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Kogawara, Takafumi; Wakai, Eiichi; Kikuchi, Takayuki; Yamamoto, Michiyoshi; Molla, J.*
Fusion Engineering and Design, 86(12), p.2904 - 2907, 2011/12
Times Cited Count:3 Percentile:25.34(Nuclear Science & Technology)no abstracts in English
Wakai, Eiichi; Yamamoto, Michiyoshi; Molla, J.*; Yokomine, Takehiko*; Nogami, Shuhei*
Fusion Engineering and Design, 86(6-8), p.712 - 715, 2011/10
Times Cited Count:6 Percentile:43.25(Nuclear Science & Technology)The main purpose of present phase of IFMIF/EVEDA (International Fusion Materials Irradiation Facility/Engineering Validation and Engineering Design Activities) is to produce a detailed report of IFMIF engineering design with the integrated design of all facilities in IFMIF. The main function of the IFMIF is to give the demanded design database for the licensing of DEMO reactors and further reactors, and it is achieved from the materials data set obtained from the high, medium, and low flux test modules (HFTM, MFTM and LFTM) of IFMIF. In the evaluation using small specimens, developments and guidelines of small specimen test technique or technology (SSTT) are also demanded for the achievements. This paper is summarized about the design plan and requirements in these test modules and testing items in IFMIF.
Molla, J.*; Yamamoto, Michiyoshi; Polato, A.*; Soldaini, M.*; Takeuchi, Hiroshi; Wakai, Eiichi
Fusion Engineering and Design, 86(9-11), p.2522 - 2525, 2011/10
Times Cited Count:3 Percentile:25.34(Nuclear Science & Technology)The workload for the Post Irradiation Examination facility during the operation of IFMIF is evaluated in this paper are based on the IFMIF specifications proposed by IFMIF user's community, available irradiation volumes in the test modules and materials properties required to compile the materials database.
Wakai, Eiichi; Kikuchi, Takayuki; Kogawara, Takafumi; Kimura, Haruyuki; Yokomine, Takehiko*; Kimura, Akihiko*; Nogami, Shuhei*; Kurishita, Hiroaki*; Saito, Masahiro*; Nishimura, Arata*; et al.
Proceedings of 23rd IAEA Fusion Energy Conference (FEC 2010) (CD-ROM), 6 Pages, 2011/03
Japanese activities of test facilities in IFMIF-EVEDA (International Fusion Materials Irradiation Facility-Engineering Validation and Engineering Design Activities) project have three subjects of engineering design of post irradiation examination (PIE) facilities, small specimen test technique (SSTT), and engineering design of high flux test module (HFTM), and this paper is summarized about present status. Functional analysis and design of 2-D and 3-D models of PIE facility were performed. In HFTM, as materials of heater, W-3Re alloy and/or SiC/SiC composite were selected in the points of high temperature materials, fabrication technology and some suitable properties such as resistance of thermal shock, high temperature re-crystallization, ductility, resistance of irradiation degradation, and low-activation. In SSTT, a test machine of fracture toughness was designed and developed for small specimens with 10 mm square, and it had high accuracy controllability for stress and displacement.
Sugimoto, Masayoshi; Garin, P.*; Vermare, C.*; Shinto, Katsuhiro; Grschel, F.*; Nakamura, Kazuyuki; Molla, J.*; Arnaud, J.*
Fusion Science and Technology, 56(1), p.259 - 266, 2009/07
Times Cited Count:0 Percentile:0.00(Nuclear Science & Technology)One year has passed after the start of the Engineering Validation and Engineering Design Activities of the International Fusion Materials Irradiation Facility (IFMIF/EVEDA), which is a project performed under the Broader Approach Agreement of the fusion energy research between Japan and Europe. The project team to manage the overall activities was established at Rokkasho in Japan, and 12 people are working for planning and scheduling of whole project plan and for coordinating the annual work programs. In this year the management tools like WBS are defined and the detailed engineering design works are ready to start. However, as the collaboration between the project team and each contributing institutes in Japan and Europe is important to complete the fully integrated design of the IFMIF, a high level of the communication and sharing of information and knowledge is necessary to be established. The workshop like meeting is a good opportunity to discuss about the issues by all contributors at a single place. In the first meeting held in September the details of requirements/specifications for neutron generation, including ion beam - liquid lithium target - neutron irradiation capsule, concerned in their interfaces were defined.
Hidaka, Koshi*; Kimura, Toru*; Abdel-Rahman, H. M.*; Nguyen, J.-T.*; McDaniel, K. F.*; Kohlbrenner, W. E.*; Molla, A.*; Adachi, Motoyasu; Tamada, Taro; Kuroki, Ryota; et al.
Journal of Medicinal Chemistry, 52(23), p.7604 - 7617, 2009/07
Times Cited Count:20 Percentile:45.74(Chemistry, Medicinal)A series of HIV protease inhibitor based on the allophenylnorstatine structure with various P2' moieties were synthesized. Among these analogues, we discovered that a small allyl group would maintain potent enzyme inhibitory activity compared to that of the -methylbenzyl moiety in clinical candidate 1 (KNI-764, also known as JE-2147, AG-1776 or SM-319777). Introduction of an anilinic amino group to 2 (KNI-727) improved water-solubility and anti-HIV-1 activity. X-ray crystallographic analysis of 13k (KNI-1689) with a -methallyl group at P2' position revealed hydrophobic interactions with Ala28, Ile84, and Ile50' similar to that of 1. The presence of an additional methyl group on the allyl group in compound 13k significantly increased anti-HIV activity over 1, while providing a rational drug design for structural minimization and improving membrane permeability.
Molla, J.*; Nakamura, Kazuyuki
Fusion Engineering and Design, 84(2-6), p.247 - 251, 2009/06
Times Cited Count:6 Percentile:40.30(Nuclear Science & Technology)IFMIF is considered as a key element in the achievement of fusion reactors. Experiments performed in IFMIF will produce valuable information on the behavior of materials under reactor conditions. The project entered in July 2007 into EVEDA phase. The engineering design will be completed by June 2013. The Test Facilities is one of the three main systems that compose IFMIF. Irradiation of samples, remote handling between different rooms, post-irradiation studies and all the required technologies to operate the Test Facilities will be part of this system. The intense neutron flux in the Test Cell, the heat load in the modules, the use of tritium for in-situ experiments and the presence of high radioactivity levels in the access Cell makes the design of the Test Cell system somewhat complicated. The main challenges for the design of the Test Cell and the required Validation of new technologies will be studied in this paper.
Nakamura, Kazuyuki; Molla, J.*
no journal, ,
International Fusion Materials Irradiation Facility (IFMIF) is the most important facility for the development of the fusion materials, and Engineering Validation and Engineering Design Activities (EVEDA) of IFMIF have been carried out from July in 2007. IFMIF consists of the three major systems, and the function of the Test Facilities system is mainly to keep the steady irradiation condition such as temperature and to achieve the best performance of the post irradiation examination with the irradiated small samples. The goal of IFMIF/EVEDA for the Test Facilities is to complete the engineering design of the Test Facilities and to provide the necessary information for the integrated design of IFMIF. To perform the design tasks, it is additionally necessary to be accomplished with the validation tasks on the key components and supporting design tasks. This paper will describe the progress and key issues of the Test Facilities system in the IFMIF/EVEDA project.
Kogawara, Takafumi; Wakai, Eiichi; Kikuchi, Takayuki; Nakamura, Kazuyuki; Molla, J.*
no journal, ,
no abstracts in English
Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki; Yamamoto, Michiyoshi; Molla, J.*; Kimura, Akihiko*; Kasada, Ryuta*; Kim, B.*; Nogami, Shuhei*; Hasegawa, Akira*; et al.
no journal, ,
no abstracts in English
Wakai, Eiichi; Kogawara, Takafumi; Kikuchi, Takayuki; Yokomine, Takehiko*; Molla, J.*; Yamamoto, Michiyoshi
no journal, ,
no abstracts in English
Nakamura, Kazuyuki; Garin, P.*; Sugimoto, Masayoshi; Molla, J.*; Mslang, A.*; Wakai, Eiichi
no journal, ,
IFMIF/EVEDA Test facility activities, which consisted of design, validation and supporting tasks, started last July. In the activities, several tasks shared to Japan and EU will be performed until June in 2013. For the Japanese tasks, JAEA, universities and other organization will contribute the activities. For the EU tasks, FZK (Germany), CIEMAT (Spain), PSI (Switzerland) and SCK-CEN (Belgium) will contribute the activities. First draft design reports will be supplied at June in 2012.
Kikuchi, Takayuki; Sugimoto, Masayoshi; Nakamura, Kazuyuki; Wakai, Eiichi; Garin, P.*; Molla, J.*
no journal, ,
Post irradiation examination (PIE) facilities where the examination item is enforceable after it irradiates it being examined by the conceptual design are designed in detail in IFMIF/EVEDA. It reports on the examination situation in the current state this time.