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Konno, Chikara; Wada, Masayuki*; Kondo, Keitaro; Onishi, Seiki; Takakura, Kosuke; Ochiai, Kentaro; Sato, Satoshi
Fusion Engineering and Design, 86(9-11), p.2682 - 2685, 2011/10
Times Cited Count：4 Percentile：32.59(Nuclear Science & Technology)JENDL-4, the major revised version of Japanese Evaluated Nuclear Data Library (JENDL), was released in spring, 2010. We analyzed the fusion neutronics benchmark experiments on iron at JAEA/FNS with JENDL-4.0 and MCNP4C as the detail benchmark test of JENDL-4.0 iron data. As a result, it is found out that the problems of iron data in JENDL-3.3 are adequately revised in JENDL-4.0 iron data; e.g. the first inelastic scattering cross section data of 
Fe and angular distribution of elastic scattering of 
Fe. The iron data in JENDL-4.0 are comparable to and are partly better than those in ENDF/B-VII.0 and JEFF-3.1.
Konno, Chikara; Takakura, Kosuke; Wada, Masayuki*; Kondo, Keitaro; Onishi, Seiki*; Ochiai, Kentaro; Sato, Satoshi
Progress in Nuclear Science and Technology (Internet), 2, p.346 - 357, 2011/10
The major revised version of Japanese Evaluated Nuclear Data Library (JENDL), JENDL-4, was released in 2010 spring. As the benchmark test of JENDL-4.0 in the shielding and fusion neutronics fields, we analyzed many integral benchmark experiments (in-situ and Time-of-Flight (TOF) experiments) with DT neutrons at JAEA/FNS with the MCNP code and JENDL-4.0. The experiments with assemblies including beryllium, carbon, silicon, vanadium, copper, tungsten and lead, nuclear data of which were revised in JENDL-4.0, were selected for this benchmark test. As a result, it is found that JENDL-4 improved some problems pointed out in JENDL-3.3 and that it is comparable to ENDF/B-VII.0 and JEFF-3.1.
Konno, Chikara; Ochiai, Kentaro; Takakura, Kosuke; Onishi, Seiki; Kondo, Keitaro; Wada, Masayuki*; Sato, Satoshi
Fusion Engineering and Design, 85(10-12), p.2054 - 2058, 2010/12
Times Cited Count：1 Percentile：9.99(Nuclear Science & Technology)In the last ISFNT, we presented re-analyses of fusion neutronics benchmark experiments on beryllium at JAEA/FNS and reported that all the calculations with JENDL-3.3, FENDL-2.1, JEFF-3.1 and ENDF/B-VII.0 overestimated experimental data on low energy neutrons and that the calculation with JEFF-3.1 had a strange peak around 12 MeV. Here we investigate reasons for these problems. As a result, It was found out that the official ACE file MCJEFF3.1 of JEFF-3.1 had an inconsistency with the original JEFF-3.1, which caused the strange larger neutron peak around 12 MeV. We also find out that the calculated thermal neutron peak is probably too large. It is indicated that the coherent elastic scattering cross section data in the thermal neutron flux law data of beryllium metal are too large.
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.
Sato, Satoshi; Takakura, Kosuke; Ochiai, Kentaro; Kondo, Keitaro; Tatebe, Yosuke; Onishi, Seiki; Wada, Masayuki*; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; et al.
Fusion Science and Technology, 56(1), p.227 - 231, 2009/07
Times Cited Count：1 Percentile：10.22(Nuclear Science & Technology)Previously DT neutronics experiments were performed by using partial blanket mockups for Japanese ITER test blanket module at JAEA FNS, and tritium production rates (TPR) inside blanket mockups were measured in details. The calculation with the nuclear data library FENDL-2.1 and Monte Carlo code MCNP4C agreed well with most of the measured TPRs within uncertainty of 10%. On the other hand, overestimations were found for the TPR in the experiment with a reflector and the TPR around the boundary between the rear part of the breeder layer and the beryllium layer by more than 10%. In order to confirm this concern, we measured reaction rate distribution in the partial blanket mockups with DT neutrons with two solid breeder blanket partial mockups, (Be/Li
TiO
/Be, SS316/LiTiO/SS316). Experiments were performed with and without a neutron source reflector. In order to measure reaction rate distributions, the activation foil method was applied using Nb and Au foils in this study. Experimental analyses were performed by MCNP4C with FENDL-2.1. Calculation results to experimental ones (C/Es) on the Au reaction rate with a reflector were larger than those without one. Detailed results are presented in this conference.
Konno, Chikara; Ochiai, Kentaro; Wada, Masayuki*; Takakura, Kosuke; Sato, Satoshi
Fusion Engineering and Design, 84(7-11), p.1095 - 1098, 2009/06
Times Cited Count：3 Percentile：24.52(Nuclear Science & Technology)Iron is one of the most important elements for radiation shielding in fusion reactors and nuclear data on iron are required to be more accurate for thicker shield in future fusion reactors such as DEMO. In order to evaluate the accuracy of the latest nuclear data on iron, the fusion neutronics integral experiment on iron at JAEA/FNS was analyzed in detail. The Monte Carlo code MCNP-4C was used for this analysis with the latest nuclear data libraries of FENDL-2.1, JENDL-3.3, FENDL-2.1, JEFF-3.1 and ENDF/B-VII.0. As a result, generally the calculation with ENDF/B-VII.0 best agreed with the measurement, while the calculation with JENDL-3.3 overestimated the measured neutrons below 10 keV. We examined which iron isotope and reaction in JENDL-3.3 caused the overestimation based on ENDF/B-VII.0. Then it was found out that the first inelastic scattering cross section of Fe in JENDL-3.3 caused the overestimation of the iron experiment.
Konno, Chikara; Ochiai, Kentaro; Wada, Masayuki*; Sato, Satoshi
Fusion Engineering and Design, 83(10-12), p.1774 - 1781, 2008/12
Times Cited Count：14 Percentile：66.71(Nuclear Science & Technology)Many integral benchmark experiments with DT neutrons have been carried out for nuclear data verification for fusion nuclear design at JAEA FNS; simple benchmark experiments, time-of-flight, breeding blanket experiments. For a few years several nuclear data libraries have been newly released; JENDL-3.3, FENDL-2.1, JEFF-3.1 and ENDF/B-VII.0. It is essential to verify these libraries through analyses of integral benchmark experiments. Thus we carried out a series of analyses for the benchmark experiments at JAEA FNS with FENDL-2.1, JENDL-3.3, JEFF-3.1 and ENDF/B-VII.0. The Monte Carlo code MCNP-4C was used for this analysis. Calculated results were compared with measured ones. They were also compared each other. The calculated results with FENDL-2.1, JENDL-3.3, JEFF-3.1 and ENDF/B-VII.0 were almost the same and represented the measured ones except for some experiments.
Ochiai, Kentaro; Sato, Satoshi; Wada, Masayuki*; Iida, Hiromasa; Takakura, Kosuke; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Konno, Chikara
Fusion Engineering and Design, 83(10-12), p.1725 - 1728, 2008/12
Times Cited Count：1 Percentile：10.05(Nuclear Science & Technology)Under the ITER/ITA task, we have conducted the neutron streaming experiment simulating narrow and deep gaps at boundaries between ITER vacuum vessel and equatorial port plugs. Micro fission chambers and some activation foils were utilized to measure fission rates and reaction rates to evaluate the relative fast and slow neutron fluences along the gap in the experimental assembly. The MCNP4C, TORT and Attila codes were used for the experimental analysis. From comparing our measurements and calculations, the following facts were found: (1) In case of a such narrow and deep gap structure, the calculation with MCNP, TORT and ATTILA codes and FENDL-2.1 is sufficient to predict fast neutron field inside the gap.: (2) Angular quadrature set of upward biased U315 and last collided source calculation on TORT and Attila were very important technique for accurate estimation of neutron transport.
Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Konno, Chikara; Nishitani, Takeo
Fusion Engineering and Design, 83(7-9), p.1304 - 1308, 2008/12
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)In the experiment with a reflector and TPR around the boundary between the rear parts of the breeder layer and the beryllium, TPRs calculated by MCNP overestimated the experimental results by more than 10% for our breeding blanket neutronics experiments with DT neutrons carried out at JAEA FNS. We have pointed out that the nuclear data have some problems on back scattered neutrons. Thus we modified the backward part of angular distributions in FENDL-2.1 in order to investigate the possibility of improvement of the overestimation in this study. By decreasing backward part of angular distributions in the elastic scattering of Fe by uniformly 50% from the original data for the incident neutron less than 0.11 MeV, the overestimation was improved for the enriched breeding blanket experiment with a reflector. Also by decreasing backward part of 
Be by uniformly 20% for the incident neutron of 0.62-14.94 MeV, the overestimation was improved on the TPR around the boundary.
Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Yamauchi, Michinori; Iida, Hiromasa; Nishitani, Takeo; Konno, Chikara
Proceedings of International Conference on Nuclear Data for Science and Technology (ND 2007), Vol.2, p.995 - 998, 2008/05
Times Cited Count：0 Percentile：0.2(Nuclear Science & Technology)no abstracts in English
Ochiai, Kentaro; Sato, Satoshi; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori; Abe, Yuichi; Nishitani, Takeo; Konno, Chikara
Fusion Engineering and Design, 82(15-24), p.2794 - 2798, 2007/10
Times Cited Count：5 Percentile：37.19(Nuclear Science & Technology)Neutron streaming experiments have been conducted by using the FNS D-T neutron source at Japan Atomic Energy Agency under the ITER/ITA Task 73-10 in order to evaluate effects of the slit on nuclear properties and validate prediction accuracies on numerical simulations. The experimental assembly with a slit of 2 cm in width and 55 cm in depth was prepared with two iron blocks of 30 cm in height, 100 cm in width and 55cm in thickness as first campaign. The slit was located in the 12-cm upper part from the D-T neutron source point. In order to evaluate distributions of the neutron fluxes along the slit as a function of the depth from the assembly surface, fission reaction rates were measured by U-238 and U-235 micro-fission chambers. The experimental accuracies of these fission reaction rates are within 5%. Monte-Carlo calculation code, MCNP-4c, was used to calculate the U-238 and U-235 reaction rates and neutron energy spectra due to each measured position. From our first experiment, the following facts were found: (1) At d = 20 and 40 cm, reaction rates on U-238, which represent fast neutron flux, decreased by about three orders of magnitude along slits with 50 cm in depth. Monte Carlo calculation results agree well with measured values within 6 %. (2) Reaction rates on U-235, which represent thermal neutron flux, decrease by about one order of magnitude along slits with 50 cm in depth. Values of C/E of U-238 and U-235 reaction rates were 1.10-1.22 and 1.10-1.23 respectively and the calculated values overestimated slightly.
Sato, Satoshi; Ochiai, Kentaro; Verzilov, Y.*; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori; Nishitani, Takeo; Konno, Chikara
Nuclear Fusion, 47(7), p.517 - 521, 2007/07
Times Cited Count：22 Percentile：60.47(Physics, Fluids & Plasmas)no abstracts in English
Sato, Satoshi; Verzilov, Y.*; Ochiai, Kentaro; Wada, Masayuki*; Kutsukake, Chuzo; Tanaka, Shigeru; Abe, Yuichi; Seki, Masakazu; Oginuma, Yoshikazu*; Kawabe, Masaru*; et al.
Journal of Nuclear Science and Technology, 44(4), p.657 - 663, 2007/04
Times Cited Count：9 Percentile：54.87(Nuclear Science & Technology)Neutronics experiments have been performed for the solid breeder blanket using a DT neutron source at the FNS facility in JAEA. We have applied the blanket mockup composed of two enriched LiTiO and three beryllium layers, and measured the detailed spatial distribution of the tritium production rate (TPR) using enriched LiCO pellets. TPRs in the pellets have been measured by a liquid scintillation counter. Experiments have been done under a condition with a neutron reflector surrounding the DT neutron source. Numerical simulations have been performed using the MCNP-4C with the FENDL-2.0 and JENDL-3.3. The ranges of ratios of calculation results to experimental ones (C/Es) are 0.97-1.17 concerning with local TPR, and 1.04-1.09 for the integrated tritium production. It is found that the total integrated tritium production, which corresponds to tritium breeding ratio, can be predicted within uncertainty of 10% using the Monte Carlo calculation code and latest nuclear data libraries.
Sato, Satoshi; Verzilov, Y.*; Ochiai, Kentaro; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori; Nishitani, Takeo; Konno, Chikara
Proceedings of 21st IAEA Fusion Energy Conference (FEC 2006) (CD-ROM), 8 Pages, 2007/03
no abstracts in English
Sato, Satoshi; Wada, Masayuki*; Nishitani, Takeo; Konno, Chikara
Plasma and Fusion Research (Internet), 2, p.002_1 - 002_4, 2007/02
no abstracts in English
Verzilov, Y. M.; Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Klix, A.*; Nishitani, Takeo
Fusion Engineering and Design, 82(1), p.1 - 9, 2007/01
Times Cited Count：9 Percentile：54.87(Nuclear Science & Technology)no abstracts in English
Nishitani, Takeo; Yamauchi, Michinori*; Nishio, Satoshi; Wada, Masayuki*
Fusion Engineering and Design, 81(8-14), p.1245 - 1249, 2006/02
Times Cited Count：13 Percentile：65.83(Nuclear Science & Technology)no abstracts in English
Sato, Satoshi; Verzilov, Y. M.; Ochiai, Kentaro; Nakao, Makoto*; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori*; Nishitani, Takeo
Fusion Engineering and Design, 81(8-14), p.1183 - 1193, 2006/02
Times Cited Count：19 Percentile：77.5(Nuclear Science & Technology)no abstracts in English
Yamauchi, Michinori*; Ochiai, Kentaro; Morimoto, Yuichi*; Wada, Masayuki*; Sato, Satoshi; Nishitani, Takeo
Radiation Protection Dosimetry, 116(1-4), p.542 - 546, 2005/12
Times Cited Count：3 Percentile：24.22(Environmental Sciences)no abstracts in English
Sato, Satoshi; Nakao, Makoto*; Verzilov, Y. M.; Ochiai, Kentaro; Wada, Masayuki*; Kubota, Naoyoshi; Kondo, Keitaro; Yamauchi, Michinori*; Nishitani, Takeo
Nuclear Fusion, 45(7), p.656 - 662, 2005/07
Times Cited Count：8 Percentile：28.14(Physics, Fluids & Plasmas)no abstracts in English
