Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Tsuchiya, Harufumi; Harada, Hideo; Koizumi, Mitsuo; Kitatani, Fumito; Takamine, Jun; Kureta, Masatoshi; Iimura, Hideki; Kimura, Atsushi; Becker, B.*; Kopecky, S.*; et al.
Proceedings of INMM 55th Annual Meeting (Internet), 6 Pages, 2014/07
Nagatani, Taketeru; Nakajima, Shinji; Kosuge, Yoshihiro*; Shiromo, Hideo; Asano, Takashi
Proceedings of INMM 55th Annual Meeting (Internet), 10 Pages, 2014/07
Meltdown of the reactor cores of Units 1-3 occurred at Fukushima Daiichi Nuclear Power Plants (1F). Fuel debris at 1F contains minor actinides and fission products and neutron absorber. These materials make it difficult to quantify fertile nuclear materials in fuel debris by the conventional passive neutron technique. We consider that DDSI and PNAR which focused on fissile material are promising techniques to quantify the nuclear materials in the fuel debris. A concept of application of these techniques to fuel debris measurement was investigated and presented at the last INMM annual meeting. In order to evaluate the applicability of these techniques to fuel debris measurement, we investigated the neutron behavior in the fuel debris by using MCNPX simulation code. Because property of fuel debris is not clear, source term data used were prepared by referring TMI data. This paper provides results of MCNPX simulation for fuel debris measurement at 1F with passive neutron techniques.
Nakajima, Shinji; Nagatani, Taketeru; Shiromo, Hideo; Asano, Takashi; Marlow, J. B.*; Swinhoe, M. T.*; Menlove, H. O.*; Rael, C. D.*; Kawasue, Akane*; Iso, Shoko*; et al.
Proceedings of INMM 55th Annual Meeting (Internet), 10 Pages, 2014/07
The Advanced Fuel Assembly Assay System (AFAS) is an unattended non-destructive assay (NDA) system by neutron measurement to verify the plutonium amount in an LWR plutonium and uranium mixed oxide (MOX) fuel assembly. The assembly will be fabricated in the MOX fuel fabrication plant under construction by the Japan Nuclear Fuel Limited. The AFAS has been developed by Los Alamos National Laboratory under the auspices of the Secretariat of Nuclear Regulation Authority in Japan. The AFAS is the first NDA system which will verify the active length of the assembly without inspector attendance. Japan Atomic Energy Agency (JAEA) has conducted the performance test for the AFAS under the contract with Nuclear Material Control Center to demonstrate this active length verification technology by using MOX fuel assemblies owned by JAEA. As the results, it was confirmed that measurement error of the active length for the MOX fuel assembly was less than 0.1% and it was satisfied with requirement by IAEA. This paper provides the performance test results for the active length verification of the AFAS.
scintillation detector system for neutron resonance densitometry (NRD)Koizumi, Mitsuo; Tsuchiya, Harufumi; Kitatani, Fumito; Harada, Hideo; Takamine, Jun; Kureta, Masatoshi; Seya, Michio; Kimura, Atsushi; Iimura, Hideki; Becker, B.*; et al.
Proceedings of INMM 55th Annual Meeting (Internet), 7 Pages, 2014/07
Harada, Hideo; Schillebeeckx, P.*; Tsuchiya, Harufumi; Kitatani, Fumito; Koizumi, Mitsuo; Takamine, Jun; Kureta, Masatoshi; Iimura, Hideki; Kimura, Atsushi; Seya, Michio; et al.
Proceedings of INMM 55th Annual Meeting (Internet), 8 Pages, 2014/07
Kimura, Yoshiki; Shinohara, Nobuo; Sato, Kaneaki; Toda, Nobufumi; Shinoda, Yoshiharu; Funatake, Yoshio; Watahiki, Masaru; Kuno, Yusuke
Proceedings of INMM 55th Annual Meeting (Internet), 7 Pages, 2014/07
In 2010, the Japan Government issued the national statement at Nuclear Security Summit (Washington D.C., USA) to develop technologies related to measurement and detection of nuclear materials for nuclear forensics within three-year timeframe, and to share the products with the international community in order to contribute to strengthening the nuclear security system. In response to this statement, JAEA that possesses sufficient technical capabilities to fulfil this nuclear forensics mission has started a nuclear forensics technology development project since JFY 2011. This paper will present the progress of the development project during JFY 2011 to 2013. This project includes the developments of analytical technologies such as isotope and impurity measurements, morphology analysis, age determination technique, and the prototype of national nuclear forensics library (NNFL). Some future prospects of this project will be also presented in this paper.
Noro, Naoko
Proceedings of INMM 55th Annual Meeting (Internet), 10 Pages, 2014/07
Reflecting the recommendation on physical protection by the International Atomic Energy Agency, nuclear security regulations in Japan were revised in March 2012 and new regulation requires operators to establish a framework to promote nuclear security culture within their organization, including the involvement of top management. This presentation introduces the efforts by the operators to develop effective nuclear security culture program within their organizations. It also introduces lessons learned by ISCN through its activities to promote nuclear security in Japan.
Kuno, Yusuke; Hara, Daisuke*
Proceedings of INMM 55th Annual Meeting (Internet), 9 Pages, 2014/07
Comparison study of material-oriented Proliferation Resistance (PR) for plutonium in spent fuels resulting from both cases of direct disposal and recycle use is quantitatively made. The extended the figure-of-merit (FOM) described in term of time was used, where dose of actual spent fuels and their chemical/physical properties, and material quantity are additionally considered to the original FOM. This case study on spent fuels from LWR, once/twice recycles with MOX-LWR and Fast Reactor showed significant differences on FOM (attractiveness) among them.
Komeda, Masao; Ozu, Akira; Haruyama, Mitsuo; Takase, Misao*; Kureta, Masatoshi; Nakatsuka, Yoshiaki; Zaima, Naoki; Nakashima, Shinichi; Otsuka, Yoshimasa
Proceedings of INMM 55th Annual Meeting (Internet), 9 Pages, 2014/07
We have researched and developed the FNDI method for a long time through experiments in NUCEF in JAEA Tokai. Referred from the pilot machine, we designed a demonstrator, called as JAWAS-N, for applying to non-destructive assay tools for uranium waste drums in JAEA Ningyo. In this paper, we present the modeling and the simulations concerning JAWAS-N's characteristics, and discuss for practical use compared analytical results with obtained some experimental data.
B
O
ceramic scintillator detectorsNakamura, Hironobu; Ozu, Akira; Kobayashi, Nozomi*; Mukai, Yasunobu; Sakasai, Kaoru; Nakamura, Tatsuya; Soyama, Kazuhiko; Kureta, Masatoshi; Kurita, Tsutomu; Seya, Michio
Proceedings of INMM 55th Annual Meeting (Internet), 9 Pages, 2014/07
To establish an alternative technique of He-3 neutron detector that is used for nuclear material accountancy and safeguards, we have started an R&D project to develop a new type of neutron detector (Pu NDA system) using ZnS/BO ceramic scintillator with support of Japanese government. The design of the alternative system (ASAS: Alternative Sample Assay System) is basically referenced from INVS (INVentory Sample assay system) which is passive neutron assay system of plutonium and has total 18 He-3 tubes (about 42% of counting efficiency), and the small amount of Pu in the MOX powder or Pu nitrate solution in a vial can be measured. In order to establish the technology and performance after the fabrication of the new detector progresses, we are planning to conduct demonstration activity in the early 2015 experimentally. The demonstration activity implements the confirmation of reproducibility about sample positioning, optimization of detector parameters, counting statistical uncertainty, stability (temperature and 
-ray change) check and figure of merit (FOM) using check source and actual MOX powder. In addition to that, performance comparison between current INVS and the ASAS are also conducted. In this paper, we present some analytical study results using a Monte-Carlo simulation code (MCNP), entire ASAS design and demonstration plan to prove technology and performance.
Seya, Michio; Kureta, Masatoshi; Soyama, Kazuhiko; Nakamura, Hironobu; Harada, Hideo; Hajima, Ryoichi
Proceedings of INMM 55th Annual Meeting (Internet), 10 Pages, 2014/07
JAEA has been implementing development programs of basic technologies of the following advanced NDA (non-destructive assay) of nuclear material (NM) for nuclear safeguards and security. (1) Alternative to 
He neutron detection using ZnS/BO ceramic scintillator, (2) NRD (neutron resonance densitometry) using NRTA (neutron resonance transmission analysis) and NRCA (neutron resonance capture analysis), (3) NRF (nuclear resonance fluorescence)-NDA using laser Compton scattered (LCS) -rays (intense mono-energetic -rays). The development program (1) is for NDA systems that use ZnS/BO ceramic scintillator as alternative neutron detector to He for coming shortage of its supply. The program (2) is for a NDA system of isotopic composition measurement (non-destructive mass spectroscopy) in targets such as particle-like melted fuel debris using NRTA and NRCA. The program (3) is for NDA systems using a specific NRF reaction of certain Pu/U isotope caused by mono-energetic LCS -ray with energy tuned to the specific excited state of the isotope. This paper introduces above three programs.
B+He integrated continuous monitor (BHCM) to holdup monitoring in glove boxesMukai, Yasunobu; LaFleur, A. M.*; Nakamura, Hironobu; Menlove, H. O.*; Swinhoe, M. T.*; Marlow, J. B.*; Kurita, Tsutomu
Proceedings of INMM 55th Annual Meeting (Internet), 8 Pages, 2014/07
In order to improve the safeguards and nuclear material accountancy of holdup measurements and establish an alternative technology for He shortage, we have designed the B + He Integrated Continuous Monitor (BHCM) and implemented the measurements to continuously monitor the holup in gloveboxes at Plutonium Conversion Developoment Facility. In this paper, we present the outline of BHCM, the comparison between MCNP simulations and the measured results in preliminaly test and a demonstration of process monitoring ability during operation to see the relation between Totals trend and operational status by using B detection tubes.
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.
Makino, Risa; Swinhoe, M. T.*; Suzuki, Yoshimasa; Mukai, Yasunobu; Menlove, H. O.*; Marlow, J. B.*; Nakamura, Hironobu
Proceedings of INMM 55th Annual Meeting (Internet), 9 Pages, 2014/07
The Inventory Verification Sample systems (INVS) is a non-destructive assay (NDA) system for small inventory samples to quantify the Pu amount in Pu and U-Pu nitrate solutions and MOX powder with 31.3% counting efficiency (for Cf). It has been used for IAEA safeguards measurement for many years at the Plutonium Conversion Development Facility (PCDF) for the samples taken at the time of Random Interim Inspection (RII) and Physical Inventory Verification (PIV), and is currently used as partial defects verification equipment with uncertainty about 3
5% accuracy for solution samples. The INVS is a inline detector therefore it is very convenient to use since it can be used for a sample inside the glove box without bag-out. If the measurement uncertainty can be improved (to 1%), it is expected that the usage can be extended to the operator's own measurements in MC&A to reduce effort and the number of destructive analyses (DA). In order to improve the measurement uncertainty, we have performed multiplicity measurements using a variety of solution samples (concentration, acidity and volume) to determine the Pu amount and uncertainty, although the multiplicity analysis is challenging. To control the measurement quality, a few MOX ceramic fuel pellets with known Pu amount are used. The results are evaluated by three kinds of methods (calibration curve, known-
and multiplicity) to determine the best measurement method. In the range of concentration of typical samples, we could confirm good correlations between measured doubles and 
Pu effective mass in the three methods. Especially, the conventional calibration curve method showed a good performance with short measurement time and small uncertainty when the calibration standards were a good match to the unknown samples. In this paper, we present the INVS system design and measurement results with uncertainty using solution samples and comparison results among the three calibration methods.
Naoi, Yosuke; Kobayashi, Naoki; Senzaki, Masao
Proceedings of INMM 55th Annual Meeting (Internet), 9 Pages, 2014/07
Within the Asian region, China and ROK also committed at the 2010 Security Summit to establishing similar training centers. ROK established one in February 2014, and China started construction on its center in October 2013, aiming to commence activities in 2015. In 2013, the International Atomic Energy Agency (IAEA) started discussions with these three countries for the harmonization of the contents of their centers' training activities. The purpose of these discussions is to avoid duplication of effort, since three centers of a similar kind will be established in the Asian region. In these discussions, ISCN has taken the lead to find ways to make this harmonization a reality. This paper will present the result of ISCN's activities over the past three and a half years; the current situation of the cooperation among the three countries, Japan, China, and ROK; and the future efforts to be made.
Sumi, Mika; Abe, Katsuo; Kageyama, Tomio; Mason, P.*
no journal, ,
In order to obtain reliable accountancy analysis results, IDMS is applied at most of the Pu handling facilities in Japan. Reference materials, referred to as LSD spikes were developed to allow facilities, regulatory and safeguards organizations to accurately measure nuclear materials. Because of expected difficulties in the long term supply of Pu reference materials, which are the main source for LSD spike preparation, the JAEA decided to evaluate the possibility of using domestically available MOX as a Pu source material. JAEA-PFDC started to produce and certify Pu reference materials that are suitable for use in producing LSD spikes in collaboration with the US DOE-NBL. From the MOX-Pu characterized in 2008, two types of the LSD spikes were prepared and distributed for verification. The detailed purification procedure, results of the intercomparison of LSD spikes and interim intercomparison of the MOX-Pu prepared in 2012 will be presented.
Shizuma, Toshiyuki; Hayakawa, Takehito; Angell, C.; Hajima, Ryoichi; Minato, Futoshi; Suyama, Kenya; Seya, Michio; Johnson, M.*; McNabb, D.*
no journal, ,
It is required to measure spent nuclear fuel as accurate as possible for nuclear material management concerning nuclear security and safeguards. The system performance such as counting precision for the -ray nondestructive assay (NDA) based on nuclear resonance fluorescence (NRF) would be affected by radiation backgrounds from spent fuel. Generally, the -ray spectrum of radiation backgrounds from spent fuel has characteristic shape with an exponential fall-off as a function of -ray energy. Therefore, the NRF measurement at higher energies is preferable to obtain a better signal-to-noise ratio. The counting precision is also affected by backgrounds from the coherent scattering such as Rayleigh, nuclear Thomson, and Delbr
ck scattering. In order to minimize the Coherent scattering contribution, we propose a method in which NRF transitions to the first excited state is measured. We calculated the radiation background counts from spent fuel as well as the coherent scattering background. Assuming various cross sections for NRF in the range of 3 to 100 eV barn at excitation energies of 2 to 5 MeV, we have estimated the statistical uncertainties of the proposed NDA system. We also discuss the NRF strength based on the previous experimental data as well as theoretical prediction by quasi-particle random phase approximation (QRPA).
Hori, Keiichiro; Heinberg, C.; Conner, J.*; Browne, M.*; Colin, C.*
no journal, ,
At the time of accident, about 270 tons of fuel were in Units 1- 3 at Fukushima Daiichi Nuclear Power Station. Up to that time, material accountancy was implemented as an item facility for adequate material control and for the International Atomic Energy Agency's safeguards verification. Fuel debris contains nuclear fuel materials, fission products and structural materials, etc. Fuel debris will need to be controlled adequately after removal from the reactors, but material accountancy measures as an item facility no longer can be applied because of meltdown of the fuel. Development of measurement technologies for fuel debris may be required for adequate material control and accountancy of special nuclear material in the fuel debris at Fukushima Daiichi. Japan Atomic Energy Agency (JAEA) and United States Department of Energy/National Nuclear Security Administration (DOE/NNSA) have agreed to collaborate to investigate past experience on material control at severe accidents involving reactor core fuels and potential measurement technologies for fuel debris measurement. Besides DOE/NNSA and JAEA, Japanese Government, Tokyo Electric Power Company (TEPCO), Central Research Institute of Electric Power Industry (CRIEPI) and the U.S. National Laboratories have been collaborating in this effort. This paper describes the purpose, objectives, structure and process of this collaboration.
Tomikawa, Hirofumi; Watahiki, Masaru; Kuno, Yusuke
no journal, ,
Japan is the only non-nuclear-weapon country with nuclear fuel cycle facilities including uranium enrichment and reprocessing facilities. The evolution of technologies has been instrumental in improving facility and safeguards efficiency. Older facilities with small material throughput operated almost manually. In contrast, more modern facilities with large material throughput were designed for improved throughput and accountancy and introduced state-of-art safeguards technologies. Japan has the experience of a series of new types of nuclear facilities which are pilot scale through commercial size. This paper presents the efforts and evolutions of the safeguards technology development introduced to the bulk handling facilities including uranium enrichment, reprocessing and MOX fuel fabrication facilities in Japan, through international cooperation. The evolution of technologies has benefited both the State/Operator and the IAEA.
spectrometry of low-volatile FPs for accountancy of special nuclear material in molten core material of Fukushima Daiichi Nuclear Power Plant; Detectability of leakage -ray and fundamental characteristics of U-Ce/Eu compoundTomikawa, Hirofumi; Sagara, Hiroshi*; Shiba, Tomooki*; Ishimi, Akihiro; Osaka, Masahiko; Watahiki, Masaru; Kuno, Yusuke
no journal, ,
For nuclear material accountancy of molten core material in Fukushima Daiichi Nuclear Power Station units 1, 2 and 3 (1F1, 1F2 and 1F3), a variety of technologies are being evaluated from the viewpoint of applicability for in-situ measurement. For one of the technologies, a feasibility study of passive spectroscopy of low-volatile fission products (FPs) has been performed by reviewing TMI-2 experience, and studying the correlation of actinides and FPs inventory in the cores of 1F1, 1F2 and 1F3, considering the sensitivity of axial neutron spectrum, void, burnup, enrichment distribution unique to BWR fuel, and leakage -ray from molten core materials sphere model. In this paper, numerical simulation of leakage -ray from molten core materials in a hypothetical canister is dealt with for determination of radioactivity of low-volatile high-energy emission FPs, which could be utilized for special nuclear material (SNM) quantity estimation coupled with SNM/FPs ratio derived from core inventory calculations. This paper also presents the summary of survey results of high-temperature chemical stability of lanthanides coexisting with nuclear material in a certain atmospheres and temperatures simulating severe accident.
technologiesTomikawa, Hirofumi; Heinberg, C.; Nauchi, Yasushi*; Vo, D.*; Carroll, C.*; Hori, Keiichiro
no journal, ,
In order to survey technologies to be developed for nuclear material quantification of fuel debris at 1F, Japan Atomic Energy Agency (JAEA) and United States Department of Energy (DOE) started collaborative research from November 2012. Under the collaborative research, three Working Groups, Neutron Working Group (NWG), Gamma Working Group (GWG) and Source Term Working Group (STWG) were established. The roles of GWG are to identify measurement systems that could be studied further for possible implementation at 1F. Candidate measurement technologies are Gross Counting, Dosimetry, -ray Spectroscopy, -ray Densitometry, -ray Imaging, Transmission (X-ray) Radiography, Prompt Fission -ray Counting and Spectroscopy, and Neutron Induced -ray Spectroscopy. Taking into account system cost, system size, measurement time, development period, and potential for applicability to fuel debris, GWG members have identified recommended combinations among the technologies supplemented with neutron measurement technologies. The evaluation was carried out by literature search and simulation works. This paper provides recommendations of the GWG for measurement systems based on mainly measurement technologies for nuclear material accountancy of fuel debris at 1F.