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Tamura, Koji; Nakanishi, Ryuzo; Oba, Hironori; Karino, Takahiro; Shibata, Takuya; Taira, Takunori*; Wakaida, Ikuo
Journal of Nuclear Science and Technology, 61(8), p.1109 - 1116, 2024/08
Times Cited Count：2 Percentile：15.37(Nuclear Science & Technology)
ceramicsVauchy, R.; Hirooka, Shun; Watanabe, Masashi; Yokoyama, Keisuke; Sunaoshi, Takeo*; Yamada, Tadahisa*; Nakamichi, Shinya; Murakami, Tatsutoshi
Ceramics International, 49(2), p.3058 - 3065, 2023/01
Times Cited Count：11 Percentile：54.21(Materials Science, Ceramics)Ueta, Shohei; Imai, Yoshiyuki; Watanabe, Masashi; Segawa, Tomoomi; Yan, X.
International Journal of Applied Ceramic Technology, 20(1), p.261 - 265, 2023/01
Times Cited Count：6 Percentile：31.39(Materials Science, Ceramics)Tobita, Minoru*; Konda, Miki; Omori, Takeshi*; Nabatame, Tsutomu*; Onizawa, Takashi*; Kurosawa, Katsuaki*; Haraga, Tomoko; Aono, Ryuji; Mitsukai, Akina; Tsuchida, Daiki; et al.
JAEA-Data/Code 2022-007, 40 Pages, 2022/11
JAEA-Data-Code-2022-007.pdf:1.99MB
Radioactive wastes generated from nuclear research facilities in Japan Atomic Energy Agency are planning to be buried in the near surface disposal field. Therefore, it is required to establish the method to evaluate the radioactivity concentrations of radioactive wastes until the beginning of disposal. In order to contribute to this work, we collected and analyzed concrete, ash, ceramic and brick samples generated from JRR-3, JRR4 and JRTF facilities. In this report, we summarized the radioactivity concentrations of 24 radionuclides (
H, 
C, 
Cl, 
Ca, 
Co, 
Ni, 
Sr, 
Nb, 
Tc, 
Ag, 
I, 
Cs, 
Ba, 
Eu, 
Eu, 
Ho, 
U, 
U, Pu, 
Pu, 
Pu, 
Am, 
Am, 
Cm) which were obtained from radiochemical analysis of the samples in fiscal years 2020-2021.
Collaborative Laboratories for Advanced Decommissioning Science; Tokyo Institute of Technology*
JAEA-Review 2021-077, 217 Pages, 2022/03
JAEA-Review-2021-077.pdf:12.34MB
The Collaborative Laboratories for Advanced Decommissioning Science (CLADS), Japan Atomic Energy Agency (JAEA), had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project (hereafter referred to "the Project") in FY2020. The Project aims to contribute to solving problems in the nuclear energy field represented by the decommissioning of the Fukushima Daiichi Nuclear Power Station, Tokyo Electric Power Company Holdings, Inc. (TEPCO). For this purpose, intelligence was collected from all over the world, and basic research and human resource development were promoted by closely integrating/collaborating knowledge and experiences in various fields beyond the barrier of conventional organizations and research fields. The sponsor of the Project was moved from the Ministry of Education, Culture, Sports, Science and Technology to JAEA since the newly adopted proposals in FY2018. On this occasion, JAEA constructed a new research system where JAEA-academia collaboration is reinforced and medium-to-long term research/development and human resource development contributing to the decommissioning are stably and consecutively implemented. Among the adopted proposals in FY2019, this report summarizes the research results of the "Development of stable solidification technique of ALPS sediment wastes by apatite ceramics" conducted in FY2020. The present study aims to establish an apatite solidification process of radioactive sediment wastes, which were generated from the ALPS process manipulating the large amount of contaminated water from Fukushima Daiichi Nuclear Power Station. In FY2020, the synthetic scheme and elemental composition were updated to precipitation method to accept the actual ALPS sediment wastes in engineering scale. The synthesis of apatite or phosphate wastes and their molding conditions were surveyed, and the relations among elemental compositions, structures and chemical properties were clarified.
Tamura, Koji; Nakanishi, Ryuzo; Oba, Hironori; Taira, Takunori*; Wakaida, Ikuo
Japanese Journal of Applied Physics, 61(3), p.032003_1 - 032003_5, 2022/03
Times Cited Count：2 Percentile：11.79(Physics, Applied)Collaborative Laboratories for Advanced Decommissioning Science; Tokyo Institute of Technology*
JAEA-Review 2020-060, 116 Pages, 2021/02
JAEA-Review-2020-060.pdf:16.98MB
JAEA/CLADS had been conducting the Nuclear Energy Science & Technology and Human Resource Development Project in FY2019. Among the adopted proposals in FY2019, this report summarizes the research results of the "Development of Stable Solidification Technique of ALPS Sediment Wastes by Apatite Ceramics" conducted in FY2019.
Lambertin, D.*; Davy, C. A.*; Hauss, G.*; Planel, B.*; Marchand, B.*; Cantarel, V.
Proceedings of 1st International Conference on Innovation in Low-Carbon Cement and Concrete Technology (ILCCC 2019) (USB Flash Drive), 4 Pages, 2019/06
Composite materials made of geopolymer (GP) cement and organic liquids are useful to synthetize porosity-controlled media, for the management of radioactive organic liquid waste, or as phase change materials (PCM). Indeed, GP cements are able to integrate huge amounts of organic oils by direct emulsion in the fresh paste. The emulsion (GEOIL) remains stable during GP hardening. In this contribution, by using 3D X Ray micro Computed Tomography (micro CT) with a voxel size of 1 micron, we investigate the effect of formulation parameters (oil proportion, Si/Al molar ratio, surfactant) on the 3D oil droplet structure of GEOIL pastes. Samples are emulsified in the fresh state, and imaged in the hardened state. Porosity, oil droplet size distribution and mean distance between droplets are all determined quantitatively. It is observed that the presence of surfactant provides significantly smaller oil droplets. The increase in Si/Al ratio also decreases the oil droplet sizes, but to a lesser extent.
Ioki, Kimihiro*; Hiranai, Shinichi; Moriyama, Shinichi; Tanaka, Suguru*
Fusion Engineering and Design, 109-111(Part A), p.951 - 955, 2016/11
Times Cited Count：5 Percentile：37.64(Nuclear Science & Technology)A dummy load dissipates the RF power and is required to test and adjust a gyrotron or a transmission line. The most critical issue is long-term reliability in the vacuum and coolant boundary of the rotation mechanism for current large-scale dummy loads. A new design has been developed to use linear movement for the reflector assembly to mitigate the heat deposition concentration. The thickness distribution of the ceramic layer is carefully analyzed and optimized. A prototypical dummy load will be manufactured as the next step.
Seya, Michio; Kobayashi, Naoki; Naoi, Yosuke; Hajima, Ryoichi; Soyama, Kazuhiko; Kureta, Masatoshi; Nakamura, Hironobu; Harada, Hideo
Book of Abstracts, Presentations and Papers of Symposium on International Safeguards; Linking Strategy, Implementation and People (Internet), 8 Pages, 2015/03
JAEA-ISCN has been implementing basic development programs of the advanced NDA technologies for nuclear material (NM) since 2011JFY (Japanese Fiscal Year), which are (1) NRF (Nuclear resonance fluorescence) NDA technology using laser Compton scattered (LCS) 
-rays (intense mono-energetic -rays), (2) Alternative to He neutron detection technology using ZnS/BO
ceramic scintillator, and (3) NRD (Neutron resonance densitometry) using NRTA (Neutron resonance transmission analysis) and NRCA (Neutron resonance capture analysis). These programs are going to be finished in 2014JFY and have demonstration tests in February - March 2015.
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.
BO ceramic scintillator detector as an alternative to a He-gas-based detector for a plutonium canister assay systemNakamura, Tatsuya; Ozu, Akira; To, Kentaro; Sakasai, Kaoru; Suzuki, Hiroyuki; Honda, Katsunori; Birumachi, Atsushi; Ebine, Masumi; Yamagishi, Hideshi*; Takase, Misao; et al.
Nuclear Instruments and Methods in Physics Research A, 763, p.340 - 346, 2014/05
Times Cited Count：3 Percentile：25.15(Instruments & Instrumentation)A neutron-sensitive ZnS/BO ceramic scintillator detector was developed as an alternative to a He-gas-based detector for use in a plutonium canister assay system. The detector has a modular structure, with a flat ZnS/BOceramic scintillator strip that is installed diagonally inside a light-reflecting aluminium case with a square cross section. The prototype detectors, which have a neutron-sensitive area of 30 mm 
250 mm, exhibited a sensitivity of 21.7-23.4 
0.1 cps
nv for thermal neutrons, a Cs -ray sensitivity of 1.1-1.9 
0.2 10
and a count variation of less than 6% over the detector length. A trial experiment revealed a temperature coefficient of less than -0.24 0.05% / 
C over the temperature range of 20-50C.
O ceramics from precursor polymers by radiation curingWach, R.; Sugimoto, Masaki; Yoshikawa, Masahito
Key Engineering Materials, 317-318, p.573 - 576, 2006/08
no abstracts in English
O-SiO including CrPO
, Out-of-pile testsKulsartov, T. V.*; Hayashi, Kimio; Nakamichi, Masaru*; Afanasyev, S. E.*; Shestakov, V. P.*; Chikhray, Y. V.*; Kenzhin, E. A.*; Kolbaenkov, A. N.*
Fusion Engineering and Design, 81(1-7), p.701 - 705, 2006/02
Times Cited Count：50 Percentile：93.65(Nuclear Science & Technology)no abstracts in English
Baba, Shinichi; Nemoto, Makoto*; Sozawa, Shizuo; Yamaji, Masatoshi*; Ishihara, Masahiro; Sawa, Kazuhiro
JAERI-Tech 2005-055, 157 Pages, 2005/09
JAERI-Tech-2005-055.pdf:19.06MB
The Japan Atomic Energy Research Institute (JAERI) has been carrying out the research on radiation damage mechanism of heat-resistant ceramics composite materials, as one of the subjects of the innovative basic research on high temperature engineering using the High Temperature Engineering Test Reactor (HTTR). A series of preliminary irradiation tests is being made using the Japan Materials Testing Reactor (JMTR). The present report describes results of post-irradiation examinations so far on specimens irradiated in the second and third capsule, designated 98M-41A and 99M-30A, to fast neutron fluences of 1.010
m
(E
1MeV) at temperatures of 973K-1173K and 1273K-1473K. The PIE were conducted as the fundamental statistics index of the diametral dimensions for irradiated specimen, irradiation induced dimensional change rate and thermal expansion rate.
Serizawa, Hiroyuki; Kikuchi, Hironobu; Iwai, Takashi; Arai, Yasuo; Kurosawa, Makoto; Mimura, Hideaki; Abe, Jiro
JAERI-Tech 2005-039, 23 Pages, 2005/07
JAERI-Tech-2005-039.pdf:2.89MB
A high-temperature ultrasonic measuring system had been designed and installed in a glovebox (711-DGB) to study a mechanical property of nuclear fuel containing trans-uranium (TRU) elements. A figuration apparatus for the cylinder-type sample preparation had also been modified and installed in an established glovebox (142-D). The system consists of an ultrasonic probe, a heating furnace, cooling water-circulating system, a cooling air compressor, vacuum system, gas supplying system and control system. An A/D converter board and an pulsar/Receiver board for the measurement of wave velocity were installed in a personal computer. The apparatus was modified to install into the glovebox. Some safety functions were supplied to the control system. The shape and size of the sample was revised to minimize the amount of TRU elements for the use of the measurement. The maximum sample temperature is 1500 C. The performance of the installed apparatuses and the glovebox were confirmed through a series of tests.
O ceramics from precursor polymers by radiation curingWach, R.; Sugimoto, Masaki; Lam, N. D.; Yoshikawa, Masahito
Proceedings of 8th SPSJ International Polymer Conference (IPC 2005) (CD-ROM), 60 Pages, 2005/07
no abstracts in English
Shobuda, Yoshihiro; Chin, Y. H.*; Omi, Kazuhito*; Toyama, Takeshi*
Proceedings of 2005 Particle Accelerator Conference (PAC '05) (CD-ROM), p.1898 - 1900, 2005/00
At 3GeV RCS(Rapid Cycle Synchrotron) in J-PARC, the ceramic chamber is adopted to aviod the excess eddy current. This ceramic chamber is surrounded by Cu-stripes to supress the leak field caused by the beam. The inner surface of the chamber is coated with TiN to suppress the secondary electron emission. In order to discuss the beam instability, we have to calculate the impedance for this chamber. Previously, the impedance was calculated by replacing the Cu-stripes to the conducting beam pipe. In this paper we deal with Cu-stripes realistically, and compare the results with the previous results. The resistivity of Cu-stripes and the TiN are also considered.
Shibata, Taiju; Motohashi, Yoshinobu*; Ishihara, Masahiro; Baba, Shinichi; Ito, Tsutomu*; Sawa, Kazuhiro
Nihon Kikai Gakkai Kanto Shibu Ibaraki Koenkai (2004) Koen Rombunshu (No.040-3), p.63 - 64, 2004/09
no abstracts in English
Kikuchi, Makoto*; Motohashi, Yoshinobu*; Ito, Tsutomu*; Sakuma, Takaaki*; Shibata, Taiju; Baba, Shinichi; Ishihara, Masahiro; Sawa, Kazuhiro; Hojo, Tomohiro*; Tsuji, Nobumasa*
Nihon Kikai Gakkai Kanto Shibu Ibaraki Koenkai (2004) Koen Rombunshu (No.040-3), p.57 - 58, 2004/09
no abstracts in English
