Influence of clay-doped water on permeability in granite rock mass

Nara, Yoshitaka*; Kashiwaya, Koki*; Oketani, Kazuki*; Fujii, Hirokazu*; Zhao, Y.*; Kato, Masaji*; Aoyagi, Kazuhei; Ozaki, Yusuke; Matsui, Hiroya; Kono, Masanori*

Zairyo, 73(3), p.220 - 225, 2024/03

https://doi.org/10.2472/jsms.73.220

The fractures in the rock are the main pass of groundwater flow and solute transport. The filling of fine-grained particle, such as clay minerals, was confirmed to decrease the permeability of rock by laboratory experiment. This research aimed to verify the occurrence of the phenomena in the field. The water containing the clay minerals was injected into the rock at the 200m stage of the Mizunami Underground research laboratory. The hydraulic conductivity decreased two order before and after the injection. This result suggested that the decrease of hydraulic conductivity by the filling of fine-grained particle in the fractures occurred in the real field.

Progress report of Japanese simulation research projects using the high-performance computer system Helios in the International Fusion Energy Research Centre

Ishizawa, Akihiro*; Idomura, Yasuhiro; Imadera, Kenji*; Kasuya, Naohiro*; Kanno, Ryutaro*; Satake, Shinsuke*; Tatsuno, Tomoya*; Nakata, Motoki*; Nunami, Masanori*; Maeyama, Shinya*; et al.

Purazuma, Kaku Yugo Gakkai-Shi, 92(3), p.157 - 210, 2016/03

http://www.jspf.or.jp/Journal/PDF_JSPF/jspf2016_03/jspf2016_03-157.pdf

The high-performance computer system Helios which is located at The Computational Simulation Centre (CSC) in The International Fusion Energy Research Centre (IFERC) started its operation in January 2012 under the Broader Approach (BA) agreement between Japan and the EU. The Helios system has been used for magnetised fusion related simulation studies in the EU and Japan and has kept high average usage rate. As a result, the Helios system has contributed to many research products in a wide range of research areas from core plasma physics to reactor material and reactor engineering. This project review gives a short catalogue of domestic simulation research projects. First, we outline the IFERC-CSC project. After that, shown are objectives of the research projects, numerical schemes used in simulation codes, obtained results and necessary computations in future.

Corrosion-erosion test of SS316L grain boundary engineering materials (GBEM) in lead bismuth flowing loop

Saito, Shigeru; Kikuchi, Kenji*; Hamaguchi, Dai; Tezuka, Masao*; Miyagi, Masanori*; Kokawa, Hiroyuki*; Watanabe, Seiichi*

Journal of Nuclear Materials, 431(1-3), p.91 - 96, 2012/12

https://doi.org/10.1016/j.jnucmat.2011.11.040

To evaluate lifetime of structural materials for ADS, corrosion tests in LBE have been done at JAEA. The corrosion test was performed by using JAEA lead-bismuth flowing loop (JLBL-1). Experimental condition was as follows; The temperature of high and low temperature parts of the loop were 450C and 350C, respectively. Flowing velocity at the test specimens was about 1m/s. Plate type SS316L-BM and SS316L-GBEM were used as a specimens. After the 3,000 hours operation, the test specimens were cut and macroscopic observation was carried out. The result showed that both materials were intensively eroded. Corrosion depth and LBE penetration through grain boundaries of GBEM were smaller than these of 316SS-BM.

The Crystal structure of -Al(OH); Neutron diffraction measurements and ab initio calculations

Matsui, Masanori*; Komatsu, Kazuki*; Ikeda, Emi*; Sano, Asami; Goto, Hirotada*; Yagi, Takehiko*

American Mineralogist, 96(5-6), p.854 - 859, 2011/05

https://doi.org/10.2138/am.2011.3672

Neutron powder diffraction analyses of -Al(OD) revealed that the crystals are orthorhombic with space group 222, but not as reported previously by X-ray diffraction data. The initial lattice parameters and the atomic positions of both Al and O were taken from previous X-ray structural analyses for the structure, while the H atom positions were determined using ab initio calculations. The -Al(OH) structure possesses one relatively long and two short O-H...O hydrogen bonds. Ab initio calculations are also used to find that -Al(OH) with space group 222 transforms to another high pressure polymorph with space group at around 67 GPa, and that the two short hydrogen bonds in -Al(OH) become both symmetric through the transformation, in which the protons are located at the midpoints of the O...O hydrogen bonds.

Conceptual design of irradiation experimental device for 12 inch NTD-Si ingot in JRR-4 (Contract research)

Yagi, Masahiro; Watanabe, Masanori; Oyama, Koji; Komeda, Masao; Yamamoto, Kazuyoshi; Kashima, Yoichi

JAEA-Technology 2008-015, 91 Pages, 2008/03

JAEA-Technology-2008-015.pdf:22.92MB

The irradiation experimental device is designed by surveying analytically an irradiation condition to improve the neutron flux distribution of the radial direction on NTD-Si by using neutron transportation calculation Monte Carlo calculation code MCNP5 in order to develop neutron irradiation technology for the large-diameter silicon to 12 inches diameter at the maximum and an irradiation experiment will be performed in JRR-4. Thus the validity of the design technique of the irradiation device will be confirmed by this experiment. The irradiation experimental device is installed in the side of the core tank outer wall. A 12 inches silicon ingot of 60cm in height is irradiated in a reflector cover which surrounds the silicon ingot for increasing the flux. The silicon ingot is rotated during irradiation in order to require the condition of uniformly distributed thermal neutron flux over whole circumferences. A uniform irradiation condition was achieved by the pass-through core method, in which silicon ingot moved up and down with rotating. The condition was satisfied when silicon was covered with the thermal neutron filter, which is made from aluminum alloy of thickness of 2mm with natural boron element ratio of 1.5%, and was moved in the range from -42mm to 22mm for the center of the reactor core. The deviation of the Si-30 neutron absorption reaction rate was range from -3.2% to +5.3% in the intermediate volume of 40cm height and the neutron absorption reaction ratio of the circumference to the center was within 1.09 in the volume.

Research and development of high performance FBR core materials based on grain boundary engineering, 1; Trial production

Yamashita, Shinichiro; Yano, Yasuhide; Endo, Masaki*; Sakaguchi, Norihito*; Watanabe, Seiichi*; Miyagi, Masanori*; Sato, Shinya*; Sato, Yutaka*; Kokawa, Hiroyuki*; Kawai, Masayoshi*

no journal, , 

no abstracts in English

Electron heat transport analysis based on multi-scale simulations of electron- and ion-scale turbulence

Maeyama, Shinya; Watanabe, Tomohiko*; Idomura, Yasuhiro; Nakata, Motoki; Yagi, Masatoshi; Miyato, Naoaki; Nunami, Masanori*; Ishizawa, Akihiro*

no journal, , 

no abstracts in English

Multi-scale interactions between electron- and ion-scale turbulence and their effects on turbulent transport

Maeyama, Shinya; Watanabe, Tomohiko*; Idomura, Yasuhiro; Nakata, Motoki; Yagi, Masatoshi; Miyato, Naoaki; Nunami, Masanori*; Ishizawa, Akihiro*

no journal, , 

Application of the local seismic observation data for the common exercise in East Asia Regional NDC Workshop 2014

Fujii, Takanari*; Otsu, Takayuki*; Yagi, Masanori*; Yonezawa, Chushiro*; Jih, R.*; Kalinowski, M.*; Kang, I.-B.*; Chi, H.-C.*; Yamamoto, Yoichi; Kijima, Yuichi

no journal, , 

As a part of East Asia Regional NDC Workshop 2014 Mongolia (EARNW2014), the common exercise took place for the purpose of investigation from both of radionuclide and waveform analysis. Each participating NDC analyzed distributed fictitious RN data and real SHI data including non-IMS to find and investigate candidate event. The Japanese NDC-1 (JWA) tried to locate and discriminate the event utilizing local seismic observation data such as NECESSArray (NorthEast China Extended SeiSmic Array) and Korean local data kindly provided by KIGAM. Signals from this event were detected at many stations in such non-IMS network, and it indicated that these local/regional seismic data could contribute largely to estimate more reliable event location and discrimination.

Conceptual design about the 12-inch NTD-Si irradiation experimental device, 1; Study of uniform irradiation condition in NTD-Si ingot with large-diameter by nuclear analyses

Yagi, Masahiro; Kashima, Yoichi; Watanabe, Masanori; Yamamoto, Kazuyoshi

no journal, , 

The irradiation experimental device is designed by surveying analytically an irradiation condition to improve the neutron flux distribution of the diameter direction on NTD-Si by using Monte Carlo calculation code MCNP5 in order to develop neutron irradiation technology for the large-diameter silicon to 12 inches diameter at the maximum. Some irradiation experiment will be performed to confirm validity of the design technique in JRR-4 by using the experimental device for the 12 inches NTD-Si ingot. The experimental device is installed in the No.1 reactor pool side of the core tank outer wall. The 12 inches silicon of 60 cm in height is irradiated in a reflector cover which surrounds the silicon for increasing the flux. The silicon also is irradiated with rotating in order to require the condition of uniformly distributed thermal neutron flux over whole circumferences. A uniform irradiation condition was achieved by the pass-through core method with adding the thermal neutron filter which covers the silicon surface and is able to move up and down with rotating. The condition was satisfied when silicon was covered with the thermal neutron filter, which is made from aluminum alloy of 2 mm thickness with natural boron element ratio of 1.5%, and was run in the range from -42 mm to 22 mm for the center of the reactor core. The deviation of the Si-30 neutron absorption reaction rate was range from -3.22% to +5.27% in the intermediate volume of 40 cm height and the neutron absorption reaction ratio of the circumference to the center was within 1.09 in the volume.