuclear security using LCS $$gamma$$-rays, (6) Development of active neutron NDA techniques using a pulsed neutron (D-T) source, (7) Feasibility study on monitoring of high active liquid waste in tanks inside cell. This paper presents the results of basic technology development programs already done and introduces above new programs.

Journal Articles

Capacity building cooperation on nuclear security; Japan's experience of COE cooperation with Indonesia

Noro, Naoko; Naoi, Yosuke; Matsuzawa, Reina

Proceedings of INMM 56th Annual Meeting (Internet), 9 Pages, 2015/07

For effective human capacity building, COE collaboration is an essential factor. As Japan's COE, ISCN has expanded its capacity to provide nuclear security training and infrastructure development support with the strong support from U.S. This paper describes the methodology and contents of ISCN's human resource development cooperation with Indonesia through COEs. The purpose of this paper is to provide a model for capacity building cooperation in nuclear security by introducing Japan's experience, and thus contribute to strengthen regional as well as global nuclear security.

Journal Articles

Demonstrating the integral resonance transmission method; Conceptual and experimental studies

Angell, C.; Hayakawa, Takehito; Shizuma, Toshiyuki; Hajima, Ryoichi; Quiter, B. J.*; Ludewigt, B. L.*; Karwowski, H. J.*; Rich, G.*; Silano, J.*

Proceedings of INMM 56th Annual Meeting (Internet), 9 Pages, 2015/07

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