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Journal Articles

Simulation of the self-propagating hydrogen-air premixed flame in a closed-vessel by an open-source CFD code

Thwe Thwe, A.; Terada, Atsuhiko; Hino, Ryutaro; Nagaishi, Ryuji; Kadowaki, Satoshi

Journal of Nuclear Science and Technology, 59(5), p.573 - 579, 2022/05

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

The simulations of the combustion of self-propagating hydrogen-air premixed flame are performed by an open-source CFD code. The flame propagation behavior, flame radius, temperature and pressure are analyzed by varying the initial laminar flame speed and grid size. When the initial laminar speed increases, the thermal expansion effects become strong which leads the increase of flame radius along with the increase of flame surface area, flame temperature and pressure. A new laminar flame speed model derived previously from the results of experiment is also introduced to the code and the obtained flame radii are compared with those from the experiments. The formation of cellular flame fronts is captured by simulation and the cell separation on the flame surface vividly appears when the gird resolution becomes sufficiently higher. The propagation behavior of cellular flame front and the flame radius obtained from the simulations have the reasonable agreement with the previous experiments.

Journal Articles

Gamma detector response simulation inside the pedestal of Fukushima Daiichi Nuclear Power Station

Riyana, E. S.; Okumura, Keisuke; Terashima, Kenichi; Matsumura, Taichi; Sakamoto, Masahiro

Mechanical Engineering Journal (Internet), 7(3), p.19-00543_1 - 19-00543_8, 2020/06

Journal Articles

Proposal of benchmark problem of thermal striping phenomena in planar triple parallel jets tests for fundamental code validation in sodium-cooled fast reactor development

Kobayashi, Jun; Tanaka, Masaaki; Ohno, Shuji; Ohshima, Hiroyuki; Kamide, Hideki

Proceedings of 16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-16) (USB Flash Drive), p.6664 - 6677, 2015/08

Numerical simulation is recognized an essential tool for the physical phenomena analysis and plant design study of a sodium-cooled fast reactor (SFR). In order to enhance credibility of the numerical results in the activities for plant design by using numerical simulations, it is recognized that verification and validation (V&V) process is very important. In this study, experiments for planar triple parallel jets mixing phenomena conducted in JAEA were proposed as benchmark problems for the code validation in the area of thermal striping study in the SFR development.

Journal Articles

Technetium separation for future reprocessing

Asakura, Toshihide; Hotoku, Shinobu; Ban, Yasutoshi; Matsumura, Masakazu; Morita, Yasuji

Journal of Nuclear and Radiochemical Sciences, 6(3), p.271 - 274, 2005/12

Tc extraction and separation experiments were performed basing on PUREX technique with using spent UO$$_{2}$$ fuel with burn-up of 44 GWd/t. The experimental results were examined with performing calculations by a simulation code ESSCAR (Extraction System Simulation Code for Advanced Reprocessing). It was demonstrated that Tc can be almost quantitatively extracted from a dissolver solution and that Tc can also be almost quantitatively recovered by scrubbing. Further, it was clearly presented from the calculation results of ESSCAR that the extraction mechanism of Tc is dominated by the synergistic effect of Zr and U.

Journal Articles

Simulation codes of chemical separation process of spent fuel reprocessing; Tool for process development and safety research

Asakura, Toshihide; Sato, Makoto; Matsumura, Masakazu; Morita, Yasuji

JAERI-Conf 2005-007, p.345 - 347, 2005/08

This paper reviews the succeeding development and utilization of Extraction System Simulation Code for Advanced Reprocessing (ESSCAR). From the viewpoint of development, more tests with spent fuel and calculations should be performed with better understanding of the physico-chemical phenomena in a separation process. From the viewpoint of process safety research on fuel cycle facilities, it is important to know the process behavior of a key substance; being highly reactive but existing only trace amount.

Journal Articles

Gyrokinetic simulations of tokamak micro-turbulence including kinetic electron effects

Idomura, Yasuhiro; Tokuda, Shinji; Kishimoto, Yasuaki

Journal of Plasma and Fusion Research SERIES, Vol.6, p.17 - 72, 2004/00

A global gyrokinetic toroidal particle code for a 3D nonlinear simulation (GT3D) has been developed for a comprehensive study of the ion and electron anomalous transport arising from the ion temperature gradient driven - trapped electron mode (ITG-TEM) turbulence in tokamak plasmas. In the preliminary linear ITG-TEM calculations, basic properties of ITG-TEM modes are confirmed. Adding trapped electrons not only increases the growth rate of the ITG mode, but also produces another unstable electron mode, the TEM mode, which is unstable even at $$eta_i = 0$$. The dominant mode changes from the ITG mode to the TEM mode depending on $$k_theta$$ and $$eta_i$$. In linear benchmark calculations using Cyclone base case parameters, eigenfrequencies obtained from GT3D, GTC(PPPL-UCI) and FULL(PPPL) show reasonable quantitative agreement.

Journal Articles

An EGS4 user code developed for design and optimization of $$gamma$$-ray detection systems

Oishi, Tetsuya; Tsutsumi, Masahiro; Sugita, Takeshi*; Yoshida, Makoto

Journal of Nuclear Science and Technology, 40(6), p.441 - 445, 2003/06

 Times Cited Count:1 Percentile:10.94(Nuclear Science & Technology)

An EGS4 user code has been developed to design and optimize $$gamma$$ ray detection systems for several types of radiation sources. The code is fundamentally based on the PRESTA-CG, which is improved on the electron transport in the EGS4 and specialized for the utilization of a combinatorial geometry (CG) method. The main additional functions in the present user code are classified into two parts of the definition of radiation sources and the transport of photons. The developed user code was applied to two types of detection systems in order to demonstrate its availability. As the result, it was found that the present code allows the detailed response analysis of complicated detection systems for several sources with just a simple handling.

Journal Articles

Detailed dose assessment for the heavily exposed workers in the Tokai-mura criticality accident

Endo, Akira; Yamaguchi, Yasuhiro; Takahashi, Fumiaki

Radiation Risk Assessment Workshop Proceedings, p.151 - 156, 2003/00

We have developed a new system using numerical simulation technique for analyzing dose distribution in various postures by neutron, photon and electron exposures. The system consists of mathematical human phantoms with movable arms and legs and Monte Carlo codes MCNP and MCNPX. This system was applied to the analysis of dose distribution for the heavily exposed workers in the Tokai-mura criticality accident. The paper describes the simulation technique employed and a summary of the dose analysis.

Journal Articles

Extraction behavior of TRU elements in the nuclear fuel reprocessing

Hotoku, Shinobu; Asakura, Toshihide; Mineo, Hideaki; Uchiyama, Gunzo

Journal of Nuclear Science and Technology, 39(Suppl.3), p.313 - 316, 2002/11

no abstracts in English

Journal Articles

Simulation studies of plasma initiation and disruption in JT-60U

Senda, Ikuo*; Shoji, Teruaki; Tsunematsu, Toshihide; Matsukawa, Makoto; Ushigusa, Kenkichi

Nucl. Eng. Des., 45(1), p.15 - 29, 1999/00

no abstracts in English

Journal Articles

RELAP5/MOD3 analysis of a ROSA-IV/LSTF loss-of-RHR experiment with a 5% cold leg break

C.J.Choi*; Nakamura, Hideo

Annals of Nuclear Energy, 24(4), p.275 - 285, 1997/00

 Times Cited Count:7 Percentile:52.88(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Application of simplified condensation model to PWR LBLOCA transient analysis with TRAC-PF1 code

; Murao, Yoshio

Journal of Nuclear Science and Technology, 33(4), p.290 - 297, 1996/04

 Times Cited Count:3 Percentile:32.81(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Proceedings of the 9th Topical Meeting on Nuclear Code Development; November 9$$sim$$10, 1995, JAERI, Tokai, Japan

; Research Committee on Reactor Physics

JAERI-Conf 96-002, 160 Pages, 1996/02

JAERI-Conf-96-002.pdf:7.38MB

no abstracts in English

Journal Articles

Development of the code system ACCEL for accelerator based transmutation research

; Sasa, Toshinobu; Takada, Hiroshi; Takizuka, Takakazu

Proc. of 2nd Int. Conf. on Accelerator-Driven Transmutation Technologies and Applications, 1, p.668 - 674, 1996/00

no abstracts in English

Journal Articles

Transport calculation codes and cross section libraries

Mori, Takamasa; Kosako, Kazuaki*

Purazuma, Kaku Yugo Gakkai-Shi, 71(12), p.1212 - 1219, 1995/12

no abstracts in English

Journal Articles

Applicability of REFLA/TRAC code to a small-break LOCA of PWR

Onuki, Akira; ; Murao, Yoshio

Journal of Nuclear Science and Technology, 32(3), p.245 - 256, 1995/03

 Times Cited Count:1 Percentile:17.59(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Improvement of pressure drop caluculation model in TRAC-PF1 code

; Abe, Yutaka*; Onuki, Akira; Murao, Yoshio

JAERI-Data/Code 94-006, 40 Pages, 1994/07

JAERI-Data-Code-94-006.pdf:1.26MB

no abstracts in English

JAEA Reports

Development of REFLA/TRAC code for engineering work station

Onuki, Akira; ; Murao, Yoshio

JAERI-M 94-026, 60 Pages, 1994/03

JAERI-M-94-026.pdf:1.81MB

no abstracts in English

36 (Records 1-20 displayed on this page)