Analytical surveillance on production methods of homogeneous and uniform solid materials from spent ion exchange residuum after ion coupled plasma volume-reduction process

Otani, Hiroshi; Mizui, Hiroyuki; Higashiura, Norikazu; Bando, Fumio*; Endo, Nobuyuki*; Yamagishi, Ryuichiro*; Kume, Kyo*

Heisei-25-Nendo Koeki Zaidan Hojin Wakasawan Enerugi Kenkyu Senta kenkyu Nempo, 16, P. 66, 2014/10

no abstracts in English

Analytical surveillance of the nuclear waste package processing of the spent ion-exchange resin residual

Otani, Hiroshi; Bando, Fumio*; Endo, Nobuyuki*

Heisei-24-Nendo Koeki Zaidan Hojin Wakasawan Enerugi Kenkyu Senta kenkyu Nempo, 15, P. 89, 2013/10

no abstracts in English

Document collection of the 25th Technical Special Committee on Fugen Decommissioning

Kutsuna, Hideki; Otani, Hiroshi; Nakamura, Yasuyuki

JAEA-Review 2012-025, 30 Pages, 2012/07

JAEA-Review-2012-025.pdf:12.45MB

Fugen Nuclear Power Plant was reorganized to Fugen Decommissioning Engineering Center and started dismantling removal work of the facilities on February 12, 2008. In planning and carrying out our decommissioning technical development, "Technical special committee on Fugen decommissioning", which consists of the members well-informed, is established, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials "Current Situation of Fugen Decommissioning", "Basic Test for Making Waste Body for Spent Resin disposal", "Current Status and Future Plan on Laser Cutting Method", presented in the 25th Technical special committee on Fugen decommissioning which was held on March 16, 2012.

Document collection of the 23rd Technical Special Committee on Fugen Decommissioning

Otani, Hiroshi; Hayashi, Hirokazu; Kawagoe, Shinji; Hamada, Nobuyuki; Nakamura, Yasuyuki

JAEA-Review 2011-026, 41 Pages, 2011/07

JAEA-Review-2011-026.pdf:7.38MB

In planning and carrying out our decommissioning technical development, "Technical special committee on Fugen decommissioning", which consists of the members well-informed, is established, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials "Current Situation of Fugen Decommissioning", "Preparatory Situation for Operation of Clearance System", "Examined Situation of Nuclear Reactor Dismantlement Technology" of the 23rd Technical special committee on Fugen decommissioning which held on March 11, 2011.

Angle-resolved photoemission spectroscopy study of PrFeAsO; Comparison with LaFePO

Nishi, Ichiro*; Ishikado, Motoyuki; Ideta, Shinichiro*; Malaeb, W.*; Yoshida, Teppei*; Fujimori, Atsushi*; Kotani, Yoshinori*; Kubota, Masato*; Ono, Kanta*; Yi, M.*; et al.

Physical Review B, 84(1), p.014504_1 - 014504_5, 2011/07

https://doi.org/10.1103/PhysRevB.84.014504

We have performed an angle-resolved photoemission spectroscopy (ARPES) study of the iron-based superconductor PrFeAsO and examined the Fermi surfaces and band dispersions near the fermi level. Heavily hole-doped electronic states have been observed due to the polar nature of the cleaved surfaces. Nevertheless, we have found that the ARPES spectra basically agree with band dispersions calculated in the local density approximation (LDA) if the bandwidth is reduced by a factor of 2.5 and then the chemical potential is lowered by 70 meV. Comparison with previous ARPES results on LaFePO reveals that the energy positions of the - and -derived bands are considerably different between the two materials, which we attribute to the different pnictogen height as predicted by the LDA calculation.

Neutron powder diffraction and difference maximum entropy method analysis of protium- and deuterium-dissolved BaSnInO

Nagasaki, Takanori*; Shiotani, Shinya*; Igawa, Naoki; Yoshino, Masahito*; Iwasaki, Kota*; Fukazawa, Hiroshi; Utsumi, Wataru

Journal of Solid State Chemistry, 182(10), p.2632 - 2639, 2009/10

https://doi.org/10.1016/j.jssc.2009.06.024

We propose a new method, a difference maximum entropy method (MEM) analysis of the neutron diffraction data, for revealing the detailed structure around hydrogen atoms in proton-conducting oxides. This MEM analysis uses the differences between the structure factors of protium- and deuterium-dissolved crystals. Simulations demonstrate that it not only provides the distribution of hydrogen atoms alone, but also improves the spatial resolution of MEM mapping around hydrogen atoms. Applied to actual diffraction data of protium- and deuterium-dissolved BaSnInO at 9 K, difference MEM analysis reveals that O-D bonds mostly tilt towards the second nearest oxygen atoms, and that the distributions of deuterium and oxygen atoms are probably insignificant in interstitial regions.

An Experimental validation of the guideline for inelastic design analysis through structural model tests

Watanabe, Daigo*; Chuman, Yasuharu*; Otani, Tomomi*; Shibamoto, Hiroshi*; Inoue, Kazuhiko*; Kasahara, Naoto

Nuclear Engineering and Design, 238(2), p.389 - 398, 2008/02

https://doi.org/10.1016/j.nucengdes.2006.09.021

In this paper, the inelastic analysis procedures for the improved design of future fast breeder reactors were validated through the structural model tests and the evaluation of the experimental results by the inelastic analyses. First, a thermal fatigue test of a 316FR hollow cylinder with two longitudinal weldments was conducted under the condition of combined constant axial load and cyclic movement of axial temperature distribution, which simulated the loading condition near the free surface of coolant sodium in the main vessel of fast breeder reactors (FBRs). Second, the inelastic analyses were carried out in accordance with the recommended procedure by using the measured results of oscillating temperature distribution. Finally, the results of inelastic analyses were compared with the experimental results and it was validated that the recommended practice gave a conservative result for the deformation and a good estimation of strain range for the fatigue life evaluation.

Applicability of the system based code concept to the life-cycle design optimization of nuclear components

Asayama, Tai; Shibamoto, Hiroshi*; Otani, Tomomi*; Morishita, Masaki

Proceedings of 15th International Conference on Nuclear Engineering (ICONE-15) (CD-ROM), 6 Pages, 2007/04

https://doi.org/10.1299/jsmeicone.2007.15._ICONE1510_430

The System Based Code concept intends to optimize margins for nuclear plant component throughout the service period, by offering methodologies to determine appropriate margins corresponding to various technical items, so that a total margin of the component is at a desired level. The authors have shown that this concept can successfully be applied to the design of relatively simple components of nozzles and end-caps. This paper explores the possibility of applying the concept of the System Based Code to more complex components whose design is directly connected to the design of the plant as a whole. As such example, a vessel equivalent to that of a regenerative heat exchanger of light water reactors was postulated. It was concluded that the concept could contribute to optimize the design of actual complicated components to the regions beyond the current codes and standards allow.

Prediction of inelastic stress-strain behavior of spherical tube sheet

Igari, Toshihide*; Takao, Nobuyuki*; Otani, Tomomi*; Shibamoto, Hiroshi; Kasahara, Naoto

Nihon Kikai Gakkai 2006-Nendo Nenji Taikai Koen Rombunshu, Vol.1, p.957 - 958, 2006/09

no abstracts in English

Measurement of thermal ratcheting strain on the structures by the laser speckle method

Watanabe, Daigo*; Chuman, Yasuharu*; Otani, Tomomi*; Shibamoto, Hiroshi; Inoue, Kazuhiko*; Kasahara, Naoto

Proceedings of 2006 ASME Pressure Vessels and Piping Division Conference (PVP 2006)/International Council on Pressure Vessel Technology (ICPVT-11) (CD-ROM), 7 Pages, 2006/00

Prevention of thermal ratcheting is an important problem for high temperature components of fast breeder reactors that are subjected to cyclic thermal loads. To clarify ratcheting behaviors, structural model tests were planned. Strain measurement is important for understanding the thermal ratcheting phenomenon, however the conventional measurement by strain gauge is difficult at high temperature. Then, Laser speckle strain measurement system using the dual-beam set-up was developed to apply to high temperature structural model tests. This system was applied to the thermal ratcheting tests, which demonstrated the actual operative conditions of reactor vessels. Through comparison with uniaxial test results obtained by extensometers, the laser speckle method was verified. Measured data of structural model tests were utilized to certify the guidelines of inelastic analysis for design, which provide prediction method of strain in components of fast reactor.