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Journal Articles

Attila validation with fusion benchmark experiments at JAEA/FNS

Konno, Chikara; Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Onishi, Seiki; Takakura, Kosuke; Iida, Hiromasa

Nuclear Technology, 168(3), p.743 - 746, 2009/12

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

The three-dimensional Sn code Attila of Transpire, Inc. can use CAD data as a geometrical input directly and deal with assemblies of complicated geometry without much effort. ITER organization has a plan to adopt this code as one of the standard codes for nuclear analyses. However validation of calculations with this code is not carried out in detail so far. Thus we validate this code through analyses of some bulk experiments and streaming experiments with DT neutrons at JAEA/FNS. Analyses with the Sn code system DOORS and Monte Carlo code MCNP4C were also carried out for comparison. Agreement between Attila and DOORS calculations is very good for the bulk experiments. For streaming experiments Attila requires special treatments (biased angular quadrature sets or last collided source calculation) as well as DOORS in order to obtain similar results as those with MCNP, though Attila consumes much more time and memory than DOORS.

Journal Articles

Research and development of nuclear fusion

Ushigusa, Kenkichi; Seki, Masahiro; Ninomiya, Hiromasa; Norimatsu, Takayoshi*; Kamada, Yutaka; Mori, Masahiro; Okuno, Kiyoshi; Shibanuma, Kiyoshi; Inoue, Takashi; Sakamoto, Keishi; et al.

Genshiryoku Handobukku, p.906 - 1029, 2007/11

no abstracts in English

Journal Articles

Nuclear fusion

Ninomiya, Hiromasa; Konishi, Satoshi

Karyoku Genshiryoku Hatsuden, 52(10), p.149 - 155, 2001/10

no abstracts in English

JAEA Reports

Japanese contributions to IAEA INTOR Workshop, phase two A, part 3, chapter VIII; Blanket and first wall

*; Iida, Hiromasa; *; Adachi, Junichi*; ; Ebisawa, Katsuyuki*; *; Fukaya, Kiyoshi; *; *; et al.

JAERI-M 87-219, 336 Pages, 1988/01

JAERI-M-87-219.pdf:8.39MB

no abstracts in English

Oral presentation

Shielding analysis of IFMIF-EVEDA accelerator system, 1; Shielding analysis at beam dump for 9 MeV-125mA deutron beam

Onishi, Seiki; Maebara, Sunao; Iida, Hiromasa; Yamauchi, Michinori*; Sakaki, Hironao; Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara

no journal, , 

no abstracts in English

Oral presentation

ITER/TBM neutronics experiments at FNS, 2; Analysis

Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Konno, Chikara; Iida, Hiromasa; Yamauchi, Michinori*; Takakura, Kosuke; Onishi, Seiki; Nishitani, Takeo

no journal, , 

no abstracts in English

Oral presentation

Analyses of fusion neutronics benchmark experiments at JAEA/FNS with Attila

Konno, Chikara; Sato, Satoshi; Ochiai, Kentaro; Onishi, Seiki; Takakura, Kosuke; Wada, Masayuki*; Iida, Hiromasa

no journal, , 

The three-dimensional Sn code Attila of Transpire, Inc. can use CAD data as a geometrical input directly and deal with assemblies of complicated geometry without much effort. ITER organization has a plan to adopt this code as one of the standard codes for nuclear analyses. However validation of calculations with this code is not carried out in detail so far. Thus we validate this code through analyses of some bulk experiments and streaming experiments with DT neutrons at JAEA/FNS. Analyses with the Sn code system DOORS and Monte Carlo code MCNP4C were also carried out for comparison. Agreement between Attila and DOORS calculations is very good for the bulk experiments. For streaming experiments Attila requires special treatments (biased angular quadrature sets or last collided source calculation) as well as DOORS in order to obtain similar results as those with MCNP, though Attila consumes much more time and memory than DOORS.

Oral presentation

Progress on blanket neutronics study

Sato, Satoshi; Takakura, Kosuke; Ochiai, Kentaro; Wada, Masayuki*; Onishi, Seiki; Iida, Hiromasa; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Kawabe, Masaru; et al.

no journal, , 

no abstracts in English

Oral presentation

Analyses of fusion neutronics integral experiments at JAEA/FNS with FENDL-2.1 and other recent nuclear data libraries

Konno, Chikara; Sato, Satoshi; Ochiai, Kentaro; Takakura, Kosuke; Onishi, Seiki; Iida, Hiromasa; Wada, Masayuki*

no journal, , 

FENDL-2.1, which was released in 2004, is a collection of the best evaluation for fusion applications from the world-wide nuclear data libraries, ENDF/B-VI.8, JENDL-3.2, -3.3, Fusion File, JEFF-3.0 and Brond-2.1. It is adopted for nuclear analyses of fusion reactors such as ITER and gives good results. Recently new nuclear data libraries of JEFF-3.1 and ENDF/B-VII.0 have been released. Probably a new nuclear data selection for the next FENDL will be carried out for more accurate nuclear analyses. Thus we carried out a series of analyses for fusion neutronics integral experiments (simple geometry experiments, time-of-flight experiments) at JAEA FNS with FENDL-2.1 and other recent nuclear data libraries, in order to validate the recent nuclear data libraries. Typical results of iron, beryllium, lithium oxide, etc. will be presented in this conference.

Oral presentation

Shielding analysis for IFMIF/EVEAD accelerator

Onishi, Seiki; Maebara, Sunao; Iida, Hiromasa; Yamauchi, Michinori*; Sakaki, Hironao; Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara

no journal, , 

no abstracts in English

Oral presentation

Problem on iron data in JENDL-3.3 specified through analysis of iron integral experiment with DT neutrons

Konno, Chikara; Ochiai, Kentaro; Takakura, Kosuke; Onishi, Seiki; Sato, Satoshi; Wada, Masayuki*; Iida, Hiromasa

no journal, , 

When the integral experiment on iron with DT neutrons previously performed at JAEA/FNS was analyzed with MCNP4C and the nuclear data libraries of JENDL-3.3 and ENDF/B-VII.0, it was found out that the calculation with JENDL-3.3 overestimated the measured neutrons below 10 keV by 10%. We examined which iron isotope and reaction in JENDL-3.3 caused the overestimation by analyzing the experiment with JENDL-3.3 partly replaced to ENDF/B-VII.0. As a result, it was concluded that the first inelastic scattering cross section of $$^{57}$$Fe in JENDL-3.3 caused the overestimation of the iron experiment. The next version of JENDL should revise the first inelastic scattering cross section of $$^{57}$$Fe should be revised in the next version of JENDL.

Oral presentation

Efficient production of recombinant protease and cellulase by ${it Brevibacillus}$, expression system while difficult by ${it E. coli}$

Onishi, Hiromasa*; Mizukami, Makoto*; Hanagata, Hiroshi*; Tokunaga, Masao*; Kuroki, Ryota; Adachi, Motoyasu; Ishikawa, Kazuhiko*; Miyauchi, Akira*

no journal, , 

${it Brevibacillus}$ is one of the remarkable host developing to produce secretory proteins. The proteins above amount of 10g/L have been expressed into the medium using the Brevibacillus expression system as known examples. In addition, there are many examples of expression of proteins derived from bacteria to human proteins and including disulfide bridge. Recently, we succeeded in high-level and secretory expression of protease and cellulase which are not efficiently produced in E. coli expression system.

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