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Sugawara, Takanori; Nishihara, Kenji; Tazawa, Yujiro; Tsujimoto, Kazufumi
no journal, ,
This presentation shows fabrication and test results of a testing facility for fuel cooling that is a component of the testing facility for remote-handling of highly-radioactive MA fuels in the transmutation physics experimental facility (TEF-P) planned in the J-PARC. Evaluation formula of pressure drop and temperature increase used in the design of TEF-P was validated by the test, and, feasibility of cooling concept was confirmed.
Yokoyama, Kenji; Yamamoto, Akio*
no journal, ,
no abstracts in English
-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.
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
Matsuda, Norihiro; Sato, Tatsuhiko; Niita, Koji*; Suyama, Kenya
no journal, ,
no abstracts in English
Tanigawa, Hisashi; Gwon, H.; Kawamura, Yoshinori
no journal, ,
JAEA is developing a water-cooled ceramic breeder blanket. For the blanket strength and pressure integrity are assessed. The largest stress appears in the first wall region due to the surface heat and neutron loads. Under conditions with the thermal loads and cooling water pressure, stress in the first wall is analyzed with reference to ASME Boiler and Pressure Vessel Code. Limitations related to the primary/secondary stresses and strain are considered. Material data necessary for the assessment is summarized, and then status of preparation is studied for a structural material of reduced activation ferritic/martensitic steel, F82H. The summarized date of F82H is compared with standardized 9Cr-1Mo-V.
Amano, Katsunori; Enuma, Yasuhiro; Futagami, Satoshi; Ushiki, Hiroshi*; Kawamura, Masaya*; Ichihara, Takashi*
no journal, ,
no abstracts in English
Ishikawa, Makoto; Yokoyama, Kenji; Numata, Kazuyuki; Maruyama, Shuhei; Takeda, Toshikazu*
no journal, ,
By utilizing the MA-related measurement data, a study to adjust the JENDL-4.0-based cross sections was performed. As a result, it was obtained that the uncertainty of MA-related reactor core parameters induced from the nuclear data uncertainty could be greatly reduced.
Ikeda, Yoshitaka; JT-60SA Team
no journal, ,
no abstracts in English
Takamatsu, Kuniyoshi; Matsumoto, Tatsuya*; Morita, Koji*
no journal, ,
After Fukushima Daiichi nuclear disaster by TEPCO, a cooling system to prevent core damage became more important from the perspective of defense in depth. Therefore, a new, highly efficient RCCS with passive safety features without a requirement for electricity and mechanical drive is proposed. Employing the air as the working fluid and the ambient air as the ultimate heat sink, the new RCCS design strongly reduces the possibility of losing the heat sink for decay heat removal. The RCCS can always stably and passively remove a part of the released heat at the rated operation and the decay heat after reactor shutdown. Specifically, emergency power generators are not necessary and the decay heat can be passively removed for a long time, even forever if the heat removal capacity of the RCCS is sufficient. Moreover, we can also define the experimental conditions on radiation and natural convection for the scale-down heat removal test facility.
Mimura, Ryuji; Yokozuka, Yuta; Nemoto, Koichi; Shiraishi, Kunio
no journal, ,
no abstracts in English
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.
Ishimi, Akihiro; Katsuyama, Kozo; Akasaka, Naoaki; Misawa, Susumu*
no journal, ,
no abstracts in English