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Konno, Chikara; Ota, Masayuki; Asahara, Hiroo; Ochiai, Kentaro; Sato, Satoshi
JAEA-Conf 2014-002, p.160 - 166, 2015/02
IAEA released a new version of Evaluated Nuclear Data Library (FENDL), FENDL-3.0 in 2012 in order to extend the neutron energy range of neutron-induced reactions from 20 MeV to more than 60 MeV and to include general purpose and activation data libraries for proton- and deuteron-induced reactions up to more than 60 MeV. We already reported the benchmark tests of the general purpose data library for neutron-induced reactions below 20 MeV in FENDL-3.0. Now we present the benchmark tests of the general purpose data library for neutron-induced reactions in FENDL-3.0 by using iron and concrete shielding experiments with the 40 and 65 MeV neutron sources at TIARA in JAEA. As a result, it is found out that the calculations with FENDL-3.0 agree with the measured ones for the iron experiment well, while they overestimate the measured ones for the concrete experiment more for the thicker assemblies.
Shinto, Katsuhiro; Vermare, C.*; Asahara, Hiroo; Sugimoto, Masayoshi; Garin, P.*; Maebara, Sunao; Takahashi, Hiroki; Sakaki, Hironao; Kojima, Toshiyuki; Ohira, Shigeru; et al.
Proceedings of 6th Annual Meeting of Particle Accelerator Society of Japan (CD-ROM), p.668 - 670, 2010/03
Progress of the IFMIF/EVEDA prototype accelerator in fiscal year of 2008 is described. All the sub-systems of the prototype accelerator have started to design, settled the plan of the manufacturing and component tests and fixed the design parameters. As a result of the analysis of planning for the engineering validation of the IFMIF accelerator system, the project duration to be prolonged to the end of 2014 including some months for contingency was approved by the BA Steering Committee. In this article, the design status of each accelerator component, the interface between the accelerator components and the IFMIF/EVEDA Accelerator Building settled in International Fusion Energy Research Centre (IFERC) in Rokkasho and the proposed accelerator commissioning plan for the engineering validation will be presented.
Ida, Mizuho; Asahara, Hiroo; Nakamura, Hiroo
no journal, ,
For design of liquid lithium (Li) target of the International Fusion Materials Irradiation Facility (IFMIF), two-dimensional hydraulic/thermal-hydraulic analyses were performed using codes PHOENICS and FLOW-3D. The analyses clarified effect of a 2-step contraction nozzle with high contraction-ration of 10 upon generation of high-speed uniform flow. The nozzle was selected for IFMIF target. Also transient behaviors of pressure and velocity profiles from uniform in the nozzle to gradient on the concave back-plate were clarified. With the clarified behaviors and thermal-hydraulic analysis, no Li boiling at the IFMIF target in case of back-plate curvature of 10 m or less was predicted. EVADA Lithium Test Loop with the selected contraction nozzle is operated, hydraulically simulating IFMIF target flow to validate IFMIF design. Also three-dimensional hydraulic/thermal-hydraulic analyses using a code FLUENT are going for engineering designs of the EVEDA and IFMIF targets.
Shinto, Katsuhiro; Ohira, Shigeru; Kikuchi, Takayuki; Kubo, Takashi; Yonemoto, Kazuhiro; Kasuya, Kenichi; Maebara, Sunao; Takahashi, Hiroki; Kojima, Toshiyuki; Tsutsumi, Kazuyoshi; et al.
no journal, ,
no abstracts in English
Ota, Masayuki; Asahara, Hiroo; Ochiai, Kentaro; Sato, Satoshi; Konno, Chikara
no journal, ,
The three-dimensional Monte Carlo transport code TRIPOLI developed in CEA is adopted as one of ITER neutronics codes. However it is not always used worldwide, particularly in Japan. In this study, we examined a basic performance of TRIPOLI-4.9S which is the latest version of TRIPOLI through a simple model calculation and an analysis of iron fusion neutronics experiment with DT neutrons at JAEA/FNS and discussed improvements from the previous version and problems of TRIOPOLI-4.9S.
Konno, Chikara; Ota, Masayuki; Asahara, Hiroo; Ochiai, Kentaro; Sato, Satoshi
no journal, ,
IAEA released a new version of Evaluated Nuclear Data Library (FENDL), FENDL-3.0 in 2012 in order to extend the neutron energy range of neutron-induced reactions from 20 MeV to more than 60 MeV and to include general purpose and activation data libraries for proton- and deuteron-induced reactions up to more than 60 MeV. We have carried out benchmark tests of the general purpose data library for neutron-induced reactions in FENDL-3.0 by using iron and concrete shielding experiments with the 40 and 65 MeV neutron sources at TIARA in JAEA. As a result, it was found out that the calculations with FENDL-3.0 agreed with the measured ones for the iron experiment well, while they overestimated the measured ones for the concrete experiment more for the thicker assemblies because of the smaller non-elastic scattering cross sections of 
O in FENDL-3.0. The O data in FENDL-3.0 should be revised.
Kato, Saori; Yoshida, Shigeo*; Ochiai, Kentaro; Asahara, Hiroo; Ota, Masayuki; Sato, Satoshi; Konno, Chikara
no journal, ,
no abstracts in English
