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Oral presentation

Irradiation experiments of simulated carbonate slurry in HIC, 2; Gas retention behavior of simulated carbonate slurry under $$gamma$$-ray irradiation

Motooka, Takafumi; Nagaishi, Ryuji; Yamagishi, Isao

no journal, , 

We conducted $$gamma$$ 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 $$gamma$$ 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.

Oral presentation

Study on rapid analysis of the radioactive tritium in groundwater into the Fukushima-1 Nuclear Power Plant, 1; Applicability confirmation of the tritium column

Sasaki, Takayuki*; Akimoto, Yuji*; Seki, Kotaro; Nagano, Misato*; Ishimori, Kenichiro; Ueno, Takashi; Kameo, Yutaka

no journal, , 

no abstracts in English

Oral presentation

Uncertainty of criticality analysis of UO$$_{2}$$-concrete system under randomization

Ueki, 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.

Oral presentation

2-d scintillation detector for neutron protein diffractometer in J-PARC, 2; FPGA-based center of gravity circuit for a photon counting detector

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.

Oral presentation

Applicability study of Friction-Stir Process on CuCrZr-alloy

Hamaguchi, Dai; Morisada, Yoshiaki*; Fujii, Hidetoshi*; Tanigawa, Hiroyasu; Ozawa, Kazumi

no journal, , 

Friction-Stir Process (FSP) were applied to OFCCu and ITER-Gr CuCrZr cooling pipe in order to evaluate the applicability of the process to mechanically strengthening pure-Cu and possible structural improvement on CuCrZr alloy. Former study revealed that the achievement of very fine grain structure at certain rotational speed and also the hardness increase to about 1.5 time higher within the stir-zone but also relatively shallow stir-zone depth compared to a length of the pin and rapid void formations. In order to avoid this phenomenon, compulsory cooling with liquid Co$$_{2}$$ during the process was introduced, and the results showed the absence of void formation at relatively lower rational speed of around 300 RPM and also maintaining the effective stir-zone to relatively higher rotational speed compared to non-cooling tests. Similar FSP tests with compulsory cooling were also applied to ITER-Gr CuCrZr cooling pipe for divertor application. The detail will be reported on the presentation.

Oral presentation

Simulation of TVF glass melter operation with forming of thick sediments composed of platinum group elements

Asahi, Yoshimitsu; Nakajima, Masayoshi; Ayame, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Probabilistic risk assessment method development for high temperature gas-cooled reactors

Sato, Hiroyuki; Nishida, Akemi; Furuya, Osamu*; Muramatsu, Ken*; Itoi, Tatsuya*; Takada, Tsuyoshi*; Tanabe, Masayuki*; Yamamoto, Tsuyoshi*

no journal, , 

The proposed research aims to establish a probabilistic risk assessment method for high temperature gas-cooled reactors fully utilizing their design and safety characteristics. The method will be developed for the incorporation of a graded approach as well as a component failure evaluation model using the operation and maintenance experience in the high temperature engineering test reactor into an accident frequency analysis. In addition, a source term evaluation method considering failures in core graphite components will be developed.

Oral presentation

Present status and future prospects of the MVP code

Nagaya, Yasunobu

no journal, , 

no abstracts in English

Oral presentation

Necessity of fundamental experiments for evaluating two-phase flow behavior in a RCIC system of the Fukushima Dai-ichi Nuclear Power Plant No.2 unit

Takase, Kazuyuki; Yoshida, Hiroyuki; Okada, Hidetoshi*; Koikari, Soji*; Tsuzuki, Nobuyoshi*

no journal, , 

no abstracts in English

Oral presentation

Remote technology development for function advancement of research base, 3; Development of robot simulator for nuclear emergency response

Suzuki, Kenta; Isowa, Mitsuru; Kawabata, Kuniaki; Torii, Tatsuo

no journal, , 

no abstracts in English

Oral presentation

Source term estimation based on environmental monitoring data

Nagai, Haruyasu

no journal, , 

no abstracts in English

Oral presentation

Behavior of fission products in Fukushima Daiichi NPP under severe accidents overview of FP behavior under accidents and approaches toward advanced source term analysis, 4; Fundamental aspects of FP behavior and challenge toward further research subjects

Osaka, Masahiko; Miwa, Shuhei; Nakajima, Kunihisa; Di Lemma, F. G.; Suzuki, Chikashi; Nagase, Fumihisa

no journal, , 

Chemical behavior of fission product (FP) are of crucial importance for the improvement of FP release and transport behavior under the severe accident. Fundamental research on FP sorption behavior and evaluation of FP chemical composition in the reactor are introduced.

Oral presentation

Irradiation experiments of simulated carbonate slurry in HIC, 3; Studies on radiolysis behavior of simulated carbonate slurry

Nagaishi, Ryuji; Motooka, Takafumi; Yamagishi, Isao; Inoue, Masao; Matsumura, Taichi

no journal, , 

no abstracts in English

Oral presentation

Radioactive particles discovered in the vicinity of Fukushima Nuclear Plant

Satou, Yukihiko*; Sueki, Keisuke*; Sasa, Kimikazu*; Minowa, Haruka*; Yoshikawa, Hideki; Fujiwara, Kenso; Nakama, Shigeo

no journal, , 

We separated radioactive particles from soil and dust sample obtained around Fukushima Dai-ichi Nuclear Power Plant. Separated all particles can categorize unit-1 and unit-2 origin. And $$^{125}$$Sb was detected from unit-1 origin samples. Moreover, radioactive particle was made up 80 weight percent silica.

Oral presentation

Examination of the decreasing effect on internal exposure by sheltering, 2; Sensitivity analysis

Hirouchi, Jun; Takahara, Shogo; Watanabe, Masatoshi; Munakata, Masahiro

no journal, , 

no abstracts in English

Oral presentation

Examination of the decreasing effect on internal exposure by sheltering, 1; Literature search on variation factors

Watanabe, Masatoshi; Takahara, Shogo; Hirouchi, Jun; Munakata, Masahiro

no journal, , 

no abstracts in English

Oral presentation

Integration of knowledge management support system for the decommissioning of nuclear facilities, 4; Knowledge base development based on knowledge engineering method

Kato, Yasuaki; Yanagihara, Satoshi*; Iguchi, Yukihiro; Tezuka, Masashi; Koda, Yuya

no journal, , 

no abstracts in English

Oral presentation

Study on the monitoring of impurities in sodium by plugging meter

Suzuki, Masashi; Yoshida, Eiichi; Imamura, Hiroaki; Amano, Katsunori; Shimoyama, Kazuhito

no journal, , 

no abstracts in English

Oral presentation

Cross section adjustment methods based on minimum variance unbiased estimate

Yokoyama, Kenji; Yamamoto, Akio*

no journal, , 

no abstracts in English

249 (Records 1-20 displayed on this page)