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Journal Articles

Variation in formation and migration of self-interstitial atom clusters in electron irradiated copper with material purity and specimen preparation method

Sato, Yuki*; Abe, Yosuke; Okubo, Kenji*; Tanioka, Takashi*

Philosophical Magazine, 102(12), p.1152 - 1172, 2022/00

 Times Cited Count:0 Percentile:0(Materials Science, Multidisciplinary)

Using in situ observation with high-voltage electron microscope, one-dimensional (1D) migration of self-interstitial atom (SIA) clusters under electron irradiation at 300 K was surveyed for copper materials of five nominal purities and TEM specimens prepared with three methods. In standard (STD) specimens that were prepared through cold rolling and annealing in the vacuum, formation and 1D migration of SIA clusters did not depend much on the nominal purity. In non-annealed (NA) specimens, prepared from high purity materials through mechanical processing and electropolishing, defect structure was coarser than in STD specimens. Results of bulk annealing (BA) specimens showed that annealing of as-received block material had minor effects. Above results were discussed based on the hypothesis that impurity atoms existing in as-received materials and those induced by annealing act as traps for SIA clusters.

Journal Articles

Diffusion of tritiated water, $$^{137}$$Cs$$^{+}$$, and $$^{125}$$I$$^{-}$$ in compacted Ca-montmorillonite; Experimental and modeling approaches

Fukatsu, Yuta; Yotsuji, Kenji*; Okubo, Takahiro*; Tachi, Yukio

Applied Clay Science, 211, p.106176_1 - 106176_10, 2021/09

 Times Cited Count:10 Percentile:75.92(Chemistry, Physical)

JAEA Reports

Manufacturing miniature beam window for accelerator-driven system by cutting T91 steel

Watanabe, Nao; Sugawara, Takanori; Okubo, Nariaki; Nishihara, Kenji

JAEA-Technology 2020-026, 59 Pages, 2021/03

JAEA-Technology-2020-026.pdf:3.95MB

As a part of partitioning and transmutation technology development to reduce the burden of radioactive disposal, an investigation of Accelerator-Driven System (ADS) has been performed by Japan Atomic Energy Agency. A beam window, which is an inherent structure of the ADS, is planned to be made from T91 steel and its shape is a thin hemisphere shell. However, it had never been tried to manufacture it out of T91 steel. In this investigation, we tried to manufacture miniature beam windows by cutting T91 steel, and to discuss the process, manufacturing accuracy and geometry measurement methods. As a result, considering a real scale ADS beam window, a figure error between designing and machining ones is estimated to be about 5%. Its effect would be very small to the structural strength.

Journal Articles

New precise measurement of muonium hyperfine structure interval at J-PARC

Ueno, Yasuhiro*; Aoki, Masaharu*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; Ito, Takashi; Iwasaki, Masahiko*; et al.

Hyperfine Interactions, 238(1), p.14_1 - 14_6, 2017/11

 Times Cited Count:3 Percentile:86.59(Physics, Atomic, Molecular & Chemical)

Journal Articles

New muonium HFS measurements at J-PARC/MUSE

Strasser, P.*; Aoki, Masaharu*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; Ito, Takashi; Iwasaki, Masahiko*; et al.

Hyperfine Interactions, 237(1), p.124_1 - 124_9, 2016/12

 Times Cited Count:7 Percentile:90.97(Physics, Atomic, Molecular & Chemical)

Journal Articles

Diffusion model considering multiple pore structures in compacted bentonite

Yotsuji, Kenji; Tachi, Yukio; Okubo, Takahiro*

CMS Workshop Lectures, Vol.21, p.251 - 257, 2016/06

We have developed integrated sorption and diffusion model (ISD model) for assessment of diffusion parameters consistent with sorption processes in compacted bentonite. The ISD model gives consistent consideration to porewater chemistry, sorption and diffusion processes in compacted bentonite. The diffusion component based on the electric double layer theory and the homogeneous pore model in the ISD model accounts consistently for cation De overestimation and anion exclusion in narrow pores. The current ISD model can quantitatively account for diffusion of monovalent cations and anions, however, the model predictions disagree with diffusion data for multivalent cation and complex species. To improve the applicability of the model, it is necessary to consider the atomic level interactions between solute, solvent or clay mineral, and try that we apply the current ISD model to heterogeneous pore structure. In this study we try the application of the current ISD model to multiple pore structure. As results of numerical analysis of these models, the salinity dependence of effective diffusivity for the multi-pore model is comparatively smaller than that for the homogeneous pore model and the current diffusion model is improved.

Journal Articles

Radioactivity evaluation of the secondary sodium in DRACS of the Japan Sodium-cooled Fast Reactor

Sasaki, Kenji*; Naito, Katsuaki*; Oki, Shigeo; Okubo, Tsutomu; Kotake, Shoji*

Progress in Nuclear Science and Technology (Internet), 4, p.94 - 98, 2014/04

This paper evaluates the amount of activation of the secondary sodium in Direct Heat Exchanger (DHX) by neutrons leaked from the core, the radioactivity density, and the dose rate around the secondary sodium pipes in Direct Reactor Auxiliary Cooling System (DRACS) and confirms that the requirements in radioactivity free areas are satisfied by improving the exactness of calculation model with Monte Carlo Methodology.

Journal Articles

Development of superconducting proton linac for ADS

Ouchi, Nobuo; Akaoka, Nobuo*; Asano, Hiroyuki*; Chishiro, Etsuji; Namekawa, Yuya*; Suzuki, Hiroyuki*; Ueno, Tomoaki*; Noguchi, Shuichi*; Kako, Eiji*; Ouchi, Norihito*; et al.

Proceedings of 4th International Workshop on the Utilisation and Reliability of High Power Proton Accelerators, p.175 - 183, 2005/11

no abstracts in English

Journal Articles

Irradiation test for verification of PWR 48GWd/t high burnup fuel

Okubo, Tadatsune*; Tsukuda, Yoshiaki*; Kamimura, Katsuichiro*; Murai, Kenji*; Goto, Ken*; Doi, Soichi*; Senda, Yasuhide*; Kosaka, Yuji*; Kido, Toshiya*; Murata, Tamotsu*; et al.

Nihon Genshiryoku Gakkai-Shi, 43(9), p.906 - 915, 2001/09

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Performance test of the HTTR

Tanaka, Toshiyuki; Okubo, Minoru; Iyoku, Tatsuo; Kunitomi, Kazuhiko; Takeda, Takeshi; Sakaba, Nariaki; Saito, Kenji

Nihon Genshiryoku Gakkai-Shi, 41(6), p.686 - 698, 1999/00

 Times Cited Count:4 Percentile:34.81(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

In-situ coating device for JT-60

Obara, Kenjiro; Kawasaki, Kozo; Hiratsuka, Hajime; *; *; Miyo, Yasuhiko; Okubo, Minoru; Ota, Mitsuru

JAERI-M 88-117, 77 Pages, 1988/07

JAERI-M-88-117.pdf:2.72MB

no abstracts in English

Oral presentation

Study on Innovative Water Reactor for Flexible Fuel Cycle (FLWR), 8; Conceptual design of breeder type FLWR core using recovered uranium as blanket fuel

Uchikawa, Sadao; Nakano, Yoshihiro; Tatematsu, Kenji; Okubo, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Study on Innovative Water Reactor for Flexible Fuel Cycle (FLWR), 11; An Analysis on roles of breeder type FLWRs using enriched recovered uranium

Tatematsu, Kenji; Ishikawa, Nobuyuki; Uchikawa, Sadao; Okubo, Tsutomu

no journal, , 

In this study, the roles of breeder type FLWRs using enriched recovered uranium were quantitatively analyzed from the viewpoint of installed capacity of FLWRs, reprocessing plant capacity and the natural uranium consumption in Japanese future nuclear power generation systems. It became clear that the newly-designed breeder type FLWRs could shorten realization of the complete closed cycles to about 150 years.

Oral presentation

Study on Innovative Water Reactor for Flexible Fuel Cycle (FLWR), 10; Conceptual design of breeder type FLWR core with a breeding ratio of 1.1 for transitioning to long term sustainable fuel cycles

Uchikawa, Sadao; Okubo, Tsutomu; Nakano, Yoshihiro; Kobayashi, Noboru; Tatematsu, Kenji; Ishikawa, Nobuyuki

no journal, , 

no abstracts in English

Oral presentation

Shielding design of JSFR; Radioactivity evaluation of the secondary sodium in the DRACS

Sasaki, Kenji*; Naito, Katsuaki*; Oki, Shigeo; Okubo, Tsutomu; Kotake, Shoji*

no journal, , 

no abstracts in English

Oral presentation

Shielding design of JSFR; Evaluation of the ORNL sodium transmission measurements by using Monte Carlo code MCNP

Sasaki, Kenji*; Naito, Katsuaki*; Oki, Shigeo; Okubo, Tsutomu; Kotake, Shoji*

no journal, , 

no abstracts in English

Oral presentation

Estimation of water infiltration using ground temperature distribution at the downstream of the Mill Tailings Pond, Ningyo-toge Uranium Mine

Iwasaki, Keisuke*; Kimoto, Kazushi*; Okubo, Kenji*; Awai, Sohei*; Sakao, Ryota; Taki, Tomihiro

no journal, , 

no abstracts in English

Oral presentation

Investigation of the near surface damage layer induced by electric discharge machining in steel

Jiang, L.*; O'Rourke, B. E.*; Harada, Yoshihisa*; Takatsu, Shuhei*; Ito, Kenji*; Okubo, Masataka*; Hirade, Tetsuya; Uedono, Akira*; Suzuki, Ryoichi*; Takai, Kenichi*; et al.

no journal, , 

We are studying the depth dependence of the density of the defects induced by the electrical discharge machining (EDM) in SUS316L, using the electron probe microanalysis (EPMA), Positron annihilation lifetime spectroscopy (PALS) and X-ray diffraction (XRD). EPMA results show a large change in the composition over the first 10 $$mu$$m. This layer can be assumed to correspond to the recast layer. PALS and XRD results suggest a defect layer with a thickness of around 50 $$mu$$m. This depth can be assumed to correspond to the heat affected zone where dislocations and vacancy clusters exists. For PALS (and other methods) analysis, it is recommended to remove the topmost 100 $$mu$$m of the samples by chemical polishing after EDM.

Oral presentation

Post irradiation examination of the MEGAPIE samples at JAEA, 2

Saito, Shigeru; Kikuchi, Kenji*; Suzuki, Kazuhiro; Hatakeyama, Yuichi; Endo, Shinya; Suzuki, Miho; Okubo, Nariaki; Kondo, Keietsu

no journal, , 

The world's first megawatt-class lead-bismuth target, MEGAPIE (MEGAwatt Pilot Experiment), was dismantled and post irradiation examination (PIE) samples were prepared at PSI hot-lab. The samples were shipped to each institutions including JAEA. The samples were cut from the beam window (BW, T91) and the flow guide tube (FGT, SS316L). And all samples are prepared without LBE. The irradiation conditions of the specimens irradiated at SINQ target were as follows: proton energy was 580 MeV, irradiation temperatures were ranged from 251 to 341$$^{circ}$$C, and displacement damage levels were ranged from 0.16 to 1.57 dpa. PIE including SP (small punch) and three point bending tests were performed. SP tests were executed for T91 and SS316L specimens at R.T. in air condition. Specimen size for SP test with 2.4 mm steel-ball is 8 mm $$times$$ 8 mm $$times$$ 0.5 mm. T91 specimens were cut from the Spitze (triangle) sample and polished to thickness of 0.5 mm. The OM/SP specimens of SS316L were polished to thickness of 0.5 mm. Three point bending tests were executed for SS316L specimens at R.T. in air condition. The bend bar specimens of SS316L without notch were employed. Results of the SP tests and three point bending tests on the irradiated specimens will be presented at the workshop. Cross sectional observation on the Spitze sample and microstructural observation by TEM will be also reported.

Oral presentation

PSI SINQ specimen PIE at JAEA-WASTEF

Saito, Shigeru; Okubo, Nariaki; Endo, Shinya; Suzuki, Kazuhiro; Hatakeyama, Yuichi; Kikuchi, Kenji*

no journal, , 

To evaluate the lifetime of the beam window of an accelerator-driven transmutation system (ADS) and spallation neutron source, material irradiation programs, the STIP (SINQ target irradiation program, SINQ; Swiss spallation neutron source) and MEGAPIE (MEGAwatt Pilot Experiment), have been executed. Part of the specimens were transported to JAEA and post irradiation examination (PIE) of the specimens was carried out. In this presentation, in addition to representative results of the PIE, our experience and knowledge of irradiation experiments and PIE processes will be introduced. These information will be useful for high energy particle irradiation experiments and PIE planed under the frame work of RaDIATE.

27 (Records 1-20 displayed on this page)