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Sasaki, Takayuki*; Akimoto, Yuji*; Seki, Kotaro; Nagano, Misato*; Ishimori, Kenichiro; Ueno, Takashi; Kameo, Yutaka
no journal, ,
no abstracts in English
-concrete system under randomizationUeki, Taro
no journal, ,
Analysis framework under indeterminate material distribution is investigated for the Monte Carlo (MC) criticality calculation of continuously mixed media formed via molten core concrete interaction. Randomized Weierstrass functions (RWF) are utilized to represent the volume fractions of constituent materials. The possibility of several percent fluctuation of effective multiplication factor is shown by the MC simulation with delta-tracking.
Sato, Yuki; Kishimoto, Aya*; Kaburagi, Masaaki; Kataoka, Jun*; Torii, Tatsuo
no journal, ,
no abstracts in English
Edao, Yuki; Iwai, Yasunori; Sato, Katsumi; Hayashi, Takumi
no journal, ,
no abstracts in English
Maeda, Makoto; Komeda, Masao; Tobita, Hiroshi; Ozu, Akira; Kureta, Masatoshi
no journal, ,
JAEA has started to develop a technology which can be applicable to high radioactive special nuclear materials such as next-generation fuel cycle products. We have been developed Non-destructive assay system Active-N as a test equipment which utilizes D-T neutron generator. In a system for Differential Die-Away (DDA) method which is tested in Active-N, it is important to evaluate neutron flux to check the performance of the system. In this research, we have evaluated neutron flux in a system for Fast Neutron Direct Interrogation method which is a kind of DDA method by activation method and Monte Carlo simulation by using PHITS.
Terunuma, Hirotaka; Tanaka, Kiwamu; Kabumoto, Hiroshi; Haginoya, Masashi; Sano, Naruto; Takahashi, Masatomi; Hoshino, Masato; Aoki, Isao; Asazuma, Shinichiro
no journal, ,
no abstracts in English
generation by reaction with Ru-La-Na mix nitrates and raw materials for vitrificationNagai, Takayuki; Kobayashi, Hidekazu; Okamoto, Yoshihiro; Sato, Nobuaki*; Inose, Takehiko*; Sato, Seiichi*; Hatakeyama, Kiyoshi*; Seki, Katsumi*
no journal, ,
It is thought that a generated ruthenium compound grows from a high level radioactive liquid waste into RuO crystal by reacting to raw materials for the vitrification process. In this study, the generation reaction to RuO was confirmed by heating Ru-La-Na mix nitrates and the raw materials.
Nozawa, Takashi; Yu, J.-H.*; Park, J.-S.*; Tanigawa, Hiroyasu
no journal, ,
Silicon carbide composites are one of promising materials due to pronounced low radioactivity and excellent radiation resistivity. So far, it was proven that the edge effect of the specimen decreased composite strength depending on the specimen size for the case of off-axial tensile tests. This study then aims to evaluate fracture behavior of SiC/SiC tube materials without any edges. For that purpose, several fabric architecture composites were evaluated by expanding plug burst test to identify the fundamental data of anisotropy of the hoop strength of the composite.
Hirose, Takanori; Sakasegawa, Hideo; Tanigawa, Hisashi; Tanigawa, Hiroyasu; Kawamura, Yoshinori
no journal, ,
Material database for reduced activation ferritic/martensitic steel, F82H have been accumulated for design study on tritium breeding blanket. This study reports fatigue properties of F82H including effects of test temperature and test atmosphere to establish design fatigue curve. It is found that temperature effects on fatigue lifetime is significant above 450
C. As for effects of test atmosphere, lifetime in the vacuum was 5 times higher than that in the air at 550C.
Ezato, Koichiro; Seki, Yohji; Suzuki, Satoshi; Yokoyama, Kenji; Yamada, Hirokazu; Hirayama, Tomoyuki
no journal, ,
no abstracts in English
Nakao, Taro; Kimura, Atsushi; Terada, Kazushi; Nakamura, Shoji; Iwamoto, Osamu; Harada, Hideo; Katabuchi, Tatsuya*; Igashira, Masayuki*; Hori, Junichi*
no journal, ,
In J-PARC/MLF/ANNRI facility, new data acquisition system is now on development conforming to neutron total cross-section measurement system development. As neutron total cross-section measurement can perform with neutron capturing cross-section measurement, unified data acquisition system for total and capturing cross-section measurement have great benefits to reduce both analyzing burden and programing bug. This presentation will report on the development of data acquisition system for Ge detectors system in ANNRI. This presentation is as part of nuclear system research and development project "R&D for accuracy improvement of neutron nuclear data on minor actinides".
Seki, Yohji; Ezato, Koichiro; Suzuki, Satoshi; Yokoyama, Kenji; Yamada, Hirokazu; Hirayama, Tomoyuki
no journal, ,
JAEA is in charge of manufacturing a high heat flux (HHF) component, so-called "Outer vertical targets" in ITER divertor. The plasma facing units (PFUs) of the ITER divertor are subjected to HHF from plasma. The tungsten (W) armor tiles are metallurgically bonded onto cooling tubes made of copper alloy to achieve sufficient heat removal capability. Targets of R&D for full-W divertor are (1) to manufacture of full-scale PFU and (2) to demonstrate a durability of a heat removal capability. In the R&D through the manufacturing full-scale prototype PFU, JAEA demonstrated durability of heat removal capability of W armor tiles for HHF testing of 5000 
10 MW/m
and 1000 20 MW/m. After the HHF testing, gaps of about 0.5 mm between the W tiles decreased by about 
because the W tile was deformed by plastic strain. This paper reports deformation of shape on W surface in detail.
Yamada, Susumu; Machida, Masahiko; Watanabe, Masahisa
no journal, ,
no abstracts in English
Ando, Masami; Tanigawa, Hiroyasu; Kurotaki, Hironori
no journal, ,
Reduced activation ferritic/martensitic steel (RAFM) is the most promising candidate for the blanket structural material in DEMO fusion reactor. Void swelling behavior as well as mechanical properties change under high dose fusion neutron irradiation is very important issue on R&D of RAFM steels (F82H). The purposes of this study are to investigate the void swelling behavior with F82H IEA, Mod-3 and BA07 heats after multi-ion-irradiation and to confirm the peak swelling temperature. From results of microstructure observation for F82H Mod-3 and BA07 heats at 470C by multi-ion beam irradiation, cavities are observed from 0.8 to 1.2
m (damage level 
20 dpa) from an irradiation surface at 470C irradiated specimen. On the other hand, few cavities are observed in same region at 400C irradiation. This result shows that a swelling peak temperature with F82H weldments by ion irradiation will be also around 470C.
Tanigawa, Hiroyasu; Sakasegawa, Hideo; Hirose, Takanori; Kato, Yutai*
no journal, ,
Reduced activation ferritic/martensitic steel, F82H, is the first candidate DEMO blanket structural material, and the preparation of high dose irradiation database is underway. 87 dpa irradiation was completed and post irradiation tensile tests were conducted at the irradiation temperature. The results of the tensile test and fractography on 300C irradiated specimens will be reported.
Park, C.-H.; Kondo, Masatoshi*; Nozawa, Takashi; Tanigawa, Hiroyasu
no journal, ,
no abstracts in English
Yamada, Tomonori; Daido, Hiroyuki; Kawamura, Hiroshi; Shimada, Yoshinori*
no journal, ,
no abstracts in English
Ebine, Masumi; Nakamura, Tatsuya; To, Kentaro; Honda, Katsunori; Birumachi, Atsushi; Sakasai, Kaoru
no journal, ,
The center of gravity method is developed for a two-dimensional scintillator neutron detector for a protein diffractometer in the J-PARC/MLF. Details of the FPGA-based digital signal processing circuit and the detector performances are presented.
-ray irradiationMotooka, Takafumi; Nagaishi, Ryuji; Yamagishi, Isao
no journal, ,
We conducted ray irradiation test using simulated carbonate slurry to obtain the basic knowledge of the cause of stagnant water over the High Integrity Container. We observed a rise in water level, air bubbles in the slurry, a supernatant when the carbonate slurry with 95 g/L density was irradiated by ray at 8.5 kGy/h. The cause of the rise in water level was regarded as the volume expansion by the gas retention in the carbonate slurry.