Soundness survey of cooling tower of Utility Cooling Loop (UCL Cooling Tower) in JMTR

Oto, Tsutomu; Asano, Norikazu; Kawamata, Takanori; Yanai, Tomohiro; Nishimura, Arashi; Araki, Daisuke; Otsuka, Kaoru; Takabe, Yugo; Otsuka, Noriaki; Kojima, Keidai; et al.

JAEA-Review 2020-018, 66 Pages, 2020/11

JAEA-Review-2020-018.pdf:8.87MB

A collapse event of the cooling tower of secondary cooling system in the JMTR (Japan Materials Testing Reactor) was caused by the strong wind of Typhoon No.15 on September 9, 2019. The cause of the collapse of the cooling tower was investigated and analyzed. As the result, it was identified that four causes occurred in combination. Thus, the soundness of the cooling tower of Utility Cooling Loop (UCL cooling tower), which is a wooden cooling tower installed at the same period as the cooling tower of secondary cooling system, was investigated. The items of soundness survey are to grasp the operation conditions of the UCL cooling tower, to confirm the degradation of structural materials, the inspection items and inspection status of the UCL cooling tower, and to investigate the past meteorological data. As the results of soundness survey of the UCL cooling tower, the improvement of inspection items of the UCL cooling tower was carried out and the replacement and repair of the structural materials of the UCL cooling tower were planned for safe maintenance and management of this facility. And the renewal plan of new cooling tower was created to replace the existing UCL cooling tower. This report is summarized the soundness survey of the UCL cooling tower.

Preliminary test of the EA-AGE3 system for C measurement of CaCO samples and coral-based estimation of marine reservoir correction in the Ogasawara Islands, Northwestern Subtropical Pacific

Kokubu, Yoko; Mitsuguchi, Takehiro*; Watanabe, Takahiro; Yamada, Tsutomu*; Asami, Ryuji*; Iryu, Yasufumi*

Radiocarbon, 61(5), p.1593 - 1601, 2019/10

https://doi.org/10.1017/RDC.2019.69

We performed C measurements of two fossil and one modern corals using a combined system of an elemental analyzer and an automated graphitization equipment AGE3 (EA-AGE3 system) and JAEA-AMS-TONO. The C concentrations (pMC values) of mid-Holocene Okinawa corals obtained by our EA-AGE3 system appear to be slightly higher than those obtained by the conventional graphitization method using phosphoric acid. The pMC increase in our EA-AGE3 system may result in significant underestimation of C age especially for older samples (e.g., 10,000 BP); however, the pMC increase is negligible in C measurements of modern or recent samples. We applied the EA-AGE3 method to the pre- and post-bomb annual-band samples from the modern Ogasawara coral for C measurements. On the basis of the pre-bomb coral C data, we estimated marine reservoir correction (R) around Ogasawara Islands and its stability between 1900 and 1950 AD.

Criticality safety evaluation for the direct disposal of used nuclear fuel; preparation of data for burnup credit evaluation (Contract research)

Yamamoto, Kento*; Akie, Hiroshi; Suyama, Kenya; Hosoyamada, Ryuji*

JAEA-Technology 2015-019, 110 Pages, 2015/10

JAEA-Technology-2015-019.pdf:3.67MB

In the direct disposal of used nuclear fuel (UNF), criticality safety evaluation is one of the important issues since UNF contains some amount of fissile material. The recent development of higher-enrichment fuel has enhanced the benefit of the application of Burnup Credit. In the present study, the effects of the several parameters on the reactivity of disposal canister model were evaluated for used PWR fuel. The parameters are relevant to the uncertainties of depletion calculation code, irradiation history, and axial and horizontal burnup distribution, which are known to be important effect in the criticality safety evaluation adopting burnup credit. The latest data or methodology was adopted in this evaluation, based on the various latest studies. The appropriate margin of neutron multiplication factor in the criticality safety evaluation for UNF can be determined by adopting the methodology described in the present study.

Mizunami Underground Research Laboratory Project, Annual report for fiscal year 2013

Hama, Katsuhiro; Mikake, Shinichiro; Nishio, Kazuhisa; Kawamoto, Koji; Yamada, Nobuto; Ishibashi, Masayuki; Murakami, Hiroaki; Matsuoka, Toshiyuki; Sasao, Eiji; Sanada, Hiroyuki; et al.

JAEA-Review 2014-038, 137 Pages, 2014/12

JAEA-Review-2014-038.pdf:162.61MB

Japan Atomic Energy Agency (JAEA) at Tono Geoscience Center (TGC) is pursuing a geoscientific research and development project namely the Mizunami Underground Research Laboratory (MIU) Project in crystalline rock environment in order to construct scientific and technological basis for geological disposal of High-level Radioactive Waste (HLW). The MIU Project has three overlapping phases: Surface-based Investigation phase (Phase I), Construction phase (Phase II), and Operation phase (Phase III). The MIU Project has been ongoing the Phase II and the Phase III in fiscal year 2013. This report presents the results of the investigations, construction and collaboration studies in fiscal year 2013, as a part of the Phase II and Phase III based on the MIU Master Plan updated in 2010.

Results of pilot borehole investigation in -500m access/research gallery-north (12MI27 and 12MI33 boreholes)

Tsuyuguchi, Koji; Kuroiwa, Hiroshi; Kawamoto, Koji; Yamada, Nobuto; Onuki, Kenji; Iwatsuki, Teruki; Takeuchi, Ryuji; Ogata, Nobuhisa; Suto, Masahiro; Mikake, Shinichiro

JAEA-Technology 2013-044, 89 Pages, 2014/02

JAEA-Technology-2013-044.pdf:11.09MB
JAEA-Technology-2013-044-appendix(CD-ROM).zip:316.8MB

This document summarizes the data of pilot boreholes (12MI27, 12MI33) in the -500m Access/Research Gallery-North. The geological, hydraulic and geochemical data were obtained. In addition, groundwater monitoring system was installed in closure test gallery for the flooding test in phase III research. The results of investigation, biotite granite with medium to coarse-grained equigranular texture are characterized. Rock mass classification is B from CH class. Minor fault with fault gouge that was not presumed by an original model are observed in 12MI33. Density of fracture in 12MI27 near the Main-shaft fault tends to be compared to 12MI33. Water inflow in both boreholes is less. Permeability ranges from 4.8E-10 to 6.1E-09m/sec at the zone without alteration and with low inflow, from 1.1E-07 to 2.7E-07m/sec at the zone without alteration and with high inflow, respectively. Groundwater chemistry is rich in Na and Cl ion.

Thermochronological study of the dip-slip displacement and timing of initiation of the Atera fault

Yamada, Kunimi; Yasue, Kenichi; Iwano, Hideki*; Yamada, Ryuji*; Umeda, Koji; Omura, Kentaro*

Chishitsugaku Zasshi, 118(7), p.437 - 448, 2012/07

https://doi.org/10.5575/geosoc.2012.0015

Fission-track analyses for samples corrected from around the Atera fault indicated 2 conclusions. The dip-slip displacement of the Atera fault after Cretaceous is about 1 km. It is similar to the displacement of basement rocks or topography across the fault. These are consistent with previous studies that indicated the present Atera fault activity began after late Pliocene. The fracture zone along the fault was widely heated at about 20 Ma. It indicates that the fracture zone existed at the time and perhaps the paleo fault activity has already begun.

Effect of alumina on the enhancement of hydrogen production and the reduction of hydrogen peroxide in the -radiolysis of pure water and 0.4M HSO aqueous solution

Yamada, Reiji; Kumagai, Yuta; Nagaishi, Ryuji

International Journal of Hydrogen Energy, 36(18), p.11646 - 11653, 2011/09

https://doi.org/10.1016/j.ijhydene.2011.06.073

The H and HO produced by Co -radiation at room temperature were measured in pure water and 0.4M HSO aqueous solution with alumina powder. By increasing the addition of alumina powder, a strong reduction of HO concentrations in the solutions was obtained, and the final product H yields were correspondingly enhanced. These enhancement and reduction effects were diminished in the subsequent -radiation when irradiated alumina powder was used. The effects were reversibly restored by washing the irradiated powder with purified water. In 0.4M HSO solution with alumina powder, the H yields increased by increasing the absorbed dose rate in the region of 1-5 kGy/hr. The radiation-enhanced H production correlated with the reduction of HO concentration could be brought about by the reduction of HO molecules and OH radicals in the solutions due to alumina powder.

The Fermi chopper spectrometer 4SEASONS at J-PARC

Kajimoto, Ryoichi; Nakamura, Mitsutaka; Inamura, Yasuhiro; Mizuno, Fumio; Nakajima, Kenji; Kawamura, Seiko; Yokoo, Tetsuya*; Nakatani, Takeshi; Maruyama, Ryuji; Soyama, Kazuhiko; et al.

Journal of the Physical Society of Japan, 80(Suppl.B), p.SB025_1 - SB025_6, 2011/01

https://doi.org/10.1143/JPSJS.80SB.SB025

Development of production methods of the Sr-90/Y-90 source for hydrogen production experiments

Motoki, Riyozo; Aoki, Hiromichi; Uchida, Shoji; Nagaishi, Ryuji; Yamada, Reiji

JAEA-Technology 2008-014, 23 Pages, 2008/03

JAEA-Technology-2008-014.pdf:9.05MB

The study of producing hydrogen with a Sr-90/Y-90 source is planned to utilze the radioactive waste effectively. Therefore we developed two methods of caking Sr-90 and a catalyst for the production of hydrogen effectively. One is a method of caking SrTiO and TiO in a silica gel. And another is a method of caking SrSO and TiO in a silica gel. These solid matters are porous materials, which has a radiation resistant and chemical resistant. In addition, Y-90 which is a daughter nuclide of Sr-90 can be also used for hydrogen production.

Hydrogen production in the -radiolysis of aqueous sulfuric acid solutions containing AlO, SiO, TiO or ZrO fine particles

Yamada, Reiji; Nagaishi, Ryuji; Hatano, Yoshihiko; Yoshida, Zenko

International Journal of Hydrogen Energy, 33(3), p.929 - 936, 2008/02

https://doi.org/10.1016/j.ijhydene.2007.11.028

Hydrogen production was studied in the -radiolysis of aqueous HSO solutions containing oxide powder of AlO, SiO, TiO or ZrO. The observed yields of final product H increased with relative amounts of oxide powder in the solutions and exhibited a particular HSO concentration dependence, which was different for each oxide species and its amount. The addition of a small amount of CHOH to a HSO aqueous solution with oxide powder was quite effective for increasing the final product yields of H. The obtained results revealed that heterogeneous systems composed of oxide powder and aqueous HSO solution were more efficient for producing H molecules in -radiolysis than homogeneous systems without oxides.