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Koizumi, Mitsuo; Sakasai, Kaoru; Kureta, Masatoshi; Nakamura, Hironobu
Nihon Genshiryoku Gakkai-Shi ATOMO, 58(11), p.642 - 646, 2016/11
no abstracts in English
Nakamura, Hironobu; Mukai, Yasunobu; Tobita, Hiroshi; Nakamichi, Hideo; Ozu, Akira; Kureta, Masatoshi; Kurita, Tsutomu; Seya, Michio
Proceedings of 37th ESARDA Annual Meeting (Internet), p.45 - 53, 2015/08
JAEA conducted an R&D project to develop a new type of neutron detector using ZnS/BO ceramic scintillator (as an alternative neutron detector to He-3) with support of Japanese government. The design of the JAEAs alternative system (ASAS: Alternative Sample Assay System using ceramic scintillator tubes) refers basically to the INVS (INVentory Sample assay system) which is the passive type of neutron assay system equipped total 18 He-3 tubes and capable of measuring the small amount of Pu in the MOX powder or Pu nitrate solution in a vial for nuclear material accountancy and safeguards verification. In order to prove the alternative technology and the performance instead of He-3 detector, and to establish Pu measurement capability, JAEA developed and fabricated ASAS equipped 24 alternative ceramic scintillator tubes (which is equivalent to the same counting efficiency of INVS) and demonstrated. The demonstration activity implemented the confirmation of reproducibility about sample positioning, optimization of detector parameters, counting statistical uncertainty, stability check and figure of merit (FOM) using Cf check source and actual MOX powder in PCDF (Plutonium Conversion Development Facility). In addition, performance comparison between the current INVS and the ASAS was also implemented. In this paper, we present demonstration results with design information with Monte-Carlo simulation code (MCNP).
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 -rays, (3) Development of alternative to 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 -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.
Seya, Michio; Naoi, Yosuke; Kobayashi, Naoki; Nakamura, Takahisa; Hajima, Ryoichi; Soyama, Kazuhiko; Kureta, Masatoshi; Nakamura, Hironobu; Harada, Hideo
Kaku Busshitsu Kanri Gakkai (INMM) Nihon Shibu Dai-35-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2015/01
The Integrated Support Center for Nuclear Non-proliferation and Nuclear Security (ISCN) of Japan Atomic Energy Agency (JAEA) has been conducting (based on collaborations with JAEA other centers) the following basic technology development programs of advanced non-destructive detection/measurement of nuclear material for nuclear security and nuclear non-proliferation. (1) The demonstration test of the Pu-NDA system for spent fuel assembly using PNAR and SINRD (JAEA/USDOE(LANL) collaboration, completed in JFY2013), (2) Basic development of NDA technologies using laser Compton scattered -rays (Demonstration of an intense mono-energetic -ray source), (3) Development of alternative to He-3 neutron detection technology, (4) Development of neutron resonance densitometry (JAEA/JRC collaboration)This paper introduces above programs.
Nakamura, 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.
Mukai, 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.
Endo, Akira; Yamaguchi, Yasuhiro; Sumita, Kenji*
Journal of Nuclear Science and Technology, 40(8), p.628 - 630, 2003/08
Times Cited Count:4 Percentile:31.59(Nuclear Science & Technology)no abstracts in English
Kanno, Masaru; ; ; ;
JAERI-Tech 97-042, 53 Pages, 1997/09
no abstracts in English
Ozu, Akira; Kureta, Masatoshi; Kobayashi, Nozomi*; Takase, Misao*; Kurata, Noritaka*; Tobita, Hiroshi; Haruyama, Mitsuo; Nakamura, Tatsuya; Suzuki, Hiroyuki; Sakasai, Kaoru; et al.
no journal, ,
no abstracts in English
Sakasai, Kaoru; Nakamura, Tatsuya; To, Kentaro; Soyama, Kazuhiko
no journal, ,
After the simultaneous terrorist attacks on September 11, 2001 in the U.S., the supply for He-3 gas has stagnated. Therefore, development of alternative to the He-3 detectors has been conducted in a large neutron experiment facility such as J-PARC, where a lot of He-3 neutron detectors are required. In this report, the supply for He-3 gas in the world is over-viewed and the development status of the alternative detectors using wavelength-shifting fibers and scintillators in J-PARC is described.
Komeda, Masao; Maeda, Makoto; Tobita, Hiroshi; Ozu, Akira; Kureta, Masatoshi; Toh, Yosuke
no journal, ,
no abstracts in English
Kimura, Nobuaki; Matsui, Yoshinori; Tobita, Masahiro*; Nakamura, Jinichi; Yamaura, Takayuki
no journal, ,
Power transient tests for the fuels of light water reactors were to be carried out in the Japan Materials Testing Reactor (JMTR) using capsule-type irradiation test facilities, and the integrity of the fuels had been to be investigated by the tests. Prior to the irradiation tests of the fuels, evaluation of thermal-hydraulic behavior in the capsule using ACE-3D code were carried out. And more, the out-pile test facility, which had an electric heater pin instead of a test fuel pin, was designed and fabricated to simulate the capsules used in the power transient tests. Using this facility, necessary tests for the realization of the irradiation tests and the planning of the test methods were carried out. From these analytical and experimental results, it was confirmed that the power ramping tests for 1010 BWR fuel are able to achieve linear heat rate of 600W/cm in JMTR.
Lee, H.-J.; Rodriguez, D.; Rossi, F.; Koizumi, Mitsuo; Takahashi, Tone
no journal, ,
Oku, Takayuki
no journal, ,
We have been developing a He neutron spin filter (NSF) for the efficient utilization of pulsed neutrons, since the He NSF is effective for neutrons in the wide energy range. The He NSF is effective especially for neutrons with energy higher than several-tens-meV. It also can cover a large solid angle and polarize neutrons without deflecting them from their original trajectory, it is suitable for the analyzer for SANS and reflectometer instruments. In addition, the He NSF will be a key device in the application of recently developed magnetic field imaging technique by using polarized pulsed neutrons, since it can polarize a thick neutron beam without deteriorating projection image of the transmitted neutrons. In order to apply the He NSF to experiments at a pulsed neutron experimental facility such as the J-PARC, it is important to make the system stable and easy to setup and operate, because the system is located inside thick and bulky radiation shields for high energy gamma ray and neutrons. In this talk, we will report the development and application status of the He NSF at J-PARC MLF.
Shimizu, Haruki*; Mishima, Kenji*; Ino, Takashi*; Ichikawa, Go*; Tsuchikawa, Yusuke; Endo, Shunsuke
no journal, ,
no abstracts in English