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Journal Articles

Visualizing an ignition process of hydrogen jets containing sodium mist by high-speed imaging

Doi, Daisuke; Seino, Hiroshi; Miyahara, Shinya*; Uno, Masayoshi*

Journal of Nuclear Science and Technology, 56(6), p.521 - 532, 2019/06

JAEA Reports

Preliminary combustion analyses using OpenFOAM

Thwe, T. A.; Terada, Atsuhiko; Hino, Ryutaro

JAEA-Technology 2018-012, 45 Pages, 2019/01

JAEA-Technology-2018-012.pdf:4.34MB

Under long-term storage of nuclear wastes including low- and high-level wastes, hydrogen can be spontaneously generated from corrosion of metal wastes and container wall itself, and from radiolysis of water in the waste. For the sake of hydrogen safety and the risk reduction of environmental contamination, we have started to investigate the behavior and characteristics of hydrogen combustion and explosion in waste vessel. In this report, we performed numerical simulation to investigate the characteristics of methane combustion by applying OpenFOAM. For combustion scenario, FireFoam solver with LES frame was used. As the results, the average temperature increased when the container height and inlet size increased. The simulation of gas diffusion by FireFoam results showed that helium diffused faster than hydrogen and methane. By XiFoame solver, the simulation was performed to obtain flame propagation radius for hydrogen-air premixed flame.

Journal Articles

Multi-dimensional numerical investigation of sodium spray combustion; Benchmark analysis of SNL T3 experiment

Sonehara, Masateru; Aoyagi, Mitsuhiro; Uchibori, Akihiro; Takata, Takashi; Ohshima, Hiroyuki; Clark, A. J.*; Denman, M. R.*

Proceedings of 11th Korea-Japan Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-11) (Internet), 5 Pages, 2018/11

no abstracts in English

Journal Articles

ETSON-MITHYGENE benchmark on simulations of upward flame propagation experiment in the ENACCEF2 experimental facility

Bentaib, A.*; Chaumeix, N.*; Grosseuvres, R.*; Bleyer, A.*; Gastaldo, L.*; Maas, L.*; Jallais, S.*; Vyazmina, E.*; Kudriakov, S.*; Studer, E.*; et al.

Proceedings of 12th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics, Operation and Safety (NUTHOS-12) (USB Flash Drive), 11 Pages, 2018/10

Journal Articles

Fluid dynamic analysis on hydrogen deflagration in vertical flow channel with annular obstacles

Matsumoto, Toshinori; Sato, Masatoshi; Sugiyama, Tomoyuki; Maruyama, Yu

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 6 Pages, 2017/07

Journal Articles

Tritium distribution in the first wall of JT-60U

Masaki, Kei; Sugiyama, Kazuyoshi*; Tanabe, Tetsuo*; Goto, Yoshitaka*; Tobita, Kenji; Miyo, Yasuhiko; Kaminaga, Atsushi; Kodama, Kozo; Arai, Takashi; Miya, Naoyuki

Nippon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.130 - 139, 2003/06

no abstracts in English

Journal Articles

Tritium distribution in JT-60U W-shaped divertor

Masaki, Kei; Sugiyama, Kazuyoshi*; Tanabe, Tetsuo*; Goto, Yoshitaka*; Miyasaka, Kazutaka*; Tobita, Kenji; Miyo, Yasuhiko; Kaminaga, Atsushi; Kodama, Kozo; Arai, Takashi; et al.

Journal of Nuclear Materials, 313-316, p.514 - 518, 2003/03

 Times Cited Count:48 Percentile:4.65

Detailed tritium profiles on the JT-60U W-shaped divertor and first wall tiles were examined by Tritium Imaging Plate Technique (TIPT) and full combustion method. The tritium deposition image obtained by TIPT was consistent with the distribution measured by combustion method. The highest tritium concentration was 60 kBq/cm$$^{2}$$ at the dome top tile. However, deposition layer was not obviously observed on the dome top tile. The tritium concentration in the inner divertor target tile was lower (2 kBq/cm$$^{2}$$) even with the thick deposition layer of $$sim$$60 $$mu$$m. This tritium distribution can be explained by energetic triton particle loss due to ripple loss. According to the simulation using the OFMC code, 31% of the triton particles produced by D-D nuclear reaction is implanted deeply to the wall without fully losing the initial energy of 1 MeV.

JAEA Reports

Development of fire and explosion analysis code system -P2A- for HTGR hydrogen production system (Contract research)

Inaba, Yoshitomo; Nishihara, Tetsuo; Moriyama, Koichi*; Nakamura, Masashi*

JAERI-Data/Code 2002-014, 255 Pages, 2002/07

JAERI-Data-Code-2002-014.pdf:21.69MB

One of the most important safety design issues for an HTGR hydrogen production system is to ensure reactor safety against fire and explosion accidents in the hydrogen production plant because a large amount of combustible fluid is dealt with in the system. JAERI has the demonstration test plan to connect the hydrogen production system with the HTTR. In the plan, we considered effective measures against the fire and explosion accidents in the HTTR hydrogen production system, which were applicable to the HTGR hydrogen production system of a commercial base, and also developed the P2A code system to analyze event sequences and consequences in detail, on assumed fire and explosion accidents in the HTGR hydrogen production system and the HTTR hydrogen production system. The P2A can analyze the process of leakage, dispersion, ignition, and combustion including deflagration and detonation of the combustible fluid in the internal and external area of the reactor building. In this report, we describe the outline and the usage of the P2A, and the results of preliminary calculations.

Journal Articles

Analytical study on fire and explosion phenomena in HTTR hydrogen production system

Inaba, Yoshitomo; Nishihara, Tetsuo; Inagaki, Yoshiyuki

Proceedings of 14th Hydrogen Energy Conference (WHEC 2002) (CD-ROM), 9 Pages, 2002/06

The Japan Atomic Energy Research Institute (JAERI) has the demonstration test plan to connect a hydrogen production system by steam reforming of methane with the High Temperature engineering Test Reactor (HTTR). One of the most important safety design issues for the HTTR hydrogen production system is to ensure reactor safety against fire and explosion accidents. Therefore, we developed the P2A code system to analyze event sequences and consequences in detail, on assumed fire and explosion accidents in the HTTR hydrogen production system. It is possible that the P2A analyzes the process of leakage, dispersion and combustion including deflagration and detonation of the combustible fluid in the internal and external area of the reactor building. This paper describes the outline of the P2A and the results of preliminary calculations.

JAEA Reports

Determination of chlorine in graphite by combustion-ion chromatography

L.Chan*; Watanabe, Kazuo; Ito, Mitsuo

JAERI-Research 95-061, 13 Pages, 1995/09

JAERI-Research-95-061.pdf:0.52MB

no abstracts in English

Journal Articles

Development of spent solvent treatment process by submerged combustion technique

Uchiyama, Gunzo; Maeda, Mitsuru; Fujine, Sachio; *; *; *

Journal of Nuclear Science and Technology, 31(3), p.228 - 239, 1994/03

 Times Cited Count:8 Percentile:37.32(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of an advanced incineration technique to spent solvent treatment for improving the waste management

Uchiyama, Gunzo; Maeda, Mitsuru; *; Fujine, Sachio; *; *

Proceedings of 4th International Conference on Nuclear Fuel Reprocessing and Waste Management; RECOD '94, Vol.3, 0, p.1 - 15, 1994/00

no abstracts in English

JAEA Reports

Conceptual design study and evaluation of an advanced treatment process applying a submerged combustion technique for spent solvents

Uchiyama, Gunzo; Maeda, Mitsuru; Fujine, Sachio; *; *

JAERI-M 93-213, 204 Pages, 1993/10

JAERI-M-93-213.pdf:6.12MB

no abstracts in English

JAEA Reports

Combustion behavior of spent solvent in a submerged combustion process

Uchiyama, Gunzo; Maeda, Mitsuru; Fujine, Sachio; *; *

JAERI-M 93-191, 58 Pages, 1993/10

JAERI-M-93-191.pdf:2.23MB

no abstracts in English

Journal Articles

Ruthenium behavior in a submerged combustion process for treatment of spent solvent

*; Uchiyama, Gunzo; Fujine, Sachio; Maeda, Mitsuru

Proc. of the 3rd Int. Conf. on Nuclear Fuel Reprocessing and Waste Management,Vol. 2, p.775 - 780, 1991/00

no abstracts in English

Journal Articles

Technology development for environmental preservation by electron irradiation

Sato, Shoichi; Tokunaga, Okihiro; Arai, Hidehiko; Hashimoto, Shoji

Transactions of the American Nuclear Society, SUPPL.61, p.425 - 430, 1990/00

no abstracts in English

Journal Articles

Radiation treatment of combustion gases

Machi, Sueo; ; ; ; Kawakami, Waichiro; ; *; *; *

Radiation Physics and Chemistry, 9(1-3), p.371 - 388, 1977/03

no abstracts in English

Oral presentation

Numerical study on combustion processes of radioactive waste in an incinerator

Yanase, Shinichiro*; Sugitsue, Noritake; Ishimori, Yuu; Yokoyama, Kaoru; Ohara, Yoshiyuki; Takahashi, Nobuo; Rong, D.*; Takeda, Hiroshi*; Kochi, Toshinori*; Takami, Toshihiro*; et al.

no journal, , 

no abstracts in English

Oral presentation

Numerical investigation of sodium spray combustion test with SPHINCS code

Takata, Takashi; Ohshima, Hiroyuki; Denman, M. R.*; Clark, A. J.*

no journal, , 

As a collaboration on the field of advanced reactor modeling and simulation in Civil Nuclear Energy Research and Development Working Group (CNWG) between Japan Atomic Energy Agency (JAEA) and Sandia National Laboratories (SNL), information exchange of sodium combustion modeling and experimental data has been carried out. In the collaborative work, a benchmark analysis of Surtsey spray combustion experiments done by SNL has been conducted using SPHINCS code at JAEA and CONTAIN-LMR code at SNL. In this paper, the numerical result of SPHINCS code and the comparison between SPHINCS and CONTAIN-LMR codes are discussed. Furthermore, sensitivity analyses have also been carried out to investigate the influential factor on the experiments.

Oral presentation

Simplification of oxygen combustion process in OBT analysis

Fujiwara, Kenso; Kuwata, Haruka*; Misono, Toshiharu; Iijima, Kazuki

no journal, , 

Since various radionuclides including tritium was released into the ocean by the Fukushima Dai-ichi Nuclear Power Station accident, transfer of those to marine products has been concerned. In case of tritium, Organically Bound Tritium (OBT) was considered to be relatively important for the transfer due to its longer biological half-life. However, huge sequential treatment processes and a few weeks are needed to measure the concentration of each type of tritium. Therefore, simplification of the processes and reduction of the duration were required for the purpose of rapid analysis and obtaining more data on environmental monitoring.

Oral presentation

Approach to analysis of hydrogen combustion inside of radioactive waste vessels using CFD softwares based on an open source "OpenFOAM"

Thwe, T. A.; Terada, Atsuhiko; Hino, Ryutaro

no journal, , 

Since hydrogen is continuously generated and releases inside of high-level radioactive waste vessels, the awareness must be taken on the risk of hydrogen combustion and explosion. In hydrogen safety management, besides the experimental investigations, CFD approaches in predictions of flame propagation phenomena are of important role. As an approach to analysis of hydrogen combustion inside of vessels, we used the open source software, OpenFOAM and performed the simulations for propagation of H$$_{2}$$-air premixed flame. A new laminar flame speed model deduced from H$$_{2}$$-air explosion experiments by T. Katsumi et al. [Nagaoka Univ. Tech.] was implemented in the XiFoam solver and reproduced the propagation of H$$_{2}$$-air flame. Flame radius obtained by simulation agreed with the experimental results within 0.005s. Wrinkle flame formation was observed when the flame propagated outwardly as in experiments.

21 (Records 1-20 displayed on this page)