Mizunami Underground Research Laboratory Project, Annual report for fiscal year 2012

Hama, Katsuhiro; Mikake, Shinichiro; Nishio, Kazuhisa; Matsuoka, Toshiyuki; Ishibashi, Masayuki; Sasao, Eiji; Hikima, Ryoichi*; Tanno, Takeo*; Sanada, Hiroyuki; Onoe, Hironori; et al.

JAEA-Review 2013-050, 114 Pages, 2014/02

JAEA-Review-2013-050.pdf:19.95MB

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 2012. This report presents the results of the investigations, construction and collaboration studies in fiscal year 2012, as a part of the Phase II and Phase III based on the MIU Master Plan updated in 2010.

Mizunami Underground Research Laboratory Project, Plan for fiscal year 2012

Kunimaru, Takanori; Mikake, Shinichiro; Nishio, Kazuhisa; Tsuruta, Tadahiko; Matsuoka, Toshiyuki; Ishibashi, Masayuki; Kuboshima, Koji; Takeuchi, Ryuji; Mizuno, Takashi; Sato, Toshinori; et al.

JAEA-Review 2012-028, 31 Pages, 2012/08

JAEA-Review-2012-028.pdf:3.86MB

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 is planned in three overlapping phases; Surface-based Investigation Phase (Phase I), Construction Phase (Phase II) and Operation Phase (Phase III). Currently, the project is under the Construction Phase and the Operation Phase. This document introduces the research and development activities planned for 2012 fiscal year based on the MIU Master Plan updated in 2010, construction plan and research collaboration plan, etc.

Evaluating techniques and phenomena of Stress Corrosion Cracking (SCC) in Light Water Reactors (LWRs); SCC evaluating techniques for predicting core internal and pipe aging of LWRs, technical data collection (Contract research)

Yamamoto, Masahiro; Kato, Chiaki; Sato, Tomonori; Nakano, Junichi; Ugachi, Hirokazu; Tsukada, Takashi; Kaji, Yoshiyuki; Tsujikawa, Shigeo*; Hattori, Shigeo*; Yoshii, Tsuguyasu*; et al.

JAEA-Review 2012-007, 404 Pages, 2012/03

JAEA-Review-2012-007.pdf:36.72MB

There are many LWRs which have been operated for more than 20 years in Japan and it is expected that technique corresponding to aging plants are necessary established for safety operation in LWRs. A lot of troubles related to SCC are reported and many investigations are concerned with SCC mechanism and technical evaluation. In this paper, those research data were collected as possible widely and reviewed systematically. Current circumstances concerned with SCC in LWRs were reviewed specifically as follows: SCC incidents, SCC evaluation methods for crack initiation and propagation, the investigations concerned with SCC mechanism and monitoring technique for corrosive environment. Influences with reactor types (BWR, PWR), materials (stainless steels, Ni alloys) and SCC evaluating methods (laboratories and actual plants) were summarized as graphs and tables easy to understand in common/difference points concerned with SCC. From these arranged results, future themes were considered and remarked SCC phenomenon was summarized in actual plants. As for SCC evaluations under the accelerate conditions in the laboratory test, it was suggested that a computational prediction and modeling including statistical technique and microscopic analysis in crack initiation were important. Furthermore it was suggested that monitoring techniques predicting SCC initiation and grasping plant circumstance in operation and feasibility in actual plants were important.

TEM observation of growth process of zirconium hydride in zircaloy-4 during hydrogen ion implantation

Shinohara, Yasunari*; Abe, Hiroaki*; Iwai, Takeo*; Sekimura, Naoto*; Kido, Toshiya*; Yamamoto, Hiroyuki; Taguchi, Tomitsugu

Journal of Nuclear Science and Technology, 46(6), p.564 - 571, 2009/06

https://doi.org/10.3327/jnst.46.564

observation during hydrogen ion implantation was performed with a TEM installed in an ion accelerator to investigate the growth process of Zr hydride in Zicaloy-4. To clarify the effect of radiation damage, some samples were irradiated with 4 MeV Ni ions prior to hydrogen implantation. Growth processes of Zr hydrides accompanying the formation of dislocations were observed. The crystallographic relationship between the Zr matrix and Zr hydrides was identical with that found in previous studies: inter- and intragranular hydrides exhibiting a tendency to grow in the 110 direction. This growth can be attributed to a shear mechanism. In specimens preirradiated with Ni ions, the growth rate of hydrides was suppressed, but the growth direction was not affected by radiation defects. It was also confirmed that the black spots induced by Ni ion irradiation grew during hydrogen ion implantation, suggesting the formation of hydrides at the defects.

Secondary electron emission yields from the J-PARC RCS vacuum components

Yamamoto, Kazami; Shibata, Takeo*; Ogiwara, Norio; Kinsho, Michikazu

Vacuum, 81(6), p.788 - 792, 2007/02

https://doi.org/10.1016/j.vacuum.2005.11.052

The J-PARC 3GeV Rapid-Cycling Synchrotron (RCS) is required to provide 1MW pulsed protons to the spallation neutron target and the 50 GeV main ring. Since the acceleration period is set at a repetition rate of 25Hz, the eddy current effect due to such rapid repetition magnetic field is a big issue (i.e. the perturbation of the magnetic field and the heating owing to the ohmic loss) in the metal duct. Therefore, we choose the ceramics duct in the magnets in order to avoid the eddy current effect. But the total secondary electron emission yield (SEY) from the ceramics surface is larger than the metal one. In order to reduce these undesirable electron emitted from the chamber surface, Titanium Nitride (TiN) is coated on the inside surface of the chambers. We measured SEY from TiN coating surface with various conditions. We further investigated Diamond Like Carbon coating to search the possibility of another coating. The results of these measurements are shown.

Swelling behavior of F82H steel irradiated by triple/dual ion beams

Wakai, Eiichi; Kikuchi, Kenji; Yamamoto, Shunya; Aruga, Takeo; Ando, Masami; Tanigawa, Hiroyasu; Taguchi, Tomitsugu; Sawai, Tomotsugu; Oka, Keiichiro*; Onuki, Somei*

Journal of Nuclear Materials, 318, p.267 - 273, 2003/05

https://doi.org/10.1016/S0022-3115(03)00122-3

no abstracts in English

In-situ irradiation test of mica substrate bolometer at the JMTR reactor for the ITER diagnostics

Nishitani, Takeo; Shikama, Tatsuo*; Reichle, R.*; Hodgson, E. R.*; Ishitsuka, Etsuo; Kasai, Satoshi; Yamamoto, Shin

Fusion Engineering and Design, 63-64, p.437 - 441, 2002/12

https://doi.org/10.1016/S0920-3796(02)00126-6

no abstracts in English

Effects of triple ion beams in ferritic/martensitic steel on swelling behavior

Wakai, Eiichi; Sawai, Tomotsugu; Furuya, Kazuyuki; Naito, Akira; Aruga, Takeo; Kikuchi, Kenji; Yamashita, Shinichiro*; Onuki, Somei*; Yamamoto, Shunya; Naramoto, Hiroshi; et al.

Journal of Nuclear Materials, 307-311(Part.1), p.278 - 282, 2002/12

https://doi.org/10.1016/S0022-3115(02)01076-0

no abstracts in English

Irradiation effects on plasma diagnostic components, 2

Nishitani, Takeo; Shikama, Tatsuo*; Sugie, Tatsuo; Kasai, Satoshi; Ishitsuka, Etsuo; Kawamura, Hiroshi; Kakuta, Tsunemi; Yagi, Toshiaki; Tanaka, Shigeru; Narui, Makoto*; et al.

JAERI-Research 2002-007, 149 Pages, 2002/03

JAERI-Research-2002-007.pdf:8.08MB

no abstracts in English

Effects of co-implanted oxygen or aluminum atoms on hydrogen migration and damage structure in multiple-beam irradiated AlO

Katano, Yoshio*; Aruga, Takeo; Yamamoto, Shunya; Nakazawa, Tetsuya; Yamaki, Daiju; Noda, Kenji

Journal of Nuclear Materials, 283-287(Part.2), p.942 - 946, 2000/12

https://doi.org/10.1016/S0022-3115(00)00163-X

no abstracts in English