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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

Socio-economic effects of the material science in JAERI

Yanagisawa, Kazuaki; Takahashi, Shoji*

Scientometrics, 78(3), p.505 - 524, 2008/10

 Times Cited Count:1 Percentile:71.44(Computer Science, Interdisciplinary Applications)

A socio-economic evaluation of Material Science (MS) of JAERI was made. The goal was to reveal the emphasized basic research fields (EBRF) of MS and to observe its socio-economic networking. High ranked keywords for the former and the number of co-authored papers for the latter were used along with many MS related papers. The obtained results are: (1) The EBRF of MS of JAERI were typically represented by the keywords of ion irradiation, actinides, etc., i.e., those having a strong relation to the nuclear field. Regarding actinides, the socio-economic networking between JAERI and PS occurred at the growth rate of 3-4% per 25 years, but 8% during the past 5 years. This implies that the research cooperation between the two was markedly enhanced. (2) The EBRF of MS between JAERI and 5 selected research bodies (SRB) represented by Tokyo University was directly compared and revealed that only 7 keywords as typically represented by neutron and accelerators. After overlapping, JAERI and SRB seem to be raising the national standard level.

JAEA Reports

Structural integrity of heavy liquid-metal target installed in spallation neutron facility, 4; Consideration by fracture mechanics of target container window

Ishikura, Shuichi*; Kogawa, Hiroyuki; Futakawa, Masatoshi; Kikuchi, Kenji; Haga, Katsuhiro; Kaminaga, Masanori; Hino, Ryutaro

JAERI-Tech 2003-093, 55 Pages, 2004/01

JAERI-Tech-2003-093.pdf:5.41MB

To estimate the structural integrity of the heavy liquid-metal (Hg) target used in a MW-class neutron scattering facility, static and dynamic stress behaviors due to the incident of a 1MW-pulsed proton beam were analyzed. In the analyses, two-type target containers with semi-cylindrical type and flat type window were used as analytical models of the structural analysis codes LS-DYNA. As a result, it is confirmed that the stress generated by dynamic thermal shock becomes the largest at the center of window, and the flat type window is more advantageous from the structural viewpoint than the semi-cylindrical type window. It was confirmed to erosion damage the target container by mercury's becoming negative pressure in the window and generating the cavitation by the experiment. Therefore, it has been understood that the point top of the window was in the compression stress field by the steady state thermal stress because of the evaluation from destroying the dynamic viewpoint for the crack in the generated pit and the pit point, and the crack did not progress.

Journal Articles

Modified quasi-steady-state method to evaluate the mean power profiles of nuclear excursions in fissile solution

Nakajima, Ken; Yamamoto, Toshihiro; Miyoshi, Yoshinori

Journal of Nuclear Science and Technology, 39(11), p.1162 - 1168, 2002/11

 Times Cited Count:3 Percentile:73.4(Nuclear Science & Technology)

A modified quasi-steady-state method has been developed to evaluate the mean power during a nuclear excursion in fissile solution. The original method used the critical equation based on the one-group theory to calculate the reactivity. However, the one-group approximation reduces the calculation accuracy and the geometrical buckling used in the critical equation is not applicable to complex geometries. Then, we have modified the method to use the feedback coefficients of reactivity. Although the modified method requires an external calculation to obtain the feedback coefficients, it is applicable to complex geometries and gives more accurate results than the one-group approximation. Moreover, a new method to calculate the boiling power has been developed. using the experimental data of a supercritical experiment facility, SILENE. Experimental analyses were conducted to validate the new method for supercritical xperiments using CRAC and TRACY. The results showed good agreements with the experiments.

JAEA Reports

Multi-dimensional numerical analyses for the IFMIF target jet flows

*; ; Nakamura, Hideo

JAERI-Research 98-022, 46 Pages, 1998/03

JAERI-Research-98-022.pdf:1.92MB

no abstracts in English

Journal Articles

Experimental and analytical studies on high-speed plane jet along concave wall simulating IFMIF Li target flow

Nakamura, Hideo; Ito, Kazuhiro*; Kukita, Yutaka*; *; ; Maekawa, Hiroshi; Katsuta, Hiroji

Journal of Nuclear Materials, 258-263, p.440 - 445, 1998/00

 Times Cited Count:7 Percentile:42.56

no abstracts in English

Journal Articles

Intercomparisons of benchmark calculations for the transmission of quasi-monoenergetic neutrons generated by 43- and 68-MeV protons through iron and concrete shield

Nakane, Yoshihiro; Nakashima, Hiroshi; Nakao, Noriaki*; Ueki, Kotaro*

Proc. of 3rd Workshop on Simulating Accelerator Radiation Environments (SARE3), p.334 - 342, 1997/00

no abstracts in English

Journal Articles

Confirmatory thermal-hydraulic analyses of safety design concept of a passive safety light water reactor JPSR

Araya, Fumimasa; *; Ochiai, Masaaki

Proc. of Post-SMiRT14 Int. Seminar 18, p.E1.26 - E1.32, 1997/00

no abstracts in English

Journal Articles

Fabrication of HIPped first wall panel for fusion experimental reactor and preliminary analyses for its thermo-mechanical test

Sato, Satoshi; Furuya, Kazuyuki; Kuroda, Toshimasa*; Kurasawa, Toshimasa; *; Hatano, Toshihisa; Takatsu, Hideyuki; Osaki, Toshio*

16th IEEE/NPSS Symp. on Fusion Engineering (SOFE '95), 1, p.202 - 205, 1996/00

no abstracts in English

Journal Articles

Three-dimensional numerical analysis of mixed convective heat transfer in a horizontal square channel with heated and cooled side walls

*; Kunugi, Tomoaki; *

Nippon Kikai Gakkai Rombunshu, B, 61(586), p.2228 - 2234, 1995/06

no abstracts in English

Journal Articles

Numerical analysis on thermal-hydraulics of ribbed fuel rods for HTGRs,II; A Case with 2 dimensional square ribs

Takase, Kazuyuki; Akino, Norio

Kikai Gakkai Ibaraki Koenkai Koen Rombunshu, 0, p.127 - 128, 1995/00

no abstracts in English

Journal Articles

Large eddy simulation of turbulent heat transfer in a concentric annulus

*; *; *; Kunugi, Tomoaki

Therm. Sci. Eng., 2(2), p.16 - 25, 1994/00

no abstracts in English

Journal Articles

Numerical and experimental study on heat transfer of an impinging turbulent plane jet with confined wall

Kunugi, Tomoaki; *; *

Heat Transfer in Turbulent Flows, 1993; HTD-Vol. 246, p.25 - 31, 1993/00

no abstracts in English

Journal Articles

Simulation code SAFE for analyzing transient solvent extraction behavior

Maeda, Mitsuru; Fujine, Sachio; *; *

Transactions of the American Nuclear Society, 66, p.78 - 80, 1992/11

no abstracts in English

Journal Articles

Accident analyses for a double-flat-core type HCLWR

Okubo, Tsutomu; Iwamura, Takamichi; *; *; Murao, Yoshio

6th Proc. of Nuclear Thermal Hydraulics, p.79 - 86, 1990/11

no abstracts in English

Journal Articles

Accident analyses for a double-flat-core type HCLWR

Okubo, Tsutomu; Iwamura, Takamichi; *; *; Murao, Yoshio

Transactions of the American Nuclear Society, 62, p.662 - 663, 1990/11

no abstracts in English

18 (Records 1-18 displayed on this page)
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