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Journal Articles

Methods for regulating depth of corrosion fissures in simulated fastener holes of 7050-T7451 aluminum alloy

Aoyama, Takahito; Choudhary, S.*; Pandaleon, A.*; Burns, J. T.*; Kokaly, M.*; Restis, J.*; Ross, J.*; Kelly, R. G.*

Corrosion, 81(6), p.609 - 621, 2025/06

Journal Articles

Enhanced strength and ductility in an additively manufactured Al10SiMg alloy at cryogenic temperatures

Naeem, M.*; Rehman, A. U.*; Romero Resendiz, L.*; Salamci, E.*; Aydin, H.*; Ansari, P.*; Harjo, S.; Gong, W.; Wang, X.-L.*; 3 of others*

Communications Materials (Internet), 6, p.65_1 - 65_13, 2025/04

JAEA Reports

Elemental composition analysis of main structural materials of JMTR

Nagata, Hiroshi; Kochiyama, Mami; Chinone, Marina; Sugaya, Naoto; Nishimura, Arashi; Ishikawa, Joji; Sakai, Akihiro; Ide, Hiroshi

JAEA-Data/Code 2024-016, 44 Pages, 2025/03

JAEA-Data-Code-2024-016.pdf:3.54MB

The elemental composition of the structural materials of nuclear reactor facilities is used as one of the important parameters in activation calculations that are evaluated when formulating decommissioning plans. Regarding the elemental composition of aluminum alloys and other materials used as structural materials for test and research reactors, sufficient data is not available regarding elements other than the major elements. For this reason, samples were collected from aluminum alloy, beryllium, hafnium, and other materials that have been used as the main structural materials of JMTR (Japan Materials Testing Reactor), and their elemental compositions were analyzed. This report summarizes the elemental composition data of 78 elements obtained in FY2023.

Journal Articles

Mechanical properties of base metal and heat-affected zone in friction-stir-welded AA6061-T6 at ultra-low temperature of 20 K

Nguyen, T.-D.*; Singh, C.*; Kim, Y. S.*; Han, J. H.*; Lee, D.-H.*; Lee, K.*; Harjo, S.; Lee, S. Y.*

Journal of Materials Research and Technology, 31, p.1547 - 1556, 2024/07

 Times Cited Count:3 Percentile:70.74(Materials Science, Multidisciplinary)

Journal Articles

Improving fatigue performance of laser-welded 2024-T3 aluminum alloy using dry laser peening

Sano, Tomokazu*; Eimura, Takayuki*; Hirose, Akio*; Kawahito, Yosuke*; Katayama, Seiji*; Arakawa, Kazuto*; Masaki, Kiyotaka*; Shiro, Ayumi*; Shobu, Takahisa; Sano, Yuji*

Metals, 9(11), p.1192_1 - 1192_13, 2019/11

AA2019-0690.pdf:3.91MB

 Times Cited Count:17 Percentile:61.02(Materials Science, Multidisciplinary)

The purpose of the present study was to verify the effectiveness of dry laser peening (DryLP), which is the peening technique without a sacrificial overlay under atmospheric conditions using femtosecond laser pulses on the mechanical properties such as hardness, residual stress, and fatigue performance. After DryLP treatment of the laser-welded 2024 aluminum alloy, the softened weld metal recovered to the original hardness of base metal, while residual tensile stress in the weld metal and heat-affected zone changed to compressive stresses. The fatigue life almost doubled at a stress amplitude of 180 MPa and increased by a factor of more than 50 at 120 MPa. As a result, DryLP was found to be more effective for improving the fatigue performance of laser-welded aluminum specimens with welding defects at lower stress amplitudes.

Journal Articles

Neutron imaging analysis of hydrogen content in pure palladium and aluminum alloys

Shimizu, Kazuyuki*; Hayashida, Hirotoshi*; Toda, Hiroyuki*; Kai, Tetsuya; Matsumoto, Yoshihiro*; Matsumoto, Yoshihisa*

Nihon Kinzoku Gakkai-Shi, 83(11), p.434 - 440, 2019/11

 Times Cited Count:1 Percentile:4.90(Metallurgy & Metallurgical Engineering)

JAEA Reports

Calculations of Tritium Recoil Release from Li and U Impurities in Neutron Reflectors (Joint research)

Ishitsuka, Etsuo; Kenzhina, I.*; Okumura, Keisuke; Ho, H. Q.; Takemoto, Noriyuki; Chikhray, Y.*

JAEA-Technology 2018-010, 33 Pages, 2018/11

JAEA-Technology-2018-010.pdf:2.58MB

As a part of study on the mechanism of tritium release to the primary coolant in research and testing reactors, tritium recoil release rate from Li and U impurities in the neutron reflector made by beryllium, aluminum and graphite were calculated by PHITS code. On the other hand, the tritium production from Li and U impurities in beryllium neutron reflectors for JMTR and JRR-3M were calculated by MCNP6 and ORIGEN2 code. By using both results, the amount of recoiled tritium from beryllium neutron reflectors were estimated. It is clear that the amount of recoiled tritium from Li and U impurities in beryllium neutron reflectors are negligible, and 2 and 5 orders smaller than that from beryllium itself, respectively.

Journal Articles

Proton-induced activation cross section measurement for aluminum with proton energy range from 0.4 to 3 GeV at J-PARC

Matsuda, Hiroki; Meigo, Shinichiro; Iwamoto, Hiroki

Journal of Nuclear Science and Technology, 55(8), p.955 - 961, 2018/08

 Times Cited Count:9 Percentile:60.52(Nuclear Science & Technology)

We have started an experimental program to measure activation cross sections systematically in the proton-induced spallation reaction in structural materials commonly used in high-intensity proton accelerator-based facilities, such as Japan Proton Accelerator Research Complex (J-PARC). As the first step of the program, aluminum (Al) was chosen to verify the adequacy of the measurement technique implemented in a J-PARC proton beam environment because data of Al have been relatively well studied both by experimental measurement and simulation. Activation cross sections of $$^{7}$$Be, $$^{22}$$Na, and $$^{24}$$Na in Al were measured at proton energy points from 0.4, 1.3, 2.2 to 3.0 GeV, which could be delivered smoothly from the synchrotron. The validity of experimental data has been verified by introducing an effective proton numbers determination procedure. We compared the measured data with existing experimental data, the evaluated data (JENDL-HE/2007), and the calculations with several intra-nuclear cascade models by the Particle and Heavy Ion Transport code System (PHITS) code. Although the experimental data agreed with JENDL-HE/2007, the calculations underestimated about 40%. This could come from the evaporation model (generalized evaporation model) being implemented in the PHITS code. We found that the calculations agreed with the experimental data by an upgraded PHITS code.

Journal Articles

Implementation of a low-activation Au-In-Cd decoupler into the J-PARC 1 MW short pulsed spallation neutron source

Teshigawara, Makoto; Ikeda, Yujiro; Oi, Motoki; Harada, Masahide; Takada, Hiroshi; Kakishiro, Masanori*; Noguchi, Gaku*; Shimada, Tsubasa*; Seita, Kyoichi*; Murashima, Daisuke*; et al.

Nuclear Materials and Energy (Internet), 14, p.14 - 21, 2018/01

 Times Cited Count:1 Percentile:9.77(Nuclear Science & Technology)

We developed an Au-In-Cd (AuIC) decoupler material to reduce induced radioactivity instead of Ag-In-Cd one, which has a cut off energy of 1eV. In order to implement it into an actual moderator-reflector assembly, a number of critical engineering issues need to be resolved with regard to large-sized bonding between AuIC and A5083 alloys by the hot isostatic pressing process. We investigated this process in terms of the surface conditions, sizes, and heat capacities of large AuIC alloys. We also show a successful implementation of an AuIC decoupler into a reflector assembly, resulting in a remarkable reduction of radioactivity by AuIC compared to AIC without sacrificing neutronic performance.

Journal Articles

A Laser ion source with a thin ohmic-heating ionizer for the TIARA-ISOL

Koizumi, Mitsuo; Osa, Akihiko; Oshima, Masumi; Sekine, Toshiaki; Wakui, Takashi*; Jin, W.*; Katsuragawa, H.*; Miyatake, Hiroari*; Ishida, Yoshihisa*

Nuclear Instruments and Methods in Physics Research B, 204(1-4), p.359 - 362, 2003/05

 Times Cited Count:7 Percentile:46.32(Instruments & Instrumentation)

no abstracts in English

Journal Articles

R&D status of the annuler coupled structure linac for the JAERI/KEK joint project

Ao, Hiroyuki; Hayashizaki, Noriyosu*; Paramonov, V.*

Proceedings of 21st International Linear Accelerator Conference, p.82 - 84, 2003/00

Annular Coupled Structure (ACS) has been developed for the 190-400MeV coupled-cavity linac of the JAERI/KEK joint project. Design optimization of the ACS cavity has nearly been completed using 2D and 3D codes. In parallel with the numerical analyses, half-scale aluminum models were fabricated to confirm the numerical results. The cold-model tests also aim to finish the detailed design taking mass production procedures into account. Especially, the machining and the tuning procedures are examined in detail from the viewpoint of cost reduction and quality management. The results of the model tests are presented with those of other recent R&D works on ACS, which include fabrication R&D performed with full-scale models.

Journal Articles

Heat capacity measurements on unirradiated and irradiated fuel pellets

Amaya, M.*; Une, Katsumi*; Minato, Kazuo

Journal of Nuclear Materials, 294(1-2), p.1 - 7, 2001/04

 Times Cited Count:12 Percentile:63.80(Materials Science, Multidisciplinary)

no abstracts in English

Journal Articles

Evaluation of neutron- and proton-induced nuclear data on $$^{27}$$Al up to 2GeV

Y.-O.Lee*; J.Chang*; Fukahori, Tokio; Chiba, Satoshi

Journal of Nuclear Science and Technology, 36(12), p.1125 - 1134, 1999/12

 Times Cited Count:10 Percentile:60.71(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Quench of molten aluminum oxide associated with in-vessel debris retention by RPV internal water

Maruyama, Yu; ; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Y.Yang*; Sugimoto, Jun

NEA/CSNI/R(98)18, p.243 - 250, 1999/02

no abstracts in English

Journal Articles

Calculation of K-absorption edge in laser-shocked aluminum

; ;

Inst. Phys. Conf. Ser., (159), p.455 - 458, 1999/00

no abstracts in English

Journal Articles

Decay heat measurement on aluminum, copper and type 304 stainless steel irradiated by D-T neutrons

Maekawa, Fujio; Ikeda, Yujiro; E.T.Cheng*

Fusion Engineering and Design, 42, p.229 - 233, 1998/00

 Times Cited Count:3 Percentile:31.35(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Experiment and analysis on in-vessel debris coolability in ALPHA program

Maruyama, Yu; ; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Y.Yang*; Sugimoto, Jun

JAERI-Conf 98-009, p.100 - 106, 1998/00

no abstracts in English

Journal Articles

Research plan on in-vessel debris coolability in ALPHA program

Maruyama, Yu; Yamano, Norihiro; Kudo, Tamotsu; Moriyama, Kiyofumi; Sugimoto, Jun

JAERI-memo 08-127, p.269 - 275, 1996/06

no abstracts in English

Journal Articles

Studies on in-vessel debris coolability in ALPHA program

Maruyama, Yu; Yamano, N.; Moriyama, Kiyofumi; H.S.Park*; Kudo, Tamotsu; Sugimoto, Jun

NUREG/CP-0157, 2, p.161 - 172, 1996/00

no abstracts in English

JAEA Reports

Fuel melting and mechanical energy generation during power burst experiments with aluminum-cladding uranium silicide fuel plate

Fuketa, Toyoshi; Ishijima, Kiyomi; ; Soyama, Kazuhiko; Ichikawa, Hiroki; Kodaira, Tsuneo

JAERI-Research 95-077, 28 Pages, 1995/10

JAERI-Research-95-077.pdf:2.49MB

no abstracts in English

47 (Records 1-20 displayed on this page)