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Sumi, Mika; Surugaya, Naoki; Kurosawa, Akira; Suzuki, Toru; Kuno, Yusuke
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 8 Pages, 2010/12
For the long-term stable operation of nuclear fuel cycle facilities, it is essential to satisfy the requirements of IAEA safeguards agreement. The requirements to maintain and improve the precision of DA are supposed to grow along with nuclear fuel cycle fully in progress and Pu handling amount increases. In order to maintain long-term stability of quality level of accountancy analysis for safeguards, a special committee on "Quality Assurance (QA) for Accountancy / Safeguards analysis" was established at Atomic Energy Society Japan supported by INNN-Japan. Experts for safeguards analysis, reference materials, statistics and QA were gathered and drafted the committee standard document for isotope dilution mass spectrometry, the major accountancy analysis technique for Pu and U, supported Pu standard preparation at JAEA and summarized the items needed for QA of DA.
Lee, C. G.; Suzuki, Daisuke; Esaka, Fumitaka; Magara, Masaaki; Kimura, Takaumi; Shinohara, Nobuo
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 9 Pages, 2010/12
A method to selectively detect uranium particles with higher 
U enrichment has been developed; this method can contribute to improving particle analysis on nuclear safeguards environmental samples. The newly developed method involves three key components, (1) a two-step filtration system for particle recovery from swipe samples, (2) a system for controlling the etching time of fission track (FT) detector, (3) a system for comparing the FT morphologies and particle sizes. In order to verify the effectiveness of the screening method developed, a mixture sample containing uranium particles with natural composition and those with 10% enrichment is used. It was shown that enrichment-based screening of uranium particles is possible by comparing the FT morphologies and particle sizes, in addition to controlling the etching time. The method is expected to serve as an effective tool of the particle analysis on nuclear safeguards environmental samples.
Nakamichi, Hideo; Beddingfield, D. H.*; Nakamura, Hironobu; Mukai, Yasunobu; Kurita, Tsutomu
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 9 Pages, 2010/12
The Distributed Source-Term Analysis (DSTA) technique provides user with knowledge of the location of neutron-producing materials and the magnitude of activity in the large volume to be evaluated. We aimed that this technique can be used to identify the physical location and activity of holdup in the glove box. By using relationships between source and volume determined by MCNPX calculation, we developed a Glove Box Cleanout Assistance Tool (BCAT). The tool can be applied to the operator during cleanout to increase recovered material, to decrease unmeasured inventory, and to perform the cleanout effectively in order to reduce operator radiation-exposure. In order to demonstrate the BCAT performance, neutron measurements were performed around actual glovebox environment. As a result of the analysis, not only the more concrete holdup locations and the activities that we experimentally estimate the place to recover were determined, but also the new hidden holdup could be found out. This knowledge provides new effective cleanout methodology. Consequently, it is expected that the nuclear material accountancy for entire bulk-handling facility can be improved.
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.
Inoue, Naoko; Kawakubo, Yoko; Seya, Michio; Suzuki, Mitsutoshi; Kuno, Yusuke; Senzaki, Masao
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 9 Pages, 2010/12
The GIF Proliferation Resistance and Physical Protection (PR&PP) evaluation methodology has been developed for GEN IV nuclear energy systems under the international consensus. The PR&PP WG activities include development of the measures and metrics; establishment of the framework of PR&PP evaluation, the demonstration study using Example Sodium Fast Reactor (ESFR), which included the development of three evaluation approaches; the Case study using ESFR and four kinds of threat scenarios; the joint study with GIF System Steering Committees (SSCs) of the six reactor design concepts; and the harmonization study with the IAEA's International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO). This paper reviews the status of GIF PR&PP studies and identifies the challenges and directions for applying the methodology to evaluate future nuclear energy systems in Japan.
-raysHajima, Ryoichi; Sawamura, Masaru; Nagai, Ryoji; Nishimori, Nobuyuki; Hayakawa, Takehito; Shizuma, Toshiyuki; Kikuzawa, Nobuhiro; Fujiwara, Mamoru; Seya, Michio
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 9 Pages, 2010/12
We have proposed a nondestructive assay for Pu-239 in spent nuclear fuel assembly under water using nuclear resonance fluorescence with energy tunable monochromatic -rays generated by Compton scattering of laser photons and high energy electrons. By using -ray beams of energy of about 2 MeV with good penetrability, one can detect Pu-239 in a spent fuel assembly kept in a water pool from outside the pool wall. In order to realize such -ray source, we are developing technologies for energy-recovery linac (ERL), which is able to generate small-emittance and high-current electron beams. Here we report development status of an electron gun, superconducting cavity and also we present a design of high-flux -ray source based on an ERL.
-raysHayakawa, Takehito; Shizuma, Toshiyuki; Hajima, Ryoichi; Kikuzawa, Nobuhiro; Fujiwara, Mamoru; Seya, Michio
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 5 Pages, 2010/12
We have proposed a nondestructive assay for Pu-239 in spent fuel assembly using nuclear resonance fluorescence with energy tunable monochromatic -rays generated by Compton scattering of laser photons and high energy electrons. This method has advantages that one can detect Pu-239 in a fuel assembly kept in a water pool from outside the pool wall and that one can identify isotopes. We use the -ray beam with the energy of about 2 MeV and thereby we can detect isotopes though water shields with a thickness of several ten centimeters. We present the concept design of this system, the basic study, and detection accuracy of Pu-239 derived from simulation calculation results using a code GEANT4.
-rays to material accountancy and safeguards verification for future nuclear fuel cycle facilitiesSeya, Michio; Hajima, Ryoichi; Nishimori, Nobuyuki; Kikuzawa, Nobuhiro; Hayakawa, Takehito; Shizuma, Toshiyuki; Fujiwara, Mamoru
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-31-Kai Nenji Taikai Rombunshu (CD-ROM), 9 Pages, 2010/12
Energy-recovery linac based laser Compton scattering (LCS) X/-ray sources have possibilities of various applications to non-destructive assay (NDA) in material accountancy and safeguards verification for future nuclear fuel cycle (FNFC) facilities with advantageous features of very high intensity, monochromaticy and tunability of energy. A LCS-X-ray source with energy of 110-130 keV could be applied to a fast hybrid K-edge densitometer, and a LCS--ray source with energy of 1-3 MeV to a NDA system of Pu (and actinide) in spent nuclear fuel and high-level active waste such as hull or vitrified waste by NRF (nuclear resonance fluorescence) method. The LCS--ray source with energy of 1-3 MeV could be applied to isotopic analysis of Pu etc. for solution, solid and powder samples after nuclear resonance cross section data of actinides is prepared. Also we present an idea of actual deployment of NDA systems using LCS-X/-ray sources in a hypothetical FNFC facility.