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Zaima, Naoki; Nakashima, Shinichi; Nakatsuka, Yoshiaki; Kado, Kazumi; Haruyama, Mitsuo; Takase, Misao; Ozu, Akira; Kureta, Masatoshi
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2012/10
We developed uranium mass assay systems for 200-litter wastes drums applied passive neutron measurements by NDA method and applied for the actual wastes drums stored in URCP. The neutron measurement methodology of 
U(
,n) reaction using 
He proportional counters delivered superior performance, however also included some problems that the neutron penetration rates are depend upon matrices or density of wastes drums, so it was difficult to determine uranium mass against "unknown objects". For the purpose of solving problems active neutron measurements appears promising, we are now challenging to improve our equipments, which are composed of neutron generator, polyethylene moderators and He proportional counters. The uranium mass are determined by counting secondary neutrons generated from nuclear fissions. Our preliminary simulations suggest good performances with higher sensitivities and accuracies. It is extremely expected to contribute in the fields of safeguards works.
Haruyama, Mitsuo; Takase, Misao; Ozu, Akira; Kureta, Masatoshi; Zaima, Naoki; Nakashima, Shinichi; Nakatsuka, Yoshiaki; Kado, Kazumi
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2012/10
no abstracts in English
Koizumi, Mitsuo; Kitatani, Fumito; Harada, Hideo; Takamine, Jun; Kureta, Masatoshi; Seya, Michio; Tsuchiya, Harufumi; Iimura, Hideki
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2012/10
The melted fuel (MF) of the Fukushima Daiichi Nuclear Power Plant of the Tokyo Electric Power Company will be taken out to dismantle the reactors. At that time, quantification of nuclear materials (NM) in the melted fuel (MF) is probably required. Quantification of NMs in debris is, however, considered to be difficult because of their variety of size, shape and unknown compositions. Consequently, quantification methods have not been established so far. In this paper, we propose a method, neutron resonance densitometry (NRD), for quantification of NMs in particle like debris of MF. Techniques of neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA) or prompt 
ray analysis (PGA) are combined. A time of flight (TOF) system is introduced for the measurements.
Kureta, Masatoshi; Soyama, Kazuhiko; Seya, Michio; Ozu, Akira; Haruyama, Mitsuo; Takase, Misao; Sakasai, Kaoru; Nakamura, Tatsuya; To, Kentaro
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2012/10
Alternative techniques to neutron detection by helium-3 for nuclear security and safeguards systems are necessary to be developed since helium-3 shortage is serious. With support of Japanese government (the Ministry of Education, Culture, Sports, Science and Technology), we have started an R&D project of Pu NDA system using ZnS ceramic scintillator. Here we present development plan, production of a new type of ZnS ceramic scintillator experimentally and basic design of a PCAS alternative Pu NDA system. We are planning the demonstration tests using the alternative NDA system comparing with the current PCAS in which the helium-3 counters are installed.
Nakamura, Hironobu; Kureta, Masatoshi; Ozu, Akira; Soyama, Kazuhiko; Nakamura, Tatsuya; Mukai, Yasunobu; Seya, Michio
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 8 Pages, 2012/10
To establish an alternative technique of He neutron detector as a safeguards application, we have started an R&D project to develop a new type of neutron detector (Pu NDA) using ZnS ceramic scintillator with support of Japanese government. The detector design is basically referenced from PCDF-PCAS (Plutonium Canister Assay System) which has total 22 He tubes and is used for a MOX canister measurement. In order to prove the technology and performance after the fabrication, we are planning to conduct 2 stage of demonstration activity. The first stage of demonstration implements the confirmation of flatness response profile for vertical axis, determination of detector parameters and basic performance comparison using Cf source and MOX powder around June 2013. After some modification will have completed, the second stage of demonstration activity will be conducted around December 2013. During the activity, we plan to perform the performance comparison between current PCAS and the new Pu NDA regarding Pu mass and counting statistics. It is expected that the new Pu NDA proves good performance for establishment of alternative technology instead of He neutron detector.
Nakamichi, Hideo; Nakamura, Hironobu; Beddingfield, D.*; Mukai, Yasunobu; Kurita, Tsutomu
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2012/10
Plutonium holdup in gloveboxes (GBs) are measured by HBAS (passive neutron based NDA, Holdup Blender Assay System) for the material control and accountancy (MC&A) at Plutonium Conversion Development Facility (PCDF). In the case that the GBs are installed close to one another, the cross-talk which means neutron double counting among GBs should be corrected properly. Though we used to use predetermined constants as the cross-talk correction, a new correction methodology for neutron cross-talk among the GBs with inventory changes is required for the improvement of MC&A. In order to address the issue of variable cross-talk contributions to holdup assay values, we applied a dynamic cross-talk correction (DCTC) method, based on the distributed source-term analysis approach, to obtain the actual doubles derived from the cross-talk between multiple GBs. As a result of introduction of DCTC for HBAS measurement, we could reduce source biases from the assay result by estimating the reliable doubles-counting derived from the cross-talk. Therefore, we could improve HBAS measurement uncertainty to about 10% which is a half of conventional system. Since the DCTC methodology can be used to determine the cross-correlation among multiple inventories in small areas, it is expected that this methodology can be extended to the knowledge of safeguards by design.
Katano, Yoshiaki; Ebara, Noriyasu; Takagi, Hisatsugu; Nakamura, Takahisa; Bolind, A.; Seya, Michio
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 10 Pages, 2012/10
The ATR, "Fugen" was a prototype nuclear reactor moderated by heavy water but cooled by boiling light water. It terminated its operations in 2003 and is now being decommissioned. Nevertheless, the spent-fuel pool at Fugen still remains and currently contains both MOX spent-fuel assemblies, and it is flexible enough to be able to conduct Non Destructive Assays (NDA) experiments on the spent fuel assemblies. Therefore, JAEA and the U.S. Los Alamos National Laboratory (LANL) are planning to conduct a test of an integrated PNAR/SINRD NDA measurement system at Fugen in 2013. LANL is designing and constructing the system, and JAEA is preparing the Fugen site for the test. The total experience of preparing for and conducting NDA measurements on actual spent fuel assemblies will teach important lessons about the practicality of applying such measurements in the future to spent fuel assemblies from commercial LWR power plants, especially with regard to satisfying legal and safety requirements.
Makino, Risa; Ishiyama, Koichi; Kimura, Takashi; Yamazaki, Katsuyuki; Nakamura, Hironobu; Ikeda, Atsushi*; Yamaguchi, Katsuhiro*
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2012/10
The Integrated Safeguards (IS) applied to JNC-1 site began from August, 2008. At that time, the inspection scheme was replaced from Interim Inventory Verification (IIV) with scheduled day to Random Interim Inspection (RII) with short notice in order to strengthen deterrent against diversion of nuclear materials. To satisfy the requirements for IS in Tokai reprocessing facilities including Tokai Reprocessing Plant and Plutonium Conversion Development Facility, we have cooperated inspectorates to establish remote monitoring systems, and to introduce RII smoothly. Though the new inspection scheme requires additional efforts which contain keeping a certain number of operators every day and declaration of interim inventory lists in a short time, the whole inspection days per year during inter-campaign could be decreased to about 60% by comparing with the conventional IIV. This paper reports the effects after introduction of RII and the future tasks to be discussed regarding RII during campaign from the operator's standpoint.
Kawata, Norio; Wakabayashi, Shuji; Naito, Aisaku
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 6 Pages, 2012/10
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency set up exercise facilities for trainee of nuclear power emerging countries in Asia involved in Physical Protection (PP) including government officers in charge of nuclear security policy or nuclear security regulation, planning and management staff of PP facilities of operating companies, design professionals for PP facilities, and security personnel responsible for PP. After April in 2012, the facility started to be applied to actual ISCN's PP training and is expected as training field for not only Asian nuclear emerging country but also domestic nuclear energy companies and regulatory bodies. In order to provide effective and practical exercises, we set up the training facilities with basic measures and equipment typical of those used in actual PP facilities, e.g., protective fences, sensors, and cameras. This paper provides an outline of the facilities.
Shizuma, Toshiyuki; Hajima, Ryoichi; Hayakawa, Takehito; Angell, C.; Seya, Michio
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 5 Pages, 2012/10
We have proposed an advanced hybrid K-edge/XRF densitometory (advanced HKED) using an intense mono-energetic X-ray beam from laser Compton scattering (LCS). According to our previous simulation studies with the EGS5 Monte Carlo simulation code, it appears that quick analysis of U, Pu, and Np concentrations in resolver solutions with high precision is possible. In this paper, we discuss a method that enables simultaneous analysis of multiple elements based on the advanced HKED technique. We also report on the IAEA Workshop "XRF-Techniques for Quantitative Analysis in the Nuclear Field" held in June 2012.
Nonaka, Nobuyuki
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 7 Pages, 2012/10
At the Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency, the virtual reality (VR) training system is under development for providing a practical training environment to implement experience-oriented and interactive lessons on nuclear security for wide range of participants in human resource development assistance program mainly to Asian emerging nuclear-power countries. This system electrically recreates and visualizes nuclear facilities and training conditions in stereoscopic (3D) view on a large-scale display (CAVE system) as virtual reality training facility (VR facility) and it provides training participants with effective environments to learn installation and layout of security equipment in the facility testing and verifying visually the protection performances under various situations such as changes in day-night lighting and weather conditions, which may lead to practical exercise in the design and evaluation of the physical protection system. This paper introduces basic concept of the system and outline of training programs as well as featured aspects in using the VR technology for the nuclear security.
Kobayashi, Naoki; Naoi, Yosuke; Wakabayashi, Shuji; Naito, Aisaku; Hamada, Kazuko; Noro, Naoko; Matsuzawa, Reina
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2012/10
The Integrated Support Center for Nuclear Nonproliferation and Nuclear Security (ISCN) of the Japan Atomic Energy Agency has started its human capacity building activities, domestically and internationally, for the government officials and employees of companies of emerging nuclear power countries mainly in Asia. In this paper, I will describe the activities of ISCN on capacity building for these countries and also I will briefly describe, focusing on nuclear security, the activities of IAEA, Sandia National Laboratory of United States and the development of human capacity building support activities of neighboring countries of China and Korea. By doing this, I will describe the relationship and cooperation of ISCN with these organizations and talk about my personal views of the future development with these organizations and ISCN.
Bolind, A.; Kureta, Masatoshi; Soyama, Kazuhiko; Hajima, Ryoichi; Harada, Hideo; Nakamura, Takahisa; Seya, Michio
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 10 Pages, 2012/10
JAEA has made progress in four development programs of advanced technologies for the measurement of nuclear material for safeguards and security. In the first program, we have designed and simulated a non-destructive assay (NDA) system that uses ZnS-ceramic-scintillator neutron detectors, instead of He neutron detectors. The second program is a basic demonstration of nuclear resonance fluorescence (NRF) as an NDA technique for measuring the fissile isotopes in nuclear material. Construction of one loop of an energy-recovery linac (ERL) at KEK in Tsukuba was begun this past year, and will finish in this fiscal year. The ERL will produce a high-intensity, mono-energetic -ray beam for NRF. Also JAEA and the US Department of Energy are evaluating NRF-simulation codes. In the third program, we have started to design and construct a prototype of a new NDA system to determine the quantity of nuclear material in particle debris of melted nuclear fuel. It uses both neutron resonance transmission analysis (NRTA) and neutron resonance capture analysis (NRCA). In the fourth program, we have made detailed preparations for testing a new NDA instrument (constructed by Los Alamos National Laboratory) on used nuclear fuel assemblies in the spent fuel pool at Fugen, next year. It uses a combined technique of passive neutron albedo reactivity (PNAR) and self-interrogation neutron resonance densitometry (SINRD).
Seya, Michio; Harada, Hideo; Kitatani, Fumito; Koizumi, Mitsuo; Tsuchiya, Harufumi; Iimura, Hideki; Kureta, Masatoshi; Takamine, Jun; Hajima, Ryoichi; Hayakawa, Takehito; et al.
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 10 Pages, 2012/10
This paper presents feasibility (selection) study of NDA techniques, NRD (Neutron Resonance Densitometry) and LCSG-NRF (LCS -rays interrogation Nuclear Resonance Fluorescence), to measure nuclear material (NM) in debris of melted fuel with high precision. The melted fuel under consideration here is the one formed by the severe loss of coolant accidents of such as Units 1 - 3 of Fukushima-Daiichi NPP. NRD based on NRTA (Neutron Resonance Transmission Analysis) and NRCA (Neutron Resonance Capture Analysis) utilizing the TOF (Time of Flight) method is intended for measurement of NM (all isotopes of U/Pu) in particle-like debris. LCSG-NRF using intense LCS (Laser Compton Scattered) -rays (mono-energetic -rays) is to measure NM (all isotopes of U/Pu) in small rock-like debris and cut-shape debris (cylindrical, slab-shpape). In this paper we also summarize advantages of two techniques compared with other NDA techniques.
Bolind, A.; Seya, Michio
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-33-Kai Nenji Taikai Rombunshu (Internet), 12 Pages, 2012/10
Since 2008, the US Department of Energy, through its Next Generation Safeguards Initiative (NGSI), has renewed the research of non-destructive-assay (NDA) techniques for determining the plutonium mass in spent nuclear fuel assemblies. Of the fourteen technologies that are being considered in the NGSI, ten technologies measure neutrons to determine the fissile content of the nuclear material. These ten techniques can be categorized according to the characteristic of the neutrons that they measure. Five techniques measure the multiplication of neutrons by fissile material, three analyze the neutron energy spectrum for resonance reactions in fissile isotopes, and two measure the time coincidence of the neutrons that are emitted by fission. A basic knowledge of these principles is essential for understanding these techniques. This paper summarizes parts of this knowledge.
Nagatani, Taketeru; Nakajima, Shinji; Asano, Takashi; Kawasue, Akane*; Iso, Shoko*; Kumakura, Shinichi*; Watanabe, Takehito*; Marlow, J.*; Martyn, S.*; Menlove, H.*; et al.
no journal, ,
The AVIS (Advanced Verification for Inventory sample System), which was designed by LANL in partnership with Nuclear Material Control Center (NMCC), is a nondestructive assay (NDA) system to measure the plutonium mass for plutonium uranium mixed oxide (MOX) powder and pellet for large scale MOX fuel fabrication plant (J-MOX). The AVIS is intended to meet a performance specification of a total measurement uncertainty of less than 0.5% in the neutron (
Pu effective) measurement. It is intended that the AVIS measurement will be substituted for a fraction of the DA samples to reduce the number of DA from J-MOX. Therefore, the AVIS has a crucial role to attain effective safeguards for J-MOX. JAEA, which has experience/knowledge to develop the NDA system and plutonium handling field, was entrusted with performance testing for the AVIS from NMCC. JAEA has conducted performance testing on the AVIS using standard radiation source (neutron and ). As the results of test, it was confirmed that the AVIS has the designed performance. As a next step, JAEA will conduct the AVIS test using MOX materials in order to evaluate the relevant measurement accuracy. This paper reports the performance test results and future MOX test plans of the AVIS.
Kijima, Yuichi; Inoue, Naoko; Yamamoto, Yoichi; Oda, Tetsuzo
no journal, ,
The International Noble Gas Experiment (INGE) is being carried out for global measurements of radioactive noble gas (radioxenons), as part of the international verification regime for the Comprehensive nuclear-Test-Ban Treaty (CTBT). There are many medical institutions and nuclear facilities in and around Japan, which are possible sources of radioxenons, and it is therefore important to understand their behavior of normal background for detection of underground nuclear tests. The joint measurement is conducted by US Pacific Northwest National Laboratory (PNNL) and JAEA. A transportable and high sensitive noble gas monitoring system developed by PNNL was installed at Mutsu city, Aomori, which was selected based on the information obtained by simulations with an atmospheric transport model and the field surveys. The measurement has been started for survey on noble gas behavior in and around Japan. This paper describes the outline and the preliminary results of measurement.
Angell, C.; Hayakawa, Takehito; Shizuma, Toshiyuki; Hajima, Ryoichi
no journal, ,
Sakurai, Satoshi; Kimura, Yoshiki; Sato, Kaneaki; Toda, Nobufumi; Shinoda, Yoshiharu; Okubo, Ayako; Magara, Masaaki; Watahiki, Masaru; Kuno, Yusuke
no journal, ,
The national statement made by the Japan Government at 2010 Nuclear Security Summit (Washington D.C., U.S.A.) was to develop its nuclear forensics detection and analysis technologies in a three-year period and to share them with the international community to contribute to strengthening the nuclear security regime. The Japan Atomic Energy Agency, the organization that possesses analytical capabilities with the potential to fulfill this nuclear forensics mission, started R&D on nuclear forensics technology from JFY 2011. The main areas of development are isotopic ratio analysis, impurity analysis, uranium age determination, etc. The cooperation with US-DOE and EC-JRC were also started to effectively promote the technical development. In the presentation reported will be progress in R&D to establish nuclear forensics analytical capabilities and international cooperation.
Senzaki, Masao
no journal, ,
no abstracts in English