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Oral presentation

Effect of salt/bitumen ratio on properties of bituminized waste in contact with water

Irisawa, Keita; Osone, Osamu; Meguro, Yoshihiro

no journal, , 

no abstracts in English

Oral presentation

A Rate limiting step of HLW glass corrosion under near saturated condition

Maeda, Toshikatsu; Bamba, Tsunetaka*; Omori, Hiroyuki; Yamaguchi, Tetsuji

no journal, , 

no abstracts in English

Oral presentation

Measurement examination of Pu content in radioactive waste with portable waste assay system, 1

Ono, Yosuke; Yokoyama, Hitoshi*; Watanabe, Naoki; Miyauchi, Masami; Shuji, Yoshiyuki; Shiota, Yukito; Daidai, Misao

no journal, , 

no abstracts in English

Oral presentation

Extrusion behavior of bentonite buffer, 1; Behavior grasp by long-term experiment

Matsumoto, Kazuhiro; Fujita, Tomoo

no journal, , 

no abstracts in English

Oral presentation

Extrusion behavior of bentonite buffer, 2; Analytical study on extrusion behavior

Takaji, Kazuhiko*; Inaba, Kaoru*; Matsumoto, Kazuhiro; Fujita, Tomoo

no journal, , 

no abstracts in English

Oral presentation

Basic test for making Waste package for Spent resin disposal

Otani, Hiroshi; Higashiura, Norikazu; Mizui, Hiroyuki; Endo, Nobuyuki*; Katagiri, Genichi*; Oshio, Tadashi*; Ogawa, Hideo*

no journal, , 

no abstracts in English

Oral presentation

Support for nuclear human resource self-development by Asian countries

Sawada, Makoto; Yabuuchi, Yukiko; Arai, Nobuyoshi; Kanaizuka, Seiichi; Yamashita, Kiyonobu; Nakagawa, Norio; Murakami, Hiroyuki; Nakamura, Kazuyuki

no journal, , 

Outline of International Nuclear Human Resource Development Program (Instructor Training Program: ITP), which is sponsored by MEXT, for Asian ten countries by JAEA will be reported. ITP consists of three major activities, i.e. Instructor Training Course, Follow-up Training Course and Nuclear Safety seminars. 16 years training activity from 1996 at JAEA and Asian countries has developed around 160 of instructors and more than 2,000 of trainees in Asian countries.

Oral presentation

Alteration of the interface between bentonite and carbon steel under hyper alkaline conditions

Sakamaki, Keiko; Iwata, Hajime*; Utsunomiya, Satoshi*

no journal, , 

no abstracts in English

Oral presentation

Corrosion behavior of zircaloy in deionized water at around 100$$^{circ}$$C under anaerobic condition

Chiba, Noriaki; Maeda, Toshikatsu; Yamaguchi, Tetsuji

no journal, , 

no abstracts in English

Oral presentation

Capillary electrophoresis with laser-induced fluorescent detection method using highly emissive probes for analysis of uranium in radioactive wastes

Haraga, Tomoko; Sato, Yoshiyuki*; Shibukawa, Masami*; Kameo, Yutaka; Takahashi, Kuniaki; Saito, Shingo*

no journal, , 

JP, 2012-034711   Patent publication (In Japanese)

Actinides (Th, U, Np, Pu, Am, Cm) are important nuclides for the analysis of radioactive wastes from nuclear facilities. In order to achieve simple and rapid analysis of actinides, capillary electrophoresis-laser-induced fluorescent detection method (CE-LIF) is one of the potential candidates. In this study, new emissive probes of uranium suitable for CE-LIF were developed. The detection and separation of uranyl ions were examined using several new emissive complexing probes, each of which possessed a fluorophore and a different chelating moiety. Using acyclic tetradentate probes, the highly sensitive fluorescent detection of uranyl ions was successfully achieved. The detection limit of mid-ppt levels was determined.

Oral presentation

Characterization for decommission of uranium handling facility, 1; The Feature of the distribution of nuclide in Ningyo-Toge Environmental Engineering Center

Tanaka, Yoshio; Hata, Haruhi; Yokoyama, Kaoru; Tokuyasu, Takashi; Kaneda, Koji; Sugitsue, Noritake

no journal, , 

For decommission of uranium handling facilities, it is important to characterize the details of the facilities, which are the distribution of nuclide, the existence of hazardous waste and so on. The report mainly shows the character of distribution of uranium and its isotopes.

Oral presentation

Characterization for decommission of uranium handling facility, 2; The Simple identification method of RU and NU using a $$gamma$$ ray

Tanaka, Yoshio; Hata, Haruhi; Yokoyama, Kaoru; Tokuyasu, Takashi; Kaneda, Koji; Sugitsue, Noritake

no journal, , 

This report shows the classification method into NU group or RU group by passive $$gamma$$ ray assay. Moreover, we discuss the practicality of the method.

Oral presentation

Measurement technology of uranium quantity in uranium waste, 3; Evaluation of relative error and detection limit using simulated waste

Yokoyama, Kaoru; Sugitsue, Noritake; Suzuki, Yasuo*; Muroi, Masayuki*; Nakatsuka, Yoshiaki; Ishii, Kazuto*

no journal, , 

The computational technique using the $$gamma$$ ray of two energies emitted from $$^{238}$$U progeny nuclide ($$^{rm 234m}$$Pa) was developed to determine uranium quantity in heterogeneous waste. In this study, the relative error and detection limit evaluation results using the simulated wastes are reported.

Oral presentation

Development of PRW technology for ODS steel, 13-2; Strength evaluation test with artificially-defected test pieces

Seki, Masayuki; Kihara, Yoshiyuki; Tsukada, Tatsuya*; Motoki, Kazuhiko*; Hirako, Kazuhito*

no journal, , 

no abstracts in English

Oral presentation

Study for light water reactor with rock-like oxide fuel, 1; Scenario for direct disposal of rock-like oxide fuel

Nishihara, Kenji; Iwamura, Takamichi*; Akie, Hiroshi; Shirasu, Noriko

no journal, , 

Use of Rock-like oxide (ROX) fuel is proposed for the purpose of reduction of plutonium amount in the case of gradually stopping nuclear power generation without introducing fast breeder reactors. In this study, the mass flow and repository of three scenarios that is once-through, Pu-thermal and ROX, was analysed. As the result, amount and attractiveness as nuclear weapon of Pu was decreased in the ROX scenario in comparison with the once-through scenario, although the repository size was not reduced.

Oral presentation

Development of Level-1 PSA method for sodium-cooled fast reactors, 6; Failure probability evaluation method of natural circulation heat removal function

Yamano, Hidemasa; Sakai, Takaaki; Kurisaka, Kenichi

no journal, , 

The characteristics of fast reactor safety is that it has passive safety function such as natural circulation heat removal. Hence, it is necessary to evaluate the reliability of the passive safety function and to estimate probability of the functional failure in order to perform level 1 PSA on a plant. This paper reports sensitivity analysis and failure probability evaluation in 2011 to construct failure probability evaluation methodology on natural circulation decay heat removal.

Oral presentation

OECD/NEA ROSA-2 Project, 2; Cooldown experiment by natural circulation with loss of coolant in secondary side of steam generator

Ishigaki, Masahiro; Watanabe, Tadashi*; Takeda, Takeshi; Nakamura, Hideo

no journal, , 

no abstracts in English

Oral presentation

Study of thermal aging embrittlement on stainless steels used Fugen nuclear reactor

Nogiwa, Kimihiro; Onitsuka, Takashi; Takeuchi, Tomoaki; Abe, Teruyoshi; Sakakibara, Yasuhide; Horie, Kaoru; Nakamura, Takahisa

no journal, , 

no abstracts in English

Oral presentation

In situ experiment for redox buffer capacity with backfill in the subsurface environment

Murakami, Hiroaki; Amano, Yuki; Amamiya, Hiroki; Sasaki, Yoshito; Iwatsuki, Teruki; Yoshikawa, Hideki

no journal, , 

no abstracts in English

Oral presentation

Improvement of giant dipole resonance cross section in the PHITS code

Noda, Shusaku; Hashimoto, Shintaro; Sato, Tatsuhiko; Fukahori, Tokio; Chiba, Satoshi; Niita, Koji*

no journal, , 

The author has improved the photonuclear cross section embedded in the PHITS code.

270 (Records 1-20 displayed on this page)